TY - JOUR
T1 - Iron content of haemoglobin in iron deficiency.
AU - BEUTLER, E.
JO - Nature
JF - Nature
Y1 - 1958///
VL - 181
SP - 837
EP - 838
SN - 0028-0836
AD - BEUTLER, E.: Argonne Cancer Res. Hosp., U.S. Atomic Energy Commission, Chicago, Ill.
N1 - Accession Number: 19581405220. Publication Type: Journal Article. Language: English. Registry Number: 7439-89-6.
N2 - Haemoglobin from the blood of normal and irondeficient rats and human subjects was purified and its iron content was estimated. Iron contents were almost identical, and it is suggested that " a defect in the haem synthesis appears to limit somehow the synthesis of globin."-F. E. Hytten.
KW - animal models
KW - blood
KW - composition
KW - deficiency
KW - haemoglobin
KW - iron
KW - mineral deficiencies
KW - synthesis
KW - man
KW - rats
KW - Homo
KW - Hominidae
KW - Primates
KW - mammals
KW - vertebrates
KW - Chordata
KW - animals
KW - eukaryotes
KW - Muridae
KW - rodents
KW - small mammals
KW - hemoglobin
KW - Animal Models of Human Nutrition (VV140)
KW - Nutrition Related Disorders and Therapeutic Nutrition (VV130)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=gha&AN=19581405220&site=ehost-live&scope=site
DP - EBSCOhost
DB - gha
ER -
TY - JOUR
T1 - Strontium-calciumdiscrimination by the human placenta.
AU - RIVERA, J.
JO - Nature
JF - Nature
Y1 - 1963///
VL - 200
SP - 269
EP - 270
SN - 0028-0836
AD - RIVERA, J.: U.S. Atomic Energy Commission, Health and Safety Lab., New York.
N1 - Accession Number: 19641402746. Publication Type: Journal Article. Language: English.
N2 - The extent of discrimination by the human placenta against Sr and in favour of Ca was estimated by studies of blood taken from the maternal and fetal sides of the placenta at birth. Serum was tested for stable Sr by neutron activation analysis. If it is assumed that the concentration of Ca in maternal and fetal serum is the same, the extent of discrimination is given by the ratio of the concentrations of stable Sr in fetal and maternal serum. In 15 tests means for Sr in µg per ml serum were for fetal blood 0.07 0.03 and for maternal blood 0.10±0.05. The mean ratio was 0.82±0.38. H. G. Jones.
KW - chemical analysis
KW - fetus
KW - placenta
KW - research
KW - techniques
KW - man
KW - Homo
KW - Hominidae
KW - Primates
KW - mammals
KW - vertebrates
KW - Chordata
KW - animals
KW - eukaryotes
KW - foetus
KW - studies
KW - Techniques and Methodology (ZZ900)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=gha&AN=19641402746&site=ehost-live&scope=site
DP - EBSCOhost
DB - gha
ER -
TY - JOUR
T1 - Radium-226 in diet and human bone from San Juan, Puerto Rico.
AU - HALLDEN, N. A.
AU - HARLEY, J. H.
JO - Nature
JF - Nature
Y1 - 1964///
VL - 204
SP - 240
EP - 241
SN - 0028-0836
AD - HALLDEN, N. A.: Health and Safety Lab., U.S. Atomic Energy Commission, New York.
N1 - Accession Number: 19651402772. Publication Type: Journal Article. Language: English.
N2 - Values from surveys in 1962 and 1963 are tabulated for diet constituents. On average 250 µµc 226Ra was consumed per year and plantains, bananas and yautia supplied 118, beans 40, bread 34 and milk only 7 µµg. Intake of Ca per year was 185 g. Human bone contained 0.017±0.001 µµc per g Ca. The ratio of 226Ra in bone to that in diet was 0.013 which compared well with American values.-A. Hepburn.
KW - bananas
KW - beans
KW - bones
KW - bread
KW - intake
KW - milk
KW - surveys
KW - Puerto Rico
KW - man
KW - Musa
KW - Homo
KW - Hominidae
KW - Primates
KW - mammals
KW - vertebrates
KW - Chordata
KW - animals
KW - eukaryotes
KW - Musaceae
KW - Zingiberales
KW - monocotyledons
KW - angiosperms
KW - Spermatophyta
KW - plants
KW - Greater Antilles
KW - Caribbean
KW - America
KW - Developing Countries
KW - Latin America
KW - Porto Rico
KW - Crop Produce (QQ050)
KW - Milk and Dairy Produce (QQ010)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=gha&AN=19651402772&site=ehost-live&scope=site
DP - EBSCOhost
DB - gha
ER -
TY - JOUR
T1 - Human bone metabolism inferred from fall-out investigations.
AU - RIVERA, J.
JO - Nature
JF - Nature
Y1 - 1965///
VL - 207
SP - 1330
EP - 1332
SN - 0028-0836
AD - RIVERA, J.: Health and Safety Lab., U.S. Atomic Energy Commission, New York.
N1 - Accession Number: 19661402772. Publication Type: Journal Article. Language: English.
KW - bone density
KW - bones
KW - man
KW - Homo
KW - Hominidae
KW - Primates
KW - mammals
KW - vertebrates
KW - Chordata
KW - animals
KW - eukaryotes
KW - Physiology of Human Nutrition (VV120)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=gha&AN=19661402772&site=ehost-live&scope=site
DP - EBSCOhost
DB - gha
ER -
TY - JOUR
T1 - Manganese-54: fractional distribution in wheat and occurrence in other foods.
AU - SUTTON, D. C.
AU - KELLY, J. J.
JO - Nature
JF - Nature
Y1 - 1966///
VL - 209
SP - 1081
EP - 1083
SN - 0028-0836
AD - SUTTON, D. C.: Health and Safety Lab., U.S. Atomic Energy Commission, New York.
N1 - Accession Number: 19661405914. Publication Type: Journal Article. Language: English.
N2 - In wheat from 11 states 54Mn ranged from 209 to 974 µµc and stable Mn from 20.0 to 60.3 mg per kg. Values are tabulated for milling fractions of wheat and for 10 food samples of plant origin obtained in New York; wholewheat bread contained 123, flour 62, dry beans 58 and white bread 12.8 µµc 54Mn per kg. An intake of about 160 µµc 54Mn per week may be postulated for the general population in 1964. The amounts in food do not constitute a health hazard. A. H.
KW - beans
KW - bread
KW - flours
KW - food
KW - foods
KW - health
KW - intake
KW - milling
KW - wheat
KW - New York
KW - USA
KW - Triticum
KW - Poaceae
KW - Cyperales
KW - monocotyledons
KW - angiosperms
KW - Spermatophyta
KW - plants
KW - eukaryotes
KW - Middle Atlantic States of USA
KW - Northeastern States of USA
KW - USA
KW - North America
KW - America
KW - Developed Countries
KW - OECD Countries
KW - United States of America
KW - Crop Produce (QQ050)
KW - Food Science and Food Products (Human) (QQ000)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=gha&AN=19661405914&site=ehost-live&scope=site
DP - EBSCOhost
DB - gha
ER -
TY - JOUR
T1 - The frequency of use of various kinds of milk during infancy in middle and lower-income families.
AU - Rivera, J.
JO - American Journal of Public Health
JF - American Journal of Public Health
Y1 - 1971///
VL - 61
IS - 2
SP - 277
EP - 280
SN - 0090-0036
AD - Rivera, J.: Health & Safety Lab., US Atomic Energy Commission (376 Hudson Street), New York 10014, USA.
N1 - Accession Number: 19720400343. Publication Type: Journal Article. Language: English. Number of References: 4 ref. Subject Subsets: Human Nutrition; Dairy Science
N2 - In a survey conducted in New York City and San Francisco, it was found that >50% of infants >4 months old received fresh cows' milk and that canned formulae were most frequently used for infants of <4 months. Infants (i) from lower-income families received evaporated milk more frequently and canned formulae (Enfamil, Lactum, Similac etc.) less frequently than did those (ii) from middle-income families. In the 1st month of life, <5% of (i) infants and about 25% of (ii) infants were breast fed.
KW - breast feeding
KW - incidence
KW - infant feeding
KW - infants
KW - milk
KW - practice
KW - surveys
KW - USA
KW - man
KW - Homo
KW - Hominidae
KW - Primates
KW - mammals
KW - vertebrates
KW - Chordata
KW - animals
KW - eukaryotes
KW - APEC countries
KW - Developed Countries
KW - North America
KW - America
KW - OECD Countries
KW - formulae
KW - United States of America
KW - Human Nutrition (General) (VV100)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=lhh&AN=19720400343&site=ehost-live&scope=site
DP - EBSCOhost
DB - lhh
ER -
TY - JOUR
T1 - Comparison of external irradiation and consumption of cows' milk as critical pathways for 137Cs, 54Mn and 144Ce-144Pr released to the atmosphere.
AU - Voilleque, P. G.
AU - Pelletier, C. A.
JO - Health Physics
JF - Health Physics
Y1 - 1974///
VL - 27
IS - 2
SP - 189
EP - 199
SN - 0017-9078
AD - Voilleque, P. G.: Health Services Lab., US Atomic Energy Commission, Idaho Falls, Idaho 83401, USA.
N1 - Accession Number: 19750416752. Publication Type: Journal Article. Language: English. Number of References: 18 ref. Subject Subsets: Human Nutrition; Dairy Science
N2 - Models and data were obtained from a 4-yr study of the behaviour of fallout radionuclides on and near a Michigan dairy farm. Direct radiation from radioactive material deposited on ground and plant surfaces was found to be the most limiting exposure route for 137C and 54Mn. Ingestion of contaminated milk was a more restrictive pathway for 144C-144Pr; the derived value was comparable to the limit based on the lung dose from direct inhalation by a standard man.
KW - air
KW - milk
KW - radioactivity
KW - soil
KW - plants
KW - eukaryotes
KW - Milk and Dairy Produce (QQ010)
KW - Food Contamination, Residues and Toxicology (QQ200)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=lhh&AN=19750416752&site=ehost-live&scope=site
DP - EBSCOhost
DB - lhh
ER -
TY - GEN
T1 - Tryptoquivaline and tryptoquivalone, two tremorgenic metabolites of Aspergillus clavatus.
AU - Clardy, J.
AU - Springer, J. P.
AU - Buchi, G.
AU - Matsuo, K.
AU - Wightman, R.
T2 - Journal of the American Chemical Society
JO - Journal of the American Chemical Society
JF - Journal of the American Chemical Society
Y1 - 1975///
VL - 97
IS - 3
SP - 663
EP - 665
SN - 0002-7863
AD - Clardy, J.: Ames Lab., US Atomic Energy Commission, Ames, Iowa 50010, USA.
N1 - Accession Number: 19751320405. Publication Type: Correspondence. Language: English. Number of References: 6 ref. Subject Subsets: Animal Nutrition; Human Nutrition; Medical & Veterinary Mycology
KW - production
KW - toxins
KW - Aspergillus clavatus
KW - Aspergillus
KW - Trichocomaceae
KW - Eurotiales
KW - Eurotiomycetes
KW - Pezizomycotina
KW - Ascomycota
KW - fungi
KW - eukaryotes
KW - fungus
KW - Hyphomycetes
KW - tryptoquivaline
KW - tryptoquivalone
KW - Feed Contamination, Residues and Toxicology (RR200)
KW - Food Contamination, Residues and Toxicology (QQ200)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=lhh&AN=19751320405&site=ehost-live&scope=site
DP - EBSCOhost
DB - lhh
ER -
TY - JOUR
T1 - The controversy over radiation safety: a historical overview.
AU - Walker, J. S.
JO - Journal of the American Medical Association
JF - Journal of the American Medical Association
Y1 - 1989///
VL - 262
IS - 5
SP - 664
EP - 668
AD - Walker, J. S.: US Nuclear Regulatory Commission, Washington, DC 20555, USA.
N1 - Accession Number: 19892063814. Publication Type: Journal Article. Language: English. Subject Subsets: Public Health
N2 - "The hazards of ionizing radiation have aroused concern since a short time after the discovery of X-rays and natural radioactivity in the 1890s. Misuse of X-rays and radium prompted efforts to encourage radiation safety and to set limits on exposure, culminating in the first recommended 'tolerance doses' in 1934. After World War II, the problems of radiation protection became more complex because of the growing number of people subjected to radiation injury and the creation of radioactive elements that had never existed before the achievement of atomic fission. Judging the hazards of radiation became a matter of spirited controversy. Major public debates over the dangers of radioactive fallout from atmospheric bomb testing in the 1950s and early 1960s and the risks of nuclear power generation in later periods focused attention on the uncertainties about the consequences of exposure to low-level radiation and the difficulties of resolving them."The authors conclude: "issues that involve the use of radiation sources have not been strictly scientific matters; ... different individuals and groups are likely to take different positions in the future regarding the seemingly timeless question of what constitutes an acceptable level of exposure to radiation."J.H. Renwick
KW - exposure
KW - health hazards
KW - ionizing radiation
KW - radiation
KW - Human Health and Hygiene (General) (VV000) (Revised June 2002) [formerly Human Health and Hygiene (General)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=lhh&AN=19892063814&site=ehost-live&scope=site
DP - EBSCOhost
DB - lhh
ER -
TY - JOUR
T1 - Exploring the relationship between safety culture and safety performance in U.S. nuclear power operations.
AU - Morrow, S. L.
AU - Koves, G. K.
AU - Barnes, V. E.
A2 - Aven, T.
A2 - Reiman, T.
JO - Safety Science
JF - Safety Science
Y1 - 2014///
VL - 69
SP - 37
EP - 47
CY - Oxford; UK
PB - Elsevier Ltd
SN - 0925-7535
AD - Morrow, S. L.: United States Nuclear Regulatory Commission, Washington, DC, USA.
N1 - Accession Number: 20143248004. Publication Type: Journal Article; Conference paper. Language: English. Subject Subsets: Public Health
N2 - How do nuclear power plant workers, within a single national culture, perceive safety culture within their organizations? What is the relationship between safety culture and other indicators of safety? Is the construct of safety culture useful for predicting future plant performance? These questions were addressed in the current study using a survey administered to a sample of personnel at 97% of the nuclear power plants in the United States, resulting in 2876 responses from 63 nuclear power plant sites. Exploratory and confirmatory factor analysis revealed a multi-factor structure to the safety culture survey. For each nuclear power plant, the mean score for the total survey results and the factor means were correlated with organization-level performance indicators both concurrently and one year following the survey administration. Correlations suggested meaningful, statistically significant relationships between safety culture, as measured by the survey, and multiple nuclear power plant performance indicators. This study presents a unique look at safety culture across the United States nuclear power industry and takes a critical step toward establishing that safety culture is empirically related to safety performance.
KW - nuclear power stations
KW - safety
KW - safety at work
KW - USA
KW - APEC countries
KW - Developed Countries
KW - North America
KW - America
KW - OECD Countries
KW - nuclear power plants
KW - occupational safety
KW - United States of America
KW - Occupational Health and Safety (VV900)
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=lhh&AN=20143248004&site=ehost-live&scope=site
UR - http://www.sciencedirect.com/science/article/pii/S0925753514000484
UR - email: Stephanie.Morrow@nrc.gov
DP - EBSCOhost
DB - lhh
ER -
TY - GEN
AU - Smyth, Henry D.
T1 - THE STOCKPILING AND RATIONING OF SCIENTIFIC MANPOWER.
JO - Bulletin of the Atomic Scientists
JF - Bulletin of the Atomic Scientists
Y1 - 1951/02//
VL - 7
IS - 2
M3 - Speech
SP - 38
EP - 42
PB - Bulletin of the Atomic Scientists
SN - 00963402
N1 - Accession Number: 21318729; Smyth, Henry D. 1; Affiliation: 1: Scientist-member, U.S. Atomic Energy Commission; Source Info: Feb1951, Vol. 7 Issue 2, p38; Number of Pages: 5p; Document Type: Speech
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=21318729&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY -
AU - Pike, Sumner T.1
T1 - The Promise of Atomic Energy.
JO - Education
JF - Education
J1 - Education
PY - 1951/03//
Y1 - 1951/03//
VL - 71
IS - 7
CP - 7
M3 - Article
SP - 407
EP - 413
SN - 00131172
AB - The article discusses the importance and benefits of atomic energy. By-products of the atomic pile are used routinely in medical diagnosis and treatment. These materials are called radioisotopes. Radioisotopes have revolutionized research and have found practical uses in agriculture and industry. In some application the energy released by these materials is used. Radiation from the radioisotopes may be use to destroy cancer. On the other hand, radioisotopes can also be found in nature. All living things contain radiocarbon. This radio carbon is also called carbon 14. This radiocarbon slowly decays over a thousands of years after death. As radiocarbon decays the ratio of radiocarbon to ordinary carbon change and so scientists can be determine when plant died.
KW - Nuclear energy
KW - Force & energy
KW - Radioisotopes
KW - Carbon isotopes
KW - Radiation
KW - Cancer prevention
KW - Agriculture
KW - Industries
KW - Nature
N1 - Accession Number: 19111857; Authors: Pike, Sumner T. 1; Affiliations: 1: Member, United States Atomic Energy Commission; Subject: Nuclear energy; Subject: Force & energy; Subject: Radioisotopes; Subject: Carbon isotopes; Subject: Radiation; Subject: Cancer prevention; Subject: Agriculture; Subject: Industries; Subject: Nature; Number of Pages: 7p; Record Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=lls&AN=19111857&site=ehost-live&scope=site
DP - EBSCOhost
DB - lls
ER -
TY - JOUR
AU - Bauer, Charles K.
T1 - EXPLOITING REPORT LITERATURE: WAYS AND MEANS OF REACHING THE CONSUMER.
JO - American Documentation
JF - American Documentation
Y1 - 1952/08//
VL - 3
IS - 3
M3 - Article
SP - 161
EP - 163
SN - 0096946X
AB - The article discusses the ways to reach the consumer through the Documentation Center, through the University Research Information Centers, or libraries. Scientific research and development have tremendously increased, not only through the current defense effort but also as an inevitable result of the machine age in which we are living. Therefore research in every phase must be performed economically, thoroughly and, above all, with the least possible delay. Helping the scientist to expedite his research and to avoid unnecessary duplication is a goal that cannot be attained unless he is furnished all of the available data pertinent to his particular problems. Therefore, the librarian must find ways and means to reach his consumer in the speediest and most economical way.
KW - INFORMATION resources
KW - LIBRARIES
KW - DOCUMENTATION
KW - INFORMATION services
KW - SCIENTISTS
KW - RECORDS
N1 - Accession Number: 16878729; Bauer, Charles K. 1; Affiliations: 1: Assistant Chief Librarian, Technical Information Service, United States Atomic Energy Commission, Washington.; Issue Info: Aug1952, Vol. 3 Issue 3, p161; Thesaurus Term: INFORMATION resources; Thesaurus Term: LIBRARIES; Thesaurus Term: DOCUMENTATION; Thesaurus Term: INFORMATION services; Subject Term: SCIENTISTS; Subject Term: RECORDS; NAICS/Industry Codes: 519190 All Other Information Services; NAICS/Industry Codes: 519120 Libraries and Archives; NAICS/Industry Codes: 519121 Libraries; NAICS/Industry Codes: 236220 Commercial and Institutional Building Construction; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=16878729&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Weil, George L.
T1 - A Role for Private Nonprofit Organizations.
JO - Bulletin of the Atomic Scientists
JF - Bulletin of the Atomic Scientists
Y1 - 1953/06//
VL - 9
IS - 5
M3 - Article
SP - 165
EP - 168
PB - Bulletin of the Atomic Scientists
SN - 00963402
N1 - Accession Number: 21307125; Weil, George L. 1; Affiliation: 1: Chief, Reactors Branch, U.S. Atomic Energy Commission; Source Info: Jun1953, Vol. 9 Issue 5, p165; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=21307125&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Strauss, Lewis L.
T1 - Is Present Federal Policy In Civilian Atomic Energy Field Sound? PRO.
JO - Congressional Digest
JF - Congressional Digest
Y1 - 1957/01//
VL - 36
IS - 1
M3 - Article
SP - 12
EP - 18
PB - Congressional Digest
SN - 00105899
N1 - Accession Number: 12298527; Strauss, Lewis L. 1; Affiliation: 1: U.S. Atomic Energy Commission; Source Info: Jan1957, Vol. 36 Issue 1, p12; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=12298527&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Eisenbud, Merril
AU - Waterhouse, Carmack
AU - Cole, Fay-Cooper
T1 - LETTERS.
JO - Scientific American
JF - Scientific American
Y1 - 1959/04//
VL - 200
IS - 4
M3 - Letter
SP - 10
EP - 14
SN - 00368733
AB - A letter to the editor in response to the reviewed Linus Pauling's book "No More War," is presented.
KW - Letters to the editor
KW - War
N1 - Accession Number: 19881576; Eisenbud, Merril 1; Waterhouse, Carmack; Cole, Fay-Cooper; Affiliations: 1: Manager, New York Operations Office, United States Atomic Energy Commission, New York, N.Y.; Issue Info: Apr1959, Vol. 200 Issue 4, p10; Subject Term: Letters to the editor; Subject Term: War; Number of Pages: 3p; Document Type: Letter
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=19881576&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Haber, Alan H.
AU - Luippold, Helen J.
T1 - Action of 6 - (Substituted) Purines on Mitotic Activity in "Dormant" Lettuce Seeds.
JO - Physiologia Plantarum
JF - Physiologia Plantarum
Y1 - 1960/04//
VL - 13
IS - 2
M3 - Article
SP - 298
EP - 307
PB - Wiley-Blackwell
SN - 00319317
AB - This article reports that although kinetin has diverse effects on plant growth, it has probably attracted greatest attention as a cell division factor. Investigations of the action of kinetin in cell division have proceeded along two lines — comparisons of the chemical structure of kinetin analogs with their biological activity and cytological examinations of kinetin-treated tissues. Experiments in which the first approach was used have suggested that the function of the side chain substituted in the 6-amino group of adenine is to endow adenine with the right physical properties to reach some critical spot within the cell.
KW - Plant regulators
KW - Plant growth
KW - Cell division (Biology)
KW - Plant cells & tissues
KW - Adenine
KW - Cytology
N1 - Accession Number: 15790597; Haber, Alan H. 1; Luippold, Helen J. 1; Affiliations: 1: Biology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee Operated by Union Carbide Corporation for the U.S. Atomic Energy Commission.; Issue Info: 1960, Vol. 13 Issue 2, p298; Thesaurus Term: Plant regulators; Thesaurus Term: Plant growth; Thesaurus Term: Cell division (Biology); Subject Term: Plant cells & tissues; Subject Term: Adenine; Subject Term: Cytology; NAICS/Industry Codes: 111422 Floriculture Production; NAICS/Industry Codes: 325320 Pesticide and Other Agricultural Chemical Manufacturing; Number of Pages: 10p; Document Type: Article
L3 - 10.1111/1399-3054.ep15790597
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=15790597&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - GEN
AU - Garrett, Jerry M.
AU - van Meter, Margaret
AU - Alvarado, Frank J.
AU - Menninger, Karl
AU - Rychener, Raymond R.
AU - Deming, Jennie Como
AU - Cayce, Mary
AU - Hart, Joan
AU - Hogg, Ruth
AU - Engh, Robert A.
AU - Corbett, J. S.
AU - Clark, Duncan
AU - Broderick, Lee
AU - Hiser, Iona S.
AU - Johnson, Gladys R.
T1 - Letters.
JO - Saturday Evening Post
JF - Saturday Evening Post
Y1 - 1960/09/03/
VL - 233
IS - 10
M3 - Letter
SP - 4
EP - 4
PB - Saturday Evening Post Society, Inc..
SN - 00489239
AB - Presents letters to the editor about various issues related to social life in the U.S., published in the journal "The Saturday Evening Post." Comment about an illustration by artist Joe De Mers related to a physician; Comment about a campaign of endorsement for cigarettes by physicians; Criticism of the article "Nine Days to Die," by William Sambrot regarding radioactive waste, published in the July 9, 1960 issue of the journal.
KW - LETTERS to the editor
KW - MANNERS & customs
KW - RADIOACTIVE wastes
KW - PHYSICIANS
KW - RADIOACTIVE substances
KW - UNITED States
N1 - Accession Number: 18089126; Garrett, Jerry M. van Meter, Margaret Alvarado, Frank J. 1 Menninger, Karl 2 Rychener, Raymond R. Deming, Jennie Como Cayce, Mary Hart, Joan Hogg, Ruth Engh, Robert A. Corbett, J. S. 3 Clark, Duncan 4 Broderick, Lee Hiser, Iona S. Johnson, Gladys R.; Affiliation: 1: President, Pan American Optimist Club San Antonia, Tex. 2: Menninger Foundation, Topeka, Kans. 3: Nuclear Engineering Co., Inc. Newark, N.J. 4: Director, Office of Public Information, U.S. Atomic Energy Commission, Washington, D.C.; Source Info: 9/3/1960, Vol. 233 Issue 10, p4; Subject Term: LETTERS to the editor; Subject Term: MANNERS & customs; Subject Term: RADIOACTIVE wastes; Subject Term: PHYSICIANS; Subject Term: RADIOACTIVE substances; Subject Term: UNITED States; NAICS/Industry Codes: 621111 Offices of Physicians (except Mental Health Specialists); NAICS/Industry Codes: 621110 Offices of physicians; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562210 Waste treatment and disposal; Number of Pages: 1p; Document Type: Letter
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Dunning, Gordon M.
AU - Mattison, Lindsay
T1 - AEC OFFICIAL PROTESTS.
JO - Bulletin of the Atomic Scientists
JF - Bulletin of the Atomic Scientists
Y1 - 1964/09//
VL - 20
IS - 7
M3 - Letter
SP - 29
EP - 30
PB - Bulletin of the Atomic Scientists
SN - 00963402
N1 - Accession Number: 21498992; Dunning, Gordon M. 1 Mattison, Lindsay; Affiliation: 1: Deputy Director, Division of Operational Safety, U.S. Atomic Energy Commission; Source Info: Sep1964, Vol. 20 Issue 7, p29; Number of Pages: 2p; Document Type: Letter
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Hall, John A.
T1 - ATOMS FOR PEACE, OR WAR.
JO - Foreign Affairs
JF - Foreign Affairs
Y1 - 1965/07//
VL - 43
IS - 4
M3 - Article
SP - 602
EP - 615
PB - Foreign Affairs
SN - 00157120
N1 - Accession Number: 5801343; Hall, John A. 1; Affiliation: 1: Assistant General Manager, International Activities, U.S. Atomic Energy Commission; Source Info: Jul1965, Vol. 43 Issue 4, p602; Number of Pages: 14p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Sherrod, John
T1 - National information needs and trends
JO - Cuadra, Carlos A., Ed. Annual Review Of Information Science And Technology, Vol. 1, 1966. Interscience Publishers, New York, N.y., P. 337-351. 25 Refs. See 67-358
JF - Cuadra, Carlos A., Ed. Annual Review Of Information Science And Technology, Vol. 1, 1966. Interscience Publishers, New York, N.y., P. 337-351. 25 Refs. See 67-358
Y1 - 1966///
M3 - Book Chapter
AB - Reviews the increasing activity that is leading toward a national information network. Describes particularly the development in the federal government area, but also recounts briefly the work in the societal world. The controversial copyright bill now in congress is discussed. The author points out that any planning toward improved information handling at the national leval will have to consider ways in which government and the private sector can cooperate. There is every reason to believe that a working plan for setting-up a national information system for science and technology will evolve in the near future. The government has the necessary resources and the obligation to take the lead in this endeavor, but the fullest cooperation from the private sector, and particularly the professional societies, will be needed to ensure its success.
N1 - Accession Number: ISTA0200952; Sherrod, John 1; Affiliations: 1 : U.s. Atomic Energy Commission, Washington, D.c.; Source Info: 1966; Note: Update Code: 0200; Document Type: Book Chapter
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DP - EBSCOhost
DB - lih
ER -
TY - CONF
AU - Norris, Jr., W. E.
AU - McClelllan, R. O.
AU - Bustad, L. K.
T1 - MEETINGS.
JO - BioScience
JF - BioScience
Y1 - 1966/06//
VL - 16
IS - 6
M3 - Proceeding
SP - 417
EP - 419
SN - 00063568
AB - The article offers information on several meetings related to biosciences to be held from June 1966 to February 1967, including the Caribbean Division of the American Phytopathological Society's meeting in Venezuela, the 19th annual Conference on Engineering in Medicine and Biology in San Francisco, and the Society for Cryobiology's meeting in Boston.
KW - Conferences & conventions
KW - Life sciences -- Congresses
KW - Plant diseases -- Congresses
KW - Bioengineering -- Congresses
KW - Biomedical engineering -- Congresses
N1 - Accession Number: 31983291; Norris, Jr., W. E. 1; McClelllan, R. O. 2; Bustad, L. K. 3; Affiliations: 1 : Secretary-Treasurer, Southwest Texas State College, Sam Marcos, Texas 78666.; 2 : Division of Biology and Medicine, U.S. Atomic Energy Commission, Washington, D.C.; 3 : Radiochemistry Laboratory, University of California, Davis, California.; Source Info: Jun1966, Vol. 16 Issue 6, p417; Subject Term: Conferences & conventions; Subject Term: Life sciences -- Congresses; Subject Term: Plant diseases -- Congresses; Subject Term: Bioengineering -- Congresses; Subject Term: Biomedical engineering -- Congresses; Number of Pages: 3p; Document Type: Proceeding
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DP - EBSCOhost
DB - 8gh
ER -
TY - GEN
AU - Seaborg, Glenn T.
T1 - What's Ahead for International Science?
JO - Bulletin of the Atomic Scientists
JF - Bulletin of the Atomic Scientists
Y1 - 1967/01//
VL - 23
IS - 1
M3 - Speech
SP - 24
EP - 28
PB - Bulletin of the Atomic Scientists
SN - 00963402
N1 - Accession Number: 21499376; Seaborg, Glenn T. 1; Affiliation: 1: Chairman, U.S. Atomic Energy Commission; Source Info: Jan1967, Vol. 23 Issue 1, p24; Number of Pages: 5p; Document Type: Speech
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Sherrod, John
T1 - International cooperation on education in information science
JO - In Proceedings Of The International Conference On Education For Scientific Work, Queen Elizabeth College, London, 3rd To 7th April, 1967. 1967, Fid, The Hague. P. 217-219. Area Iv, Paper I. See Da 68-392
JF - In Proceedings Of The International Conference On Education For Scientific Work, Queen Elizabeth College, London, 3rd To 7th April, 1967. 1967, Fid, The Hague. P. 217-219. Area Iv, Paper I. See Da 68-392
Y1 - 1967///
M3 - Book
AB - It is stated that co-operative schemes for collecting, evaluating, and indexing scientific and technical information of all kinds on a world-wide basis are not feasible. Examples are the groundwork for the organization of an international nuclear information system, the proposed system for international co-operation in mechanized patent searching utilizing a world patent index and the study of icsu and unesco of the development of a world-wide science indexing service. It forecasts that by the end of the present decade international cooperation in organization the documentation in many areas of science and technology will have greatly increased. If this forecast be correct, the essential question is to ensure an adequate supply of trained personnel for designing and operating these advanced information systems on an international basis. To help provide well educated and trained personnel a continuing international seminar on information science and technology is suggested with the objective of providing an international cadre of information specialists. Major emphasis in the programme would be placed in on-the-job training at selected national and regional information centers which are actively participating in operational systems. It is suggested that the problem of educating personnel for operating international information systems deserves priority attention on the part of those who have educational responsibilities in information science.
N1 - Accession Number: ISTA0300365; Sherrod, John 1; Affiliations: 1 : Division Of Technical Information, U.s. Atomic Energy Commission, Washington, D.c.; Source Info: 1967; Note: Update Code: 0300; Document Type: Book
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DP - EBSCOhost
DB - lih
ER -
TY - GEN
AU - Kee, Walter A
T1 - There's room for improvement
JO - Special Libraries
JF - Special Libraries
Y1 - 1967/09//
VL - 58
IS - 7
M3 - Article
SP - 543
EP - 544
SN - 00386723
AB - Responding to i. A. Warheit's letter to the editor (special libraries, december 1966), the author points to an incident in his own experience where the librarian refused to participate 'in developing the broad spectrum of information services required by the organization.'
N1 - Accession Number: ISTA0200618; Kee, Walter A 1; Affiliations: 1 : U.s. Atomic Energy Commission.; Source Info: September 1967, Vol. 58 Issue 7, p543; Note: Update Code: 0200; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - lih
ER -
TY - JOUR
AU - Knutila, Chester
T1 - CPA, CLIENT AND GOVERNMENT AGENCY CO-OPERATION.
JO - Journal of Accountancy
JF - Journal of Accountancy
Y1 - 1968/02//
VL - 125
IS - 2
M3 - Article
SP - 41
EP - 43
PB - American Institute of Ceritified Public Accountants
SN - 00218448
AB - The article discusses how certified public accounting firms, the U.S. Atomic Energy Commission (AEC), and major mining and milling companies have cooperated and work together to better understand each other's problems. AEC hired independent auditors to audit the costs involving its domestic uranium procurement program. Meetings were held with the contractors and the accountants involved in the program to discuss problems and objectives. Most of the meetings focused on the scope of audits and materiality requirements.
KW - ACCOUNTING firms
KW - ACCOUNTANTS
KW - URANIUM industry
KW - CONTRACTORS
KW - AUDITING
KW - MATERIALITY (Accounting)
KW - UNITED States
KW - U.S. Atomic Energy Commission
N1 - Accession Number: 4582090; Knutila, Chester 1; Affiliations: 1: Director of the Finance and Budget Division of the U.S. Atomic Energy Commission office in Grand Junction, Colorado; Issue Info: Feb1968, Vol. 125 Issue 2, p41; Thesaurus Term: ACCOUNTING firms; Thesaurus Term: ACCOUNTANTS; Thesaurus Term: URANIUM industry; Thesaurus Term: CONTRACTORS; Thesaurus Term: AUDITING; Thesaurus Term: MATERIALITY (Accounting); Subject: UNITED States ; Company/Entity: U.S. Atomic Energy Commission; NAICS/Industry Codes: 541219 Other Accounting Services; NAICS/Industry Codes: 541212 Offices of accountants; NAICS/Industry Codes: 541211 Offices of Certified Public Accountants; NAICS/Industry Codes: 213119 Other support activities for mining; Number of Pages: 3p; Illustrations: 1 Black and White Photograph; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - GEN
AU - Stevenson, Chris G
T1 - A librarian looks at the state technical services act
JO - Special Libraries
JF - Special Libraries
Y1 - 1968/03//
VL - 59
IS - 3
M3 - Article
SP - 183
EP - 185
SN - 00386723
AB - The state technical services act of 1965 is designed to assure the fullest industrial utilization of technical information resulting from federal research and development programs. Since the mechanics of technology transfer are uncertain, the act encourages states to develop new and imaginative programs to bring useful information to local industry. Many of these programs involve extensive utilization of existing library systems. In the long run, the act wil be of great benefit to libraries and librarians since it will encourage broader use of information resources.
N1 - Accession Number: ISTA0301231; Stevenson, Chris G 1; Affiliations: 1 : U.s. Atomic Energy Commission, Richland, Washington.; Source Info: March 1968, Vol. 59 Issue 3, p183; Note: Update Code: 0300; Number of Pages: 3p; Document Type: Article
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DP - EBSCOhost
DB - lih
ER -
TY - JOUR
AU - Ramey, James T.
T1 - Competitive vigor in nuclear power.
JO - Harvard Business Review
JF - Harvard Business Review
Y1 - 1968/07//Jul/Aug1968
VL - 46
IS - 4
M3 - Article
SP - 126
EP - 142
PB - Harvard Business School Publication Corp.
SN - 00178012
AB - Here a Commissioner of the U.S. Atomic Energy Commission describes the civilian power reactor business, which contains the bulk of industrial investment in the atomic energy field; looks at the growing potentials of nuclear power for private industry; and discusses some of the key questions concerning the nature of desirable competition in nuclear power. He also reviews some of the highlights of the AEC's Plowshare Program and its projects for developing the uses of radioisotopes. The AEC's efforts to create a healthy, profitable field for private business are without parallel in U.S. history, and the author has himself played a leading role in this development. "The AEC has taken, and will continue to take, a positive approach toward competition in the nuclear industry," he writes. "It intends to lead, rather than push, and to persuade, rather than compel." [ABSTRACT FROM AUTHOR]
AB - Harvard Business Review Notice of Use Restrictions, May 2009Harvard Business Review and Harvard Business Publishing Newsletter content on EBSCOhost is licensed for the private individual use of authorized EBSCOhost users. It is not intended for use as assigned course material in academic institutions nor as corporate learning or training materials in businesses. Academic licensees may not use this content in electronic reserves, electronic course packs, persistent linking from syllabi or by any other means of incorporating the content into course resources. Business licensees may not host this content on learning management systems or use persistent linking or other means to incorporate the content into learning management systems. Harvard Business Publishing will be pleased to grant permission to make this content available through such means. For rates and permission, contact permissions@harvardbusiness.org. (Copyright applies to all Abstracts.)
KW - PUBLIC-private sector cooperation
KW - NUCLEAR power plants
KW - NUCLEAR industry
KW - GOVERNMENT policy
KW - POWER resources
KW - MANAGEMENT
KW - INDUSTRIAL management
KW - ECONOMIC aspects
KW - COMPETITION
KW - NUCLEAR energy
KW - ENERGY development
KW - NUCLEAR reactors
KW - UNITED States
KW - U.S. Atomic Energy Commission
N1 - Accession Number: 3866669; Ramey, James T. 1; Affiliations: 1: Commissioner of the U.S. Atomic Energy Commission; Issue Info: Jul/Aug1968, Vol. 46 Issue 4, p126; Thesaurus Term: PUBLIC-private sector cooperation; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: NUCLEAR industry; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: POWER resources; Thesaurus Term: MANAGEMENT; Thesaurus Term: INDUSTRIAL management; Subject Term: ECONOMIC aspects; Subject Term: COMPETITION; Subject Term: NUCLEAR energy; Subject Term: ENERGY development; Subject Term: NUCLEAR reactors; Subject: UNITED States ; Company/Entity: U.S. Atomic Energy Commission; NAICS/Industry Codes: 911910 Other federal government public administration; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 17p; Illustrations: 1 Diagram, 1 Chart, 6 Graphs, 1 Map; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Kaye, S. V.
AU - Rohwer, P. S.
AU - Cowser, K. E.
AU - Snyder, W. S.
T1 - Predicting Radiation Dose Equivalents for Populations I. Dose Models and Methods of Application.
JO - BioScience
JF - BioScience
Y1 - 1969/03//
VL - 19
IS - 3
M3 - Article
SP - 238
EP - 241
SN - 00063568
AB - The article focuses on the importance of estimation models and methods in predicting radiation dose. The nuclear explosions made in the excavation at a sea-level canal will possibly result to the exposure of human population in finite radiation. The methods of calculating the possible exposures are needed to make a radiological safety. Estimating dose equivalents also needs biological data of the human population, as well as radionuclides inventory, environmental factors, biological parameters and dose-estimation equation.
KW - Population
KW - Radiation
KW - Environmental engineering
KW - Estimation theory
KW - Radiation dosimetry
KW - Nuclear explosions
KW - Nuclear excavation
KW - Interoceanic canals
KW - Safety
N1 - Accession Number: 32065830; Kaye, S. V. 1; Rohwer, P. S. 1; Cowser, K. E. 1; Snyder, W. S. 1; Affiliations: 1 : Health Physics Division, Oak Ridge National Laboratory for the US Atomic Energy Commission; Source Info: Mar1969, Vol. 19 Issue 3, p238; Thesaurus Term: Population; Thesaurus Term: Radiation; Thesaurus Term: Environmental engineering; Subject Term: Estimation theory; Subject Term: Radiation dosimetry; Subject Term: Nuclear explosions; Subject Term: Nuclear excavation; Subject Term: Interoceanic canals; Subject Term: Safety; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - 8gh
ER -
TY - JOUR
AU - Schwartz, M. H.
T1 - COMPUTER PROJECT SELECTION IN THE BUSINESS ENTERPRISE.
JO - Journal of Accountancy
JF - Journal of Accountancy
Y1 - 1969/04//
VL - 127
IS - 4
M3 - Article
SP - 35
EP - 43
PB - American Institute of Ceritified Public Accountants
SN - 00218448
AB - This article discusses the screening, selection and evaluation of computer projects in business enterprises. The effective screening, selection and evaluation of computer projects required the criteria for making judgments, recommendations and decisions about authorizing and maintaining projects for asssigning and shifting projects. The authorization for computer projects in a business enterprise should be based on quantifiable impact on profit and loss, whether in the form of new earnings or savings, qualitative factors and institutional criteria. There is a need to analyze qualitative factors for projects whose benefits cannot be specified in dollar terms. This analysis required effective management that depends on the maintenance of institutional balance in computer resource allocation.
KW - BUSINESS planning
KW - BUSINESS enterprises
KW - RESOURCE allocation
KW - INDUSTRIAL management
KW - COMPUTER network resources
N1 - Accession Number: 4589948; Schwartz, M. H. 1,2; Affiliations: 1: Assistant controller, U.S. Atomic Energy Commission; 2: Member, Council for the School of Business and Government, George Washington University; Issue Info: Apr1969, Vol. 127 Issue 4, p35; Thesaurus Term: BUSINESS planning; Thesaurus Term: BUSINESS enterprises; Thesaurus Term: RESOURCE allocation; Thesaurus Term: INDUSTRIAL management; Subject Term: COMPUTER network resources; Number of Pages: 9p; Illustrations: 1 Black and White Photograph, 2 Charts; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Seaborg, Glenn T.
AU - Bloom, Justin L.
T1 - Fast Breeder Reactors.
JO - Scientific American
JF - Scientific American
Y1 - 1970/11//
VL - 223
IS - 5
M3 - Article
SP - 13
EP - 21
SN - 00368733
AB - The article focuses on the development of fast breeder reactors and their applications. The reactor must be operated at a much higher power density than ordinary fission reactors are. It has a blanket that surrounds the core which consists of uranium 238 in stainless-steel tubes. The sodium coolant can be used at a fairly low pressure.
KW - Electric power
KW - Uranium
KW - Sodium
KW - Breeder reactors
KW - Fast reactors
KW - METHODS AND MISCELLANEOUS
KW - Peaceful uses of atomic energy
N1 - Accession Number: 22502059; Seaborg, Glenn T. 1; Bloom, Justin L. 2; Affiliations: 1: Chairman, U.S. Atomic Energy Commission; 2: Staff assistant, U.S. Atomic Energy Commission; Issue Info: Nov1970, Vol. 223 Issue 5, p13; Thesaurus Term: Electric power; Thesaurus Term: Uranium; Thesaurus Term: Sodium; Subject Term: Breeder reactors; Subject Term: Fast reactors; Author-Supplied Keyword: METHODS AND MISCELLANEOUS; Author-Supplied Keyword: Peaceful uses of atomic energy; NAICS/Industry Codes: 213119 Other support activities for mining; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 9p; Illustrations: 8 Diagrams, 1 Chart; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - GEN
AU - Lebow, Irving
T1 - On-line input of textual data
JO - In Madeline B. Henderson, Ed. Interactive Bibliographic Systems. Proceedings Of A Forum Held At Gaithersburg, Maryland, October 4-5, 1971. 1973 April. P. 46-45. 11 Illus. 1 Tab. 0 Ref. Discussion On P. 65-68. See Isa 74-1069/y
JF - In Madeline B. Henderson, Ed. Interactive Bibliographic Systems. Proceedings Of A Forum Held At Gaithersburg, Maryland, October 4-5, 1971. 1973 April. P. 46-45. 11 Illus. 1 Tab. 0 Ref. Discussion On P. 65-68. See Isa 74-1069/y
Y1 - 1971///
M3 - Book Chapter
AB - The development of an on-line, interactive, input system to enter descriptive cataloging information and to create a data base for subsequent computer manipulation is described. The computer interacts with the terminals entering data and guides the compositor to assure entry of all essential data. The cathode-ray tube (crt) display of greek, mathematical, and normal alphanumeric characters, together with the editing, correction and recall of data, is provided.
N1 - Accession Number: ISTA0900963; Lebow, Irving 1; Affiliations: 1 : U.s. Atomic Energy Commission, Oak Ridge, Tennessee.; Source Info: 1971; Note: Update Code: 0900; Document Type: Book Chapter
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DP - EBSCOhost
DB - lih
ER -
TY - JOUR
AU - PARKER, D. R.
T1 - Germ Cells.
JO - Science
JF - Science
Y1 - 1971/01/29/
VL - 171
IS - 3969
M3 - Article
SP - 368
EP - 369
SN - 00368075
N1 - Accession Number: 85104303; PARKER, D. R. 1; Affiliations: 1: U.S. Atomic Energy Commission, Washington, D.C.; Issue Info: 1/29/1971, Vol. 171 Issue 3969, p368; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Gough, William C.
AU - Eastlund, Bernard J.
T1 - The Prospects of Fusion Power.
JO - Scientific American
JF - Scientific American
Y1 - 1971/02//
VL - 224
IS - 2
M3 - Article
SP - 50
EP - 64
SN - 00368733
AB - Examines the implications of advances in the performance of several experimental plasma containers for the immediate and long-term prospects of fusion power as of 1971. Role of energy in determining the economic well-being of a society; Energy options available for the future which include fossil and nuclear fuels; Information on several experimental plasma containers which include the Russian stellarator.
KW - Power resources
KW - Controlled fusion
KW - Fusion reactors
KW - Nuclear fusion
KW - Plasma confinement
KW - Conservation; pollution; environmental problems and protection
KW - METHODS AND MISCELLANEOUS
KW - Peaceful uses of atomic energy
N1 - Accession Number: 20747587; Gough, William C. 1; Eastlund, Bernard J. 1; Affiliations: 1: Division of Research, U.S. Atomic Energy Commission; Issue Info: Feb1971, Vol. 224 Issue 2, p50; Thesaurus Term: Power resources; Subject Term: Controlled fusion; Subject Term: Fusion reactors; Subject Term: Nuclear fusion; Subject Term: Plasma confinement; Author-Supplied Keyword: Conservation; pollution; environmental problems and protection; Author-Supplied Keyword: METHODS AND MISCELLANEOUS; Author-Supplied Keyword: Peaceful uses of atomic energy; Number of Pages: 15p; Illustrations: 7 Diagrams, 1 Chart, 6 Graphs; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Rose, David J.
T1 - Controlled Nuclear Fusion: Status and Outlook.
JO - Science
JF - Science
Y1 - 1971/05/21/
VL - 172
IS - 3985
M3 - Article
SP - 797
EP - 808
SN - 00368075
N1 - Accession Number: 85198660; Rose, David J. 1; Affiliations: 1: Director of Long-Range Planning, Oak Ridge National Laboratory (operaited by Union Carbide C orp. for U.S. Atomic Energy Commission), Oak Ridge, Tennessee 37830; Issue Info: 5/21/1971, Vol. 172 Issue 3985, p797; Number of Pages: 12p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - SEABORG, GLENN T.
T1 - Scientific Development in Africa.
JO - Science
JF - Science
Y1 - 1971/06/04/
VL - 172
IS - 3987
M3 - Article
SP - 987
EP - 987
SN - 00368075
N1 - Accession Number: 85268401; SEABORG, GLENN T. 1; Affiliations: 1: United States Atomic Energy Commission, Washington, D.C. 20545; Issue Info: 6/ 4/1971, Vol. 172 Issue 3987, p987; Number of Pages: 4/5p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Davis, J. J.
T1 - The Atomic Energy Commission's Interest in Bioenvironmental Research.
JO - BioScience
JF - BioScience
Y1 - 1971/06/15/
VL - 21
IS - 12
M3 - Article
SP - 600
EP - 602
SN - 00063568
AB - The article presents the atomic energy commission's interest in bioenvironmental research. This paper focuses on the requirements needed for the development, usage and control of atomic energy for the benefit of the national defense and national security. It has been proposed by the Atomic Energy Act (AEC) that atomic energy be used for the general welfare of humankind in uplifting the standard of living, promote world peace, and for strengthening free competition in private enterprises. AEC has developed and been pushing for various researches in the advances of technology in atomic energy.
KW - Nuclear energy
KW - Ecology
KW - Defense industries
KW - International relations
KW - National security
KW - Peace
KW - Cost & standard of living
KW - Government policy
KW - Free enterprise
N1 - Accession Number: 32116213; Davis, J. J. 1; Affiliations: 1 : Effects Evaluation Division, U.S. Atomic Energy Commission, Nevada Operations Office, P.O. Box 14100, Las Vegas, Nevada 89114; Source Info: 6/15/1971, Vol. 21 Issue 12, p600; Thesaurus Term: Nuclear energy; Thesaurus Term: Ecology; Subject Term: Defense industries; Subject Term: International relations; Subject Term: National security; Subject Term: Peace; Subject Term: Cost & standard of living; Subject Term: Government policy; Subject Term: Free enterprise; Number of Pages: 3p; Document Type: Article
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DP - EBSCOhost
DB - 8gh
ER -
TY - GEN
AU - Wilson, John H, Jr
T1 - Costs, budgeting, and economics of information processing
JO - In Cuadra, Carlos A., Ed.; Luke, Ann W., Asst. Ed. Annual Review Of Information Science And Technology. Volume 7, 1972. P. 39-67. 180 Ref. See Isa 73-485/y
JF - In Cuadra, Carlos A., Ed.; Luke, Ann W., Asst. Ed. Annual Review Of Information Science And Technology. Volume 7, 1972. P. 39-67. 180 Ref. See Isa 73-485/y
Y1 - 1972///
M3 - Book Chapter
N1 - Accession Number: ISTA0800666; Wilson, John H, Jr 1; Affiliations: 1 : U.s. Atomic Energy Commission, Washington.; Source Info: 1972; Note: Update Code: 0800; Document Type: Book Chapter
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DP - EBSCOhost
DB - lih
ER -
TY - JOUR
AU - Eason, Charles F.
AU - Brooks, Barbara G.
T1 - Should Medical Radiation Exposure Be Recorded?
JO - American Journal of Public Health
JF - American Journal of Public Health
Y1 - 1972/09//
VL - 62
IS - 9
M3 - Article
SP - 1189
EP - 1193
PB - American Public Health Association
SN - 00900036
AB - There appears to be enough evidence to support the desirability and feasibility of a study to record the diagnostic radiation exposure of radiation workers. A course of action to initiate a viable pro- gram of this type is described. [ABSTRACT FROM AUTHOR]
AB - Copyright of American Journal of Public Health is the property of American Public Health Association and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radiation -- Physiological effect
KW - Radiation exposure
KW - Radioactivity
KW - Public health research
KW - X-rays -- Industrial applications
KW - Nondestructive testing
N1 - Accession Number: 24294263; Eason, Charles F. 1; Brooks, Barbara G. 2; Affiliations: 1: Assistant for Workmen's Compensation and Radiation Records; 2: Health Physicist, United States Atomic Energy Commission, Washington, D.C.; Issue Info: Sep1972, Vol. 62 Issue 9, p1189; Thesaurus Term: Radiation -- Physiological effect; Thesaurus Term: Radiation exposure; Thesaurus Term: Radioactivity; Thesaurus Term: Public health research; Subject Term: X-rays -- Industrial applications; Subject Term: Nondestructive testing; NAICS/Industry Codes: 541380 Testing Laboratories; NAICS/Industry Codes: 541710 Research and development in the physical, engineering and life sciences; Number of Pages: 5p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - McCormick Jr., William T.
AU - Sehweitzer, Paul J.
AU - White, Thomas W.
T1 - Problem Decomposition and Data Reorganization by a Clustering Technique.
JO - Operations Research
JF - Operations Research
Y1 - 1972/09//Sep/Oct72
VL - 20
IS - 5
M3 - Article
SP - 993
EP - 1009
PB - INFORMS: Institute for Operations Research
SN - 0030364X
AB - A new cluster-analysis method, the bond energy algorithm, has been developed recently; it operates upon a raw input object-object or object-attribute data array by permuting its rows and columns in order to find informative variable groups and their interrelations. This paper describes the algorithm and illustrates by several examples its use for both problem decomposition and data reorganization. [ABSTRACT FROM AUTHOR]
AB - Copyright of Operations Research is the property of INFORMS: Institute for Operations Research and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - CLUSTER analysis (Statistics)
KW - CORRELATION (Statistics)
KW - MULTIVARIATE analysis
KW - ALGORITHMS
KW - MATHEMATICS
KW - OPERATIONS research
N1 - Accession Number: 8735242; McCormick Jr., William T. 1; Sehweitzer, Paul J. 2; White, Thomas W. 3; Affiliations: 1: Executive Office of the President and US Atomic Energy Commission, Washington, D.C.; 2: Technion—Israel Institule of Technology, Haifa, Israel; 3: Urban Institute, Washington, D.C.; Issue Info: Sep/Oct72, Vol. 20 Issue 5, p993; Thesaurus Term: CLUSTER analysis (Statistics); Thesaurus Term: CORRELATION (Statistics); Thesaurus Term: MULTIVARIATE analysis; Thesaurus Term: ALGORITHMS; Thesaurus Term: MATHEMATICS; Thesaurus Term: OPERATIONS research; NAICS/Industry Codes: 541614 Process, Physical Distribution, and Logistics Consulting Services; Number of Pages: 17p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - GEN
AU - Lebow, Irving
AU - Pflueger, Margaret L.
T1 - On-line input of descriptive cataloging
JO - In Waldron, Helen J., Ed.; Long, F. Raymond, Ed. Proceedings Of The American Society For Information Science. Volume 10. 36th Annual Meeting, Los Angeles, California, October 21-25, 1973. 1973. Greenwood Press, Westport, Connecticut. P. 188. 0 Ref. See Is
JF - In Waldron, Helen J., Ed.; Long, F. Raymond, Ed. Proceedings Of The American Society For Information Science. Volume 10. 36th Annual Meeting, Los Angeles, California, October 21-25, 1973. 1973. Greenwood Press, Westport, Connecticut. P. 188. 0 Ref. See Is
Y1 - 1973///
M3 - Book
AB - Descriptive cataloging and subject indexing via on on-line, real time system (pdp-10, two pdp-8's, 16 crt terminals, and associated hardware) at the technical information center of aec is presented. The data base developed supports recon, sdi. Inis tapes, and other computer services. Ten crt devices are utilized to input descriptive cataloging, four to input subject indexing, and two are used for programming and training. Input efficiency is improved, errors are promptly identified, noise level is lower, operator fatigue is less, complex schedule and much paper handling has been eliminated.
N1 - Accession Number: ISTA0901954; Lebow, Irving 1; Pflueger, Margaret L. 1; Affiliations: 1 : U.s. Atomic Energy Commission Technical Information Center, Oak Ridge, Tennessee.; Source Info: 1973; Note: Update Code: 0900; Document Type: Book
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DP - EBSCOhost
DB - lih
ER -
TY - GEN
AU - Gratton, Joseph G
AU - Wilson, John H., Jr.
T1 - Charging for products and services in the u.s. atomic energy commission
JO - In Waldron, Helen J., Ed.; Long, F. Raymond, Ed. Proceedings Of The American Society For Information Science. Volume 10. 36th Annual Meeting, Los Angeles, California, October 21-25, 1973. 1973. Greenwood Press, Westport, Connecticut. P. 239. 0 Ref. See Is
JF - In Waldron, Helen J., Ed.; Long, F. Raymond, Ed. Proceedings Of The American Society For Information Science. Volume 10. 36th Annual Meeting, Los Angeles, California, October 21-25, 1973. 1973. Greenwood Press, Westport, Connecticut. P. 239. 0 Ref. See Is
Y1 - 1973///
M3 - Book
AB - An effort is under way to raise revenues from products and services offered by the atomic energy commission and its contractors. Specific charging changes are discussed.
N1 - Accession Number: ISTA0901549; Gratton, Joseph G 1; Wilson, John H., Jr. 1; Affiliations: 1 : U.s. Atomic Energy Commission, Oak Ridge, Tennessee.; Source Info: 1973; Note: Update Code: 0900; Document Type: Book
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DP - EBSCOhost
DB - lih
ER -
TY - GEN
AU - Cape, James D
T1 - Descriptors for a printed subject index
JO - In Waldron, Helen J., Ed.; Long, F. Raymond, Ed. Proceedings Of The American Society For Information Science. Volume 10. 36th Annual Meeting, Los Angeles, California, October 21-25, 1973. 1973. Greenwood Press, Westport, Connecticut. P. 33-34. 2 Illus. 0
JF - In Waldron, Helen J., Ed.; Long, F. Raymond, Ed. Proceedings Of The American Society For Information Science. Volume 10. 36th Annual Meeting, Los Angeles, California, October 21-25, 1973. 1973. Greenwood Press, Westport, Connecticut. P. 33-34. 2 Illus. 0
Y1 - 1973///
M3 - Book
AB - The need to decrease cost of a subjecr index and the desire to use descriptors (keywords) assigned by contributors to international nuclear information system (inis) from other countries lead the aec (for nuclear science abstracts) and inis (for atomindex to consider alternatives to the subject-heading/modifier subject indexing up to july 1973. The subject descriptor/qualifying descriptor, title, and augmentation type of indexing was adopted. Selected descriptors (names of specific materials, things, properties, processes or concepts, but not items which describe from the inis thesaurus are specfic. Subject descriptors are selected from these and qualifying descriptors are chosen which have a logical relationship with the subject. Free language augmentation (within parentheses) of the title, or augmentation alone without the title and without parentheses appears below the subject descriptor/qualifier descriptor the new system requires no corrections solely for consistency of form, computer processing is simplified, and a subject-heading thesaurus in addition to a descriptor thesaurus is no longer required.
N1 - Accession Number: ISTA0901918; Cape, James D 1; Affiliations: 1 : U.s. Atomic Energy Commission; Source Info: 1973; Note: Update Code: 0900; Document Type: Book
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DP - EBSCOhost
DB - lih
ER -
TY - JOUR
AU - RABSON, ROBERT
AU - PLIMMER, JACK R.
T1 - Meetings.
JO - Science
JF - Science
Y1 - 1973/06/15/
VL - 180
IS - 4091
M3 - Article
SP - 1204
EP - 1205
SN - 00368075
N1 - Accession Number: 85158617; RABSON, ROBERT 1; PLIMMER, JACK R. 2; Affiliations: 1: Biology Branch, Division of Biomedical and Environmental Research, U.S. Atomic Energy Commission, Washington, D.C. 20545; 2: Pesticide Degradation Laboratory, Agricultural Environmental Quality Institute, U.S. Department of Agriculture, Beltsville, Maryland 20705; Issue Info: 6/15/1973, Vol. 180 Issue 4091, p1204; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - GEN
AU - Cape,james D
T1 - An analysis of world-wide contributions to nuclear science abstracts, volumes 25(1971) and 26 (1972)
JO - Tid-25710-r1. 1974 February. Technical Information Center, Office Of Information Services, U.s. Atomic Energy Commission, Oak Ridge, Tennessee. Iii + 76 P. 22 Illus. 3 Tab. 0 Ref
JF - Tid-25710-r1. 1974 February. Technical Information Center, Office Of Information Services, U.s. Atomic Energy Commission, Oak Ridge, Tennessee. Iii + 76 P. 22 Illus. 3 Tab. 0 Ref
Y1 - 1974///
M3 - Book Chapter
AB - The literature appearing in nuclear science abstracts (nsa) for the years 1971 and 1972 is analyzed in 3 tables, 22 figures, and 2 appendixes. The analysis includes the total number of literature items contributed arranged by country of author affiliation and broken down into type of literature: the number of items in each nsa subject category contributed by each major contributing country of author affiliation; the percent of items in each nsa category contributed by the major contributors; bar charts of the number of items in each nsa category since 1950; and lists of journals with the number of items appearing in nsa arranged by country of journal publication and in order of decreasing number of items.
N1 - Accession Number: ISTA0901745; Cape,james D 1; Affiliations: 1 : Office Of Information Services, U.s. Atomic Energy Commission, Oak Ridge, Tennessee.; Source Info: 1974; Note: Update Code: 0900; Document Type: Book Chapter
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DP - EBSCOhost
DB - lih
ER -
TY - GEN
AU - Dixon, William J.
AU - Walker, W. A.
AU - Hightower Jr., Wm. H.
AU - McCarty, Alice H.
AU - Burns, Howard J.
AU - Ammer, Christine
AU - Martini Jr., Emil P.
AU - Kaufman, Louis C.
AU - Walters, Alden G.
AU - Faragher, T. Robert
AU - Philip, W. W.
AU - Ray, Frederick G.
AU - Galbraith, John Kenneth
AU - Newburn, Robert M.
T1 - Letters to the Editor.
JO - Harvard Business Review
JF - Harvard Business Review
Y1 - 1974/07//Jul/Aug1974
VL - 52
IS - 4
M3 - Letter
SP - 150
SN - 00178012
AB - Several letters to the editor are presented in response to articles in previous issues including "Impact of Strategic Planning on Profit Performance," by Sidney Schoeffler, Robert D. Buzzell, and Donald F. Heany in the March-April 1974 issue, "Sex Stereotyping in the Executive Suite," by Benson Rosen and Thomas H. Jerdee in the March-April 1974 issue, and "Today the Shopping Center, Tomorrow the Superstore," by Walter J. Salmon, Robert D. Buzzell, and Stanton G. Cort in the January-February 1974 issue.
KW - STRATEGIC planning
KW - HYPERMARKETS
KW - SHOPPING centers
KW - LETTERS to the editor
KW - GENDER stereotypes
N1 - Accession Number: 3867186; Dixon, William J. 1; Walker, W. A. 2; Hightower Jr., Wm. H. 3; McCarty, Alice H.; Burns, Howard J. 4; Ammer, Christine 5; Martini Jr., Emil P. 6; Kaufman, Louis C. 7; Walters, Alden G. 8; Faragher, T. Robert 9; Philip, W. W. 10; Ray, Frederick G. 11; Galbraith, John Kenneth 12; Newburn, Robert M. 13; Affiliations: 1: President, Chicago, Rock Island and Pacific Railroad Company; 2: President, United States Steel Corporation; 3: President, Thomaston Mills; 4: Vice President, Recreation Products Group, Victor Comptometer Corporation; 5: Equal Employment Opportunity Task Force, National Organization for Women, Lexington, Massachusetts Chapter; 6: Chairman of the Board and President, Bergen Brunswig Corporation; 7: Sales Representative, East Coast, American Trade Magazines, Inc.; 8: Senior Vice President, Michigan National Bank; 9: President, National Bank of Commerce, Seattle, Washington; 10: President, Puget Sound National Bank; 11: Chairman of the Board and President, Rochester Savings Bank; 12: Paul M. Warburg Professor of Economics, Harvard University; 13: Personnel Officer, U.S. Atomic Energy Commission; Issue Info: Jul/Aug1974, Vol. 52 Issue 4, p150; Thesaurus Term: STRATEGIC planning; Thesaurus Term: HYPERMARKETS; Thesaurus Term: SHOPPING centers; Subject Term: LETTERS to the editor; Subject Term: GENDER stereotypes; NAICS/Industry Codes: 452910 Warehouse Clubs and Supercenters; NAICS/Industry Codes: 236220 Commercial and Institutional Building Construction; Number of Pages: 9p; Document Type: Letter
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Moore, Roger H.
T1 - Statistical Inference (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1975/12//
VL - 70
IS - 352
M3 - Book Review
SP - 966
SN - 01621459
AB - Reviews the book "Statistical Inference: Basic Concepts," by Richard B. Ellis.
KW - STATISTICS
KW - NONFICTION
KW - ELLIS, Richard B.
KW - STATISTICAL Inference: Basic Concepts (Book)
N1 - Accession Number: 4607103; Moore, Roger H. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Dec75, Vol. 70 Issue 352, p966; Thesaurus Term: STATISTICS; Subject Term: NONFICTION; Reviews & Products: STATISTICAL Inference: Basic Concepts (Book); People: ELLIS, Richard B.; Number of Pages: 1/3p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Moore, Roger H.
T1 - Statistical Distribution (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1975/12//
VL - 70
IS - 352
M3 - Book Review
SP - 966
SN - 01621459
AB - Reviews the book "Statistical Distributions: A Handbook for Students and Practitioners," by N.A.J. Hastings and J.B. Peacock.
KW - STATISTICS
KW - NONFICTION
KW - HASTINGS, N. A. J.
KW - PEACOCK, J. B.
KW - STATISTICAL Distributions: A Handbook for Students & Practitioners (Book)
N1 - Accession Number: 4607106; Moore, Roger H. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Dec75, Vol. 70 Issue 352, p966; Thesaurus Term: STATISTICS; Subject Term: NONFICTION; Reviews & Products: STATISTICAL Distributions: A Handbook for Students & Practitioners (Book); People: HASTINGS, N. A. J.; People: PEACOCK, J. B.; Number of Pages: 2p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Moore, Roger H.
T1 - Basic Ideas of Statistics/Introduction to Probability and Statistics, Fourth Edition/Elementary Statistics (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1976/09//
VL - 71
IS - 355
M3 - Book Review
SP - 772
SN - 01621459
AB - Reviews three books. "Basic Ideas of Statistics," by Bernard W. Lindgren; "Introduction to Probability and Statistics," 4th ed., by William Mendenhall; "Elementary Statistics," by G.A.F. Seber.
KW - NONFICTION
KW - MENDENHALL, William
KW - LINDGREN, Bernard W.
KW - SEBER, G. A. F.
KW - BASIC Ideas of Statistics (Book)
KW - INTRODUCTION to Probability & Statistics (Book)
KW - ELEMENTARY Statistics (Book)
N1 - Accession Number: 4607956; Moore, Roger H. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Sep76, Vol. 71 Issue 355, p772; Subject Term: NONFICTION; Reviews & Products: BASIC Ideas of Statistics (Book); Reviews & Products: INTRODUCTION to Probability & Statistics (Book); Reviews & Products: ELEMENTARY Statistics (Book); People: MENDENHALL, William; People: LINDGREN, Bernard W.; People: SEBER, G. A. F.; Number of Pages: 1/2p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Moore, Roger H.
T1 - Lecture Notes on Queueing Systems (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1976/09//
VL - 71
IS - 355
M3 - Book Review
SP - 773
SN - 01621459
AB - Reviews the book "Lecture Notes on Queueing Systems," by Brian Conolly.
KW - QUEUING theory
KW - NONFICTION
KW - CONOLLY, Brian
KW - LECTURE Notes on Queueing Systems (Book)
N1 - Accession Number: 4607989; Moore, Roger H. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Sep76, Vol. 71 Issue 355, p773; Thesaurus Term: QUEUING theory; Subject Term: NONFICTION; Reviews & Products: LECTURE Notes on Queueing Systems (Book); People: CONOLLY, Brian; Number of Pages: 2p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Moore, Roger H.
T1 - Fundamentals of Queueing Theory (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1977/03//
VL - 72
IS - 357
M3 - Book Review
SP - 232
SN - 01621459
AB - Reviews the book "Fundamentals of Queueing Theory," by Donald Gross and Carl M. Harris.
KW - QUEUING theory
KW - NONFICTION
KW - GROSS, Donald
KW - HARRIS, Carl
KW - HARRIS, Carl M.
KW - FUNDAMENTALS of Queueing Theory (Book)
N1 - Accession Number: 4607157; Moore, Roger H. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: Mar1977, Vol. 72 Issue 357, p232; Thesaurus Term: QUEUING theory; Subject Term: NONFICTION; Reviews & Products: FUNDAMENTALS of Queueing Theory (Book); People: GROSS, Donald; People: HARRIS, Carl; People: HARRIS, Carl M.; Number of Pages: 2p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Easterling, Robert G.
T1 - Reliability and Fault Tree Analysis (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1977/06//
VL - 72
IS - 358
M3 - Book Review
SP - 482
SN - 01621459
AB - Reviews the book "Reliability and Fault Tree Analysis: Theoretical and Applied Aspects of System Reliability and Safety Assessment," edited by R.E. Barlow, J.B. Fussel and N.D. Singpurwalla.
KW - STATISTICS
KW - NONFICTION
KW - BARLOW, R. E.
KW - FUSSEL, J. B.
KW - SINGPURWALLA, N. D.
KW - RELIABILITY & Fault Tree Analysis (Book)
N1 - Accession Number: 4608730; Easterling, Robert G. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Jun77, Vol. 72 Issue 358, p482; Thesaurus Term: STATISTICS; Subject Term: NONFICTION; Reviews & Products: RELIABILITY & Fault Tree Analysis (Book); People: BARLOW, R. E.; People: FUSSEL, J. B.; People: SINGPURWALLA, N. D.; Number of Pages: 2p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Moore, Roger H.
T1 - A Survey of the Literature on the Size Effect on Material Strength (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1978/06//
VL - 73
IS - 362
M3 - Book Review
SP - 446
SN - 01621459
AB - Reviews the book "A Survey of the Literature on the Size Effect on Material Strength," by H. Leon Harter.
KW - AIRFRAMES
KW - STRENGTH of materials
KW - NONFICTION
KW - HARTER, H. Leon
KW - SURVEY of the Literature on the Size Effect on Material Strength, A (Book)
N1 - Accession Number: 4603221; Moore, Roger H. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Jun78, Vol. 73 Issue 362, p446; Subject Term: AIRFRAMES; Subject Term: STRENGTH of materials; Subject Term: NONFICTION; Reviews & Products: SURVEY of the Literature on the Size Effect on Material Strength, A (Book); People: HARTER, H. Leon; Number of Pages: 1/5p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Moore, Roger H.
T1 - Sampling Inspection and Quality Control, 2nd Edition (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1978/06//
VL - 73
IS - 362
M3 - Book Review
SP - 446
SN - 01621459
AB - Reviews the book "Sampling Inspection and Quality Control," 2nd ed., by G. Barrie Wetherill.
KW - QUALITY control
KW - NONFICTION
KW - WETHERILL, G. Barrie
KW - SAMPLING Inspection & Quality Control (Book)
N1 - Accession Number: 4603232; Moore, Roger H. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Jun78, Vol. 73 Issue 362, p446; Thesaurus Term: QUALITY control; Subject Term: NONFICTION; Reviews & Products: SAMPLING Inspection & Quality Control (Book); People: WETHERILL, G. Barrie; Number of Pages: 1/5p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Abramson, Lee R.
T1 - Statistics and Public Policy (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1979/03//
VL - 74
IS - 365
M3 - Book Review
SP - 241
SN - 01621459
AB - Reviews the book "Statistics and Public Policy," edited by William B. Fairley and Frederick Mosteller.
KW - STATISTICS
KW - NONFICTION
KW - FAIRLEY, William
KW - FAIRLEY, William B.
KW - MOSTELLER, Frederick
KW - STATISTICS & Public Policy (Book)
N1 - Accession Number: 4613501; Abramson, Lee R. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Mar1979, Vol. 74 Issue 365, p241; Thesaurus Term: STATISTICS; Subject Term: NONFICTION; Reviews & Products: STATISTICS & Public Policy (Book); People: FAIRLEY, William; People: FAIRLEY, William B.; People: MOSTELLER, Frederick; Number of Pages: 3p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Stenberg, Carl W.
AU - Aron, Joan B.
T1 - CITIZEN PARTICIPATION AT GOVERNMENT EXPENSE.
JO - Public Administration Review
JF - Public Administration Review
Y1 - 1979/09//Sep/Oct79
VL - 39
IS - 5
M3 - Article
PB - Wiley-Blackwell
SN - 00333352
AB - Scholarly journals and the media have paid marked attention, within the past few years, to alternative measures for promoting participation in regulatory decision making as a step toward regulatory reform. The authors of this article are of the views that even if citizen groups have sufficient access to participate in an agency's decision-making process, they still need technical and legal information, time and resources to participate effectively. Despite agreement by many observers that a possible solution would be to compensate citizen groups for their use of legal and technical consultants, there has been little optimism on this score. Although the legislative creation of a consumer protection agency, an approach strongly favored by the new administration to present consumer interests in regulatory proceedings, once again was defeated in Congress, the demise of the consumer agency, for the near future at least, may have provided the impetus for resorting to more radical measures for protecting consumer interests.
KW - DECISION making
KW - PUBLIC administration
KW - PROBLEM solving
KW - INFORMATION resources
KW - POLITICAL participation
KW - SCHOLARLY periodicals
KW - LAW reform
N1 - Accession Number: 4601652; Stenberg, Carl W.; Aron, Joan B. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Sep/Oct79, Vol. 39 Issue 5; Thesaurus Term: DECISION making; Thesaurus Term: PUBLIC administration; Thesaurus Term: PROBLEM solving; Thesaurus Term: INFORMATION resources; Subject Term: POLITICAL participation; Subject Term: SCHOLARLY periodicals; Subject Term: LAW reform; NAICS/Industry Codes: 921190 Other General Government Support; NAICS/Industry Codes: 323111 Commercial Printing (except Screen and Books); NAICS/Industry Codes: 323119 Other printing; NAICS/Industry Codes: 511120 Periodical Publishers; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dresher, Melvin
AU - Moglewer, Sidney
T1 - Statistical Acceptance Sampling in a Competitive Environment.
JO - Operations Research
JF - Operations Research
Y1 - 1980/05//May/Jun80 Part 1 of 2
VL - 28
IS - 3
M3 - Article
SP - 503
PB - INFORMS: Institute for Operations Research
SN - 0030364X
AB - This paper presents a model and its solution for a statistical acceptance sample inventory problem in a competitive environment. The model is based upon the theory of games and is applied to a nuclear material accounting example. A game is formulated between a diverter who might deliberately steal valuable nuclear material and a defender who must make references based upon inventory difference. The diverter controls the mean of the inventory difference distribution which is not known by the defender. The solution presents a policy for the defender to estimate this distribution mean as well as other information to be used as the basis for additional statistical inferences. [ABSTRACT FROM AUTHOR]
AB - Copyright of Operations Research is the property of INFORMS: Institute for Operations Research and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SAMPLING (Statistics)
KW - INVENTORY control
KW - MATHEMATICAL statistics
KW - DISTRIBUTION (Probability theory)
KW - STATISTICS
KW - GAMES
KW - THEORY
KW - MODELS & modelmaking
KW - COMPETITION (Psychology)
N1 - Accession Number: 4474787; Dresher, Melvin 1; Moglewer, Sidney 2; Affiliations: 1: Consultant, Pacific Palisades, California.; 2: U.S. Nuclear Regulatory Commission, Washington, D.C.; Issue Info: May/Jun80 Part 1 of 2, Vol. 28 Issue 3, p503; Thesaurus Term: SAMPLING (Statistics); Thesaurus Term: INVENTORY control; Thesaurus Term: MATHEMATICAL statistics; Thesaurus Term: DISTRIBUTION (Probability theory); Thesaurus Term: STATISTICS; Subject Term: GAMES; Subject Term: THEORY; Subject Term: MODELS & modelmaking; Subject Term: COMPETITION (Psychology); NAICS/Industry Codes: 451120 Hobby, Toy, and Game Stores; NAICS/Industry Codes: 423920 Toy and Hobby Goods and Supplies Merchant Wholesalers; NAICS/Industry Codes: 339930 Doll, Toy, and Game Manufacturing; NAICS/Industry Codes: 561990 All Other Support Services; NAICS/Industry Codes: 541614 Process, Physical Distribution, and Logistics Consulting Services; NAICS/Industry Codes: 541910 Marketing Research and Public Opinion Polling; Number of Pages: 9p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
TY - GEN
AU - DelMedico, J.;
T1 - NRC's approach to nuclear pharmacy education
CT - NRC's approach to nuclear pharmacy education
JO - American Pharmacy (USA)
JF - American Pharmacy (USA)
Y1 - 1981/10/01/
VL - NS21
IS - Oct
SP - 48
EP - 49
SN - 01603450
AD - U.S. Nuclear Regulatory Commission, Washington, DC 20555
N1 - Accession Number: 19-01893; Language: English; Journal Coden: AMPHDF; Section Heading: Pharmaceutical Education; Legislation, Laws and Regulations; Abstract Author: Elvira deC. Weiss
N2 - The Nuclear Regulatory Commission's criteria for nuclear pharmacy education and licensing of commercial radiopharmacies and personnel are presented.
KW - Education, pharmaceutical--radiopharmacy--criteria, NRC;
KW - Radiopharmacy--education, pharmaceutical--criteria, NRC;
KW - Nuclear Regulatory Commission--radiopharmacy--licensure, criteria;
KW - Licensure--radiopharmacy--criteria, NRC;
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DP - EBSCOhost
DB - ipa
ER -
TY - JOUR
AU - Moglewer, Sidney
T1 - IAEA safeguards and non-proliferation.
JO - Bulletin of the Atomic Scientists
JF - Bulletin of the Atomic Scientists
Y1 - 1981/10//
VL - 37
IS - 8
M3 - Article
SP - 24
EP - 29
PB - Bulletin of the Atomic Scientists
SN - 00963402
N1 - Accession Number: 24226676; Moglewer, Sidney 1; Affiliation: 1: Senior Operation Research Analyst, U.S. Nuclear Regulatory Commission.; Source Info: Oct1981, Vol. 37 Issue 8, p24; Number of Pages: 6p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Moglewer, Sidney
T1 - On IAEA safeguards.
JO - Bulletin of the Atomic Scientists
JF - Bulletin of the Atomic Scientists
Y1 - 1982/03//
VL - 38
IS - 3
M3 - Article
SP - 41
EP - 42
PB - Bulletin of the Atomic Scientists
SN - 00963402
N1 - Accession Number: 24226552; Moglewer, Sidney 1; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.; Source Info: Mar1982, Vol. 38 Issue 3, p41; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Lurie, Dan
T1 - Probability & Statistics in Particle Physics (Book).
JO - Journal of the American Statistical Association
JF - Journal of the American Statistical Association
Y1 - 1982/06//
VL - 77
IS - 378
M3 - Book Review
SP - 497
EP - 497
SN - 01621459
AB - Reviews the book "Probability and Statistics in Particle Physics," by A.G. Frodesen, O. Skjeggestad, and H. Tofte.
KW - MATHEMATICAL statistics
KW - NONFICTION
KW - FRODESEN, A. G.
KW - SKJEGGESTAD, O.
KW - TOFTE, H.
KW - PROBABILITY & Statistics in Particle Physics (Book)
N1 - Accession Number: 4603493; Lurie, Dan 1; Affiliations: 1: U.S. Nuclear Regulatory Commission.; Issue Info: Jun82, Vol. 77 Issue 378, p497; Thesaurus Term: MATHEMATICAL statistics; Subject Term: NONFICTION; Reviews & Products: PROBABILITY & Statistics in Particle Physics (Book); People: FRODESEN, A. G.; People: SKJEGGESTAD, O.; People: TOFTE, H.; Number of Pages: 1/4p; Document Type: Book Review
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Mark, J. Carson
T1 - Research, development and production.
JO - Bulletin of the Atomic Scientists
JF - Bulletin of the Atomic Scientists
Y1 - 1983/03//
VL - 39
IS - 3
M3 - Article
SP - 45
EP - 51
PB - Bulletin of the Atomic Scientists
SN - 00963402
N1 - Accession Number: 24226202; Mark, J. Carson 1; Affiliation: 1: Chairman of Advisory Committee on Reactor Safeguards of U S Nuclear Regulatory Commission.; Source Info: Mar1983, Vol. 39 Issue 3, p45; Number of Pages: 7p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Menczer, William B.
T1 - States' Role in Radioactive Waste.
JO - Public Administration Review
JF - Public Administration Review
Y1 - 1985/05//May/Jun85
VL - 45
IS - 3
M3 - Letter
SP - 450
PB - Wiley-Blackwell
SN - 00333352
AB - Presents a letter to the editor regarding protection of public health and safety.
KW - GOVERNMENT policy
KW - STATE governments
KW - LETTERS to the editor
KW - RADIOACTIVE wastes
KW - PUBLIC health
KW - NUCLEAR energy -- Law & legislation
KW - UNITED States
N1 - Accession Number: 4601437; Menczer, William B. 1; Affiliations: 1: Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission.; Issue Info: May/Jun85, Vol. 45 Issue 3, p450; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: STATE governments; Subject Term: LETTERS to the editor; Subject Term: RADIOACTIVE wastes; Subject Term: PUBLIC health; Subject Term: NUCLEAR energy -- Law & legislation; Subject: UNITED States; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 525120 Health and Welfare Funds; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562210 Waste treatment and disposal; Number of Pages: 1/3p; Document Type: Letter
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Mazuzan, George T.
T1 - Counsels of War.
JO - Journal of American History
JF - Journal of American History
Y1 - 1985/12//
VL - 72
IS - 3
M3 - Book Review
SP - 740
EP - 741
SN - 00218723
AB - Reviewed: Counsels of War. Herken, Gregg.
KW - MILITARY strategy
KW - NONFICTION
KW - NUCLEAR weapons
KW - BOOKS -- Reviews
KW - INTELLECTUALS
KW - MILITARY policy
KW - ARMS control
KW - Herken, Gregg
KW - HERKEN, Gregg
KW - COUNSELS of War (Book)
N1 - Accession Number: 15713815; Mazuzan, George T. 1; Affiliations: 1 : United States Nuclear Regulatory Commission; Source Info: Dec1985, Vol. 72 Issue 3, p740; Note: Publication Information: New York: Knopf, 1985. 409 pp.; Historical Period: 1945 to 1984; Subject Term: MILITARY strategy; Subject Term: NONFICTION; Subject Term: NUCLEAR weapons; Subject Term: BOOKS -- Reviews; Subject Term: INTELLECTUALS; Subject Term: MILITARY policy; Subject Term: ARMS control; Number of Pages: 2p; Document Type: Book Review
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DP - EBSCOhost
DB - ahl
ER -
TY - GEN
AU - Bender, A
T1 - Optical disc-based system for information management
JO - Proceedings of Optical Publishing & Storage '87, Conference on Applications of Optical Information Systems in Publishing
JF - Proceedings of Optical Publishing & Storage '87, Conference on Applications of Optical Information Systems in Publishing
Y1 - 1987///
M3 - Conference Paper
SP - 5
EP - 8
SN - 0938734229
AB - The author reports on the development of a microcomputer-based optical disc system from the Nuclear Regulatory Commission which provides a unique approach for storing and retrieving licensing documents. Capabilities which are discussed include the performance by a user to do a full text search and retrieve either the ascii or the original digital image of the document. The NRC's plans for this system apply to the three year license review requirement mandated by the Nuclear Waste Policy Act for millions of documents which will be reviewed by the mid-1990s. System hardware is fully described and the database creation process explored, in relation to implementation issues as well as potential pitfalls of relying on this new optical technology. There is a brief comparison made between WORM and CD-ROM as possible storage media. Proceeding Published by Learned Information, Inc., United States, 1987
KW - DOCUMENT delivery
KW - INFORMATION technology
KW - Disk storage
KW - Information management
N1 - Accession Number: ISTA2301155; Bender, A 1; Affiliations: 1 : U.S. Nuclear Regulatory Commission, Washington, DC; Source Info: 1987, p5; Note: Place of Publication: United States; Note: Publisher: Learned Information, Inc.; Note: Update Code: 2300; Note: Conference Title: Proceedings of Optical Publishing & Storage '87, Conference on Applications of Optical Information Systems in Publishing; Note: Conference Location: New York, NY; Note: Conference Dates: November 11-13, 1987; Subject Term: DOCUMENT delivery; Subject Term: INFORMATION technology; Author-Supplied Keyword: Disk storage; Author-Supplied Keyword: Information management; Number of Pages: 4p; Document Type: Conference Paper
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DP - EBSCOhost
DB - lih
ER -
TY - GEN
AU - Bender, A
T1 - Optical disc based full text search and image retrival system for records management
JO - Proceedings of the National Online Meeting
JF - Proceedings of the National Online Meeting
Y1 - 1987///
M3 - Conference Paper
SP - 39
EP - 40
SN - 0938734172
AB - This article describes an online records management system developed by the U.S. Nuclear Regulatory Commission, which provides for full text search and retrieval. It is a microcomputer based system which provides user access to both ASCII text and the original image of the document on a single high resolution, split screen monitor. Proceeding Published by Learned Information, Inc., United States, 1987
KW - COMPUTER systems
KW - POLITICAL science
KW - Disk storage
KW - Images
N1 - Accession Number: ISTA2201935; Bender, A 1; Affiliations: 1 : U.S. Nuclear Regulatory Commission; Source Info: 1987, p39; Note: Place of Publication: United States; Note: Publisher: Learned Information, Inc.; Note: Update Code: 2200; Note: Conference Title: Proceedings of the National Online Meeting; Note: Conference Location: New York, NY; Note: Conference Dates: May 5-7, 1987; Subject Term: COMPUTER systems; Subject Term: POLITICAL science; Author-Supplied Keyword: Disk storage; Author-Supplied Keyword: Images; Number of Pages: 2p; Document Type: Conference Paper
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DP - EBSCOhost
DB - lih
ER -
TY - GEN
AU - Bender, A
T1 - Text/image management and optical disk system design
JO - Inform
JF - Inform
Y1 - 1987/02//
VL - 1
IS - 2
M3 - Article
SP - 20
EP - 24
SN - 08923876
AB - Optical disk systems have created new opportunities for text and image management. A number of available systems which are available today and offer the capability for scanning and storing documents on optical disk are reviewed. Database opportunities include full text storage and retrieval management systems. The process of converting a document to a searchable electronic image is presented.
KW - DATABASES
KW - IMAGE processing
KW - Disk storage
KW - Information retrieval systems
N1 - Accession Number: ISTA2104677; Bender, A 1; Affiliations: 1 : US Nuclear Regulatory Commission, Washington, DC; Source Info: Feb 1987, Vol. 1 Issue 2, p20; Note: Update Code: 2100; Subject Term: DATABASES; Subject Term: IMAGE processing; Author-Supplied Keyword: Disk storage; Author-Supplied Keyword: Information retrieval systems; Number of Pages: 5p; Document Type: Article
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DP - EBSCOhost
DB - lih
ER -
TY - GEN
AU - Bender, A
T1 - Optical disc technology for records management: a user perspective
JO - Electronic Library
JF - Electronic Library
Y1 - 1987/10//
VL - 5
IS - 5
M3 - Article
SP - 276
EP - 281
SN - 02640473
AB - The United States Nuclear Regulatory Commission is completing a pilot project which demonstrates a unique application of Worm-based optical disc technology for the storage and retrieval of government records. Information which is captured at the source or from an optical character reader is stored on the disc in the form of the ASCII text and the original image of the complete document. The full text search software and indexes to the images are all stored on the optical disc. In this way a user can perform a full text search on the records and retrieve either the ASCII or the original document. By combining full text search and image retrieval, significant improvement in recall and precision are achieved when compared to traditional simple indexing techniques.
KW - INFORMATION retrieval
KW - Disk storage
KW - Government documents
KW - Information management
N1 - Accession Number: ISTA2300879; Bender, A 1; Affiliations: 1 : United States Nuclear Regulatory Commission, Washington, DC; Source Info: Oct 1987, Vol. 5 Issue 5, p276; Note: Update Code: 2300; Subject Term: INFORMATION retrieval; Author-Supplied Keyword: Disk storage; Author-Supplied Keyword: Government documents; Author-Supplied Keyword: Information management; Number of Pages: 6p; Document Type: Article
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DP - EBSCOhost
DB - lih
ER -
TY - GEN
AU - Bender, A
T1 - An optical disk-based information retrieval system
JO - Library Hi Tech
JF - Library Hi Tech
Y1 - 1988///
VL - 6
IS - 3
M3 - Article
SP - 81
EP - 85
SN - 07378831
AB - This article describes the Nuclear Regulatory Commission's pilot program to demonstrate the application of advanced text and image processing technology for the storage and retrieval of documents relating to its waste management program. The system consists of a text database and an image database, both stored in an optical disk. The two databases are linked by a common accession number. The operator scans the pages as they appear on the monitor, and flags those pages to be converted to ASCII. Thus it is not necessary to convert the full document to get at the needed information. Image files are sent electronically to an optical character reader which processes them in off hours. The system duplicates the physical and cognitive processes that a librarian undertakes in a search: browsing, extracting, manipulating text, and generating records.
KW - IMAGE processing
KW - Disk storage
KW - Federal government
KW - Government documents
N1 - Accession Number: ISTA2303214; Bender, A 1; Affiliations: 1 : US Nuclear Regulatory Commission; Source Info: 1988, Vol. 6 Issue 3, p81; Note: Update Code: 2300; Subject Term: IMAGE processing; Author-Supplied Keyword: Disk storage; Author-Supplied Keyword: Federal government; Author-Supplied Keyword: Government documents; Number of Pages: 5p; Document Type: Article
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DP - EBSCOhost
DB - lih
ER -
TY - JOUR
AU - Walker, J. Samuel
T1 - Klau fuchs, Atom Spy.
JO - Journal of American History
JF - Journal of American History
Y1 - 1988/09//
VL - 75
IS - 2
M3 - Book Review
SP - 673
EP - 673
SN - 00218723
AB - Reviewed: Klaus Fuchs, Atom Spy. Williams, Robert Chadwell.
KW - SPIES
KW - NONFICTION
KW - NUCLEAR weapons
KW - BOOKS -- Reviews
KW - HYDROGEN bomb
KW - ESPIONAGE
KW - SOVIET Union
KW - Williams, Robert Chadwell
KW - CHADWELL, Robert
KW - FUCHS, Klaus Emil Julius, 1911-1988
KW - KLAUS Fuchs: Atom Spy (Book)
N1 - Accession Number: 15424678; Walker, J. Samuel 1; Affiliations: 1 : United States Nuclear Regulatory Commission; Source Info: Sep1988, Vol. 75 Issue 2, p673; Note: Publication Information: Cambridge, Mass.: Harvard U. Pr., 1987. 267 pp.; Historical Period: 1942 to 1950; Subject Term: SPIES; Subject Term: NONFICTION; Subject Term: NUCLEAR weapons; Subject Term: BOOKS -- Reviews; Subject Term: HYDROGEN bomb; Subject Term: ESPIONAGE; Subject: SOVIET Union; Number of Pages: 2/3p; Document Type: Book Review
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DP - EBSCOhost
DB - ahl
ER -
TY - JOUR
AU - Walker, J. Samuel
T1 - The Controversy Over Radiation Safety.
JO - JAMA: Journal of the American Medical Association
JF - JAMA: Journal of the American Medical Association
Y1 - 1989/08/04/
VL - 262
IS - 5
M3 - Article
SP - 664
EP - 668
SN - 00987484
AB - Presents a historical overview of the controversy over radiation safety. Concern on the hazards of ionizing radiation after the discovery of x-rays and natural radioactivity in the 1890s; Proposition for radiation safety and limitations on exposure after misuse of x-rays and radium; Increase of radiation research during World War II; Public concern over radioactive fallouts from atmospheric bomb testing in the 1950s and 60s.
KW - RADIATION -- Safety measures
KW - X-rays
KW - RADIUM
KW - RADIOACTIVE fallout
N1 - Accession Number: 10940895; Walker, J. Samuel 1; Affiliation: 1: Historian, US Nuclear Regulatory Commission, Washington; Source Info: 8/4/89, Vol. 262 Issue 5, p664; Subject Term: RADIATION -- Safety measures; Subject Term: X-rays; Subject Term: RADIUM; Subject Term: RADIOACTIVE fallout; Number of Pages: 5p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Walker, J. Samuel
T1 - The Controversy Over Radiation Safety.
JO - JAMA: Journal of the American Medical Association
JF - JAMA: Journal of the American Medical Association
Y1 - 1989/08/04/
VL - 262
IS - 5
M3 - Article
SP - 664
EP - 668
SN - 00987484
AB - Presents a historical overview of the controversy over radiation safety. Concern on the hazards of ionizing radiation after the discovery of x-rays and natural radioactivity in the 1890s; Proposition for radiation safety and limitations on exposure after misuse of x-rays and radium; Increase of radiation research during World War II; Public concern over radioactive fallouts from atmospheric bomb testing in the 1950s and 60s.
KW - RADIATION -- Safety measures
KW - X-rays
KW - RADIUM
KW - RADIOACTIVE fallout
N1 - Accession Number: 10940895; Walker, J. Samuel 1; Source Information: 8/4/89, Vol. 262 Issue 5, p664; Subject: RADIATION -- Safety measures; Subject: X-rays; Subject: RADIUM; Subject: RADIOACTIVE fallout; Number of Pages: 5p; Document Type: Article
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DP - EBSCOhost
DB - hch
ER -
TY - JOUR
AU - Salzberg, Allan M.
AU - Dolins, Stanley L.
AU - Salzberg, Carol A.
AU - Salzberg, A M
AU - Dolins, S L
AU - Salzberg, C A
T1 - Modeling the spread of HIV.
JO - JAMA: Journal of the American Medical Association
JF - JAMA: Journal of the American Medical Association
Y1 - 1989/09/08/
VL - 262
IS - 10
M3 - commentary
SP - 1329
EP - 1331
SN - 00987484
AB - Comments on the article 'HIV-1 Infection Among Intravenous Drug Users in Manhattan, New York City From 1977 through 1987,' by Des Jarlais et al, as presented in a 1989 issue of the 'Journal of the American Medical Association.'
KW - HIV infections
KW - INTRAVENOUS drug abuse
KW - MANHATTAN (New York, N.Y.)
N1 - Accession Number: 10940939; Salzberg, Allan M. 1 Dolins, Stanley L. 2 Salzberg, Carol A. 3 Salzberg, A M Dolins, S L Salzberg, C A; Affiliation: 1: Veterans Administration Medical Service, Miles City, Mont 2: US Nuclear Regulatory Commission, Washington, DC 3: Miles City (Mont) Community College; Source Info: 9/8/89, Vol. 262 Issue 10, p1329; Subject Term: HIV infections; Subject Term: INTRAVENOUS drug abuse; Subject Term: MANHATTAN (New York, N.Y.); Number of Pages: 3p; Illustrations: 1 Graph; Document Type: commentary
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Walker, J. Samuel
T1 - Perversions of Medical Technology.
JO - JAMA: Journal of the American Medical Association
JF - JAMA: Journal of the American Medical Association
Y1 - 1990/02/23/
VL - 263
IS - 8
M3 - Letter
SP - 1067
EP - 1067
SN - 00987484
AB - Replies to comments on an article, previously published in the 'Journal of American Medical Association,' concerning alleged perversions in medical technology in the United States.
KW - MEDICAL technology
KW - TECHNOLOGY
KW - PERIODICALS
KW - UNITED States
N1 - Accession Number: 11021051; Walker, J. Samuel 1; Affiliation: 1: US Nuclear Regulatory Commission, Washington, DC; Source Info: 2/23/90, Vol. 263 Issue 8, p1067; Subject Term: MEDICAL technology; Subject Term: TECHNOLOGY; Subject Term: PERIODICALS; Subject Term: UNITED States; NAICS/Industry Codes: 423450 Medical, Dental, and Hospital Equipment and Supplies Merchant Wholesalers; NAICS/Industry Codes: 339113 Surgical Appliance and Supplies Manufacturing; NAICS/Industry Codes: 339112 Surgical and Medical Instrument Manufacturing; NAICS/Industry Codes: 414420 Book, periodical and newspaper merchant wholesalers; NAICS/Industry Codes: 424920 Book, Periodical, and Newspaper Merchant Wholesalers; NAICS/Industry Codes: 451212 News Dealers and Newsstands; NAICS/Industry Codes: 451310 Book stores and news dealers; NAICS/Industry Codes: 323119 Other printing; Number of Pages: 1/9p; Document Type: Letter
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Wood, Robert
AD - US Nuclear Regulatory Commission
T1 - Federal Regulation of Decommissioning Economics
JO - Energy Journal
JF - Energy Journal
Y1 - 1991///Special Issue
VL - 12
SP - 45
EP - 54
SN - 01956574
N1 - Accession Number: 0245272; Keywords: Regulation; Geographic Descriptors: U.S.; Geographic Region: Northern America; Publication Type: Journal Article; Update Code: 199109
KW - Energy: Government Policy Q48
KW - Alternative Energy Sources Q42
KW - Economics of Regulation L51
KW - Electric Utilities L94
L3 - http://www.iaee.org/en/publications/journal.aspx
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=ecn&AN=0245272&site=ehost-live&scope=site
UR - http://www.iaee.org/en/publications/journal.aspx
DP - EBSCOhost
DB - ecn
ER -
TY - CHAP
AU - Walker, J. Samuel
AD - US Nuclear Regulatory Commission
A2 - LaFollette, Marcel C.
A2 - Stine, Jeffrey K.
T1 - Nuclear Power and the Environment: The Atomic Energy Commission and Thermal Pollution, 1965-1971
T2 - Technology and choice: Readings from technology and culture
PB - Chicago and London:
PB - University of Chicago Press
Y1 - 1991///
SP - 203
EP - 231
RP - [1989]
N1 - Accession Number: 0335307; Reviewed Book ISBN: 0-226-46777-5; Keywords: Atomic Energy; Energy; Environment; Nuclear; Pollution; Geographic Descriptors: U.S.; Geographic Region: Northern America; Publication Type: Collective Volume Article; Update Code: 199412
KW - Renewable Resources and Conservation: Water Q25
KW - Alternative Energy Sources Q42
KW - Economic History: Transport, Trade, Energy, Technology, and Other Services: U.S.; Canada: 1913- N72
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DP - EBSCOhost
DB - ecn
ER -
TY - JOUR
TY - GEN
AU - Serig, D. I.;
T1 - Ergonomic problem identification
CT - Ergonomic problem identification
JO - ASHP Midyear Clinical Meeting
JF - ASHP Midyear Clinical Meeting
Y1 - 1994/12/01/
VL - 29
IS - Dec
SP - PI
EP - 59
AD - U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, USA
N1 - Accession Number: 31-12145; Language: English; Publication Type: Abstract of Meeting Presentation; Section Heading: Sociology, Economics and Ethics
N2 - Reducing adverse outcomes requires knowledge of both the causes and consequences of human error specific to a particular health system. That information is best acquired by a multi-disciplinary team. The team first identifies health system goals, functions, and tasks (i.e., what people are both explicitly and implicitly required to do). The team then identifies factors which might result in human error (i.e., cause a mismatch between what persons within the system are required to do and what those persons might reasonably be expected to do). The team then assesses the likelihood and likely adverse outcomes of possible errors. Learning objectives: 1) The participant should be able to identify potential members of the multidisciplinary ergonomic team. 2) The participant should be able to assist in identifying goals, functions, and tasks within their health system. 3) The participant should be able to assist in identifying potential mismatches between what persons within their health system are required to do and what those persons can reasonably be expected to do. 4) The participant should be able to assist in identifying the likelihood and system consequence of the various errors in their health system. Self-assessment questions: 1) Why is problem identification best accomplished by a multi-disciplinary ergonomics team and who are potential members? 2) What provides the framework upon which a system performance oriented approach to ergonomic evaluation is built? 3) Name several classes of factors which might contribute to mismatches between what persons within a health system are required to do and what those persons can reasonably be expected to do. 4) Identify some factors which might help determine the consequences of a particular error? Answers: 1) Problem identification is best accomplished by a multidisciplinary team because a single individual seldom has both the needed breadth and depth of knowledge (i.e., knowledge of system goals, functions, and tasks; knowledge of factors which can affect performance of tasks; and knowledge of the potential consequences of human error within the system). 2) The framework for a system performance oriented approach to ergonomic evaluation is a function and task analysis. 3) Some classes of factors which might contribute to mismatches between human-system interfaces, procedures, training, and organization practices. 4) Some factors related to the consequences of a particular error are the potential biological consequences of an error, whether the error's effects are episodic (i.e., affects a single dose to a single patient), programmatic (i.e., affects several or all doses to a single patient), or systematic (i.e., affects several or all doses to a number of patients); and w ether detection and correction of mitigation is possible.
KW - ASHP meeting abstracts--health systems, human error;
KW - Errors--health care--human;
KW - Health care--errors--human;
KW - Team--health care--human errors, identification;
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DP - EBSCOhost
DB - ipa
ER -
TY - JOUR
TY - GEN
AU - Serig, D. I.;
T1 - Ergonomics in health systems
CT - Ergonomics in health systems
JO - ASHP Midyear Clinical Meeting
JF - ASHP Midyear Clinical Meeting
Y1 - 1994/12/01/
VL - 29
IS - Dec
SP - PI
EP - 57
AD - U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, USA
N1 - Accession Number: 31-12146; Language: English; Publication Type: Abstract of Meeting Presentation; Section Heading: Sociology, Economics and Ethics
N2 - Health system events with adverse outcomes are frequently attributed to human error. Ergonomists define human error simply as a deviation in task performance from a specified standard. In the broadest sense, human error in health and other systems occurs as the consequence of mismatches between what the systems require persons within them to do and what those persons can reasonably be expected to do. Ergonomists seek to identify factors which contribute to mismatches and error in health systems, to determine which errors can lead to unacceptable outcomes, and to design, test, and implement health system modifications which will reduce the possibility and potential severity of adverse outcomes related to human error. Learning objectives: 1) The participant should be able to define human error in a systems context. 2) The participant should be able to use the concept of mismatches between what a system requires a person to do and what that person can be reasonably expected to do to identify error likely situations. 3) The participant should be able to describe the goal of ergonomics with respect to health systems. Self-assessment questions: 1) In a systems context, what is human error? 2) In the broadest sense, to what do ergonomists attribute human error? 3) What are the goals of ergonomics with respect to health systems? Answers: 1) Human error is a deviation in task performance from a specified standard. 2) In the broadest sense, ergonomists attribute human error to mismatches between what persons within a system are required to do and what those persons can be reasonably expected to do. 3) The goals of ergonomics with respect to health systems are to identify factors which contribute to mismatches and error, to determine which errors can lead to unacceptable outcomes, and to design, test, and implement modifications which will reduce the possibility and potential severity of adverse outcomes related to human error.
KW - ASHP meeting abstracts--health systems, human error;
KW - Errors--health care--human;
KW - Health care--errors--human;
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DP - EBSCOhost
DB - ipa
ER -
TY - JOUR
AU - Paperiello, C.J.
T1 - Risk assessment and risk management implications of hormesis.
JO - Human & Experimental Toxicology
JF - Human & Experimental Toxicology
Y1 - 1998/08//
VL - 17
IS - 8
M3 - Article
SP - 460
EP - 462
PB - Sage Publications, Ltd.
SN - 09603271
AB - Discusses the risk management and risk assessment efforts of the United States Nuclear Regulatory Commission toward the implications of hormesis in public health. Discussion on the regulation of ionizing radiation protection standards in the country; Importance of risk management in the creation of risk regulation; How the possible change in the linear no-threshold model for the effect of low level ionizing radiation can impact radiation exposure in the country.
KW - HORMESIS
KW - RISK management in business
KW - RISK assessment
KW - PUBLIC health -- United States
KW - UNITED States
KW - hormesis
KW - radiation
KW - risk assessment
KW - risk management
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 4664060; Paperiello, C.J. 1; Affiliation: 1: US Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, 11545 Rockville Pike (T-8A23), Maryland 20852, USA; Source Info: 1998, Vol. 17 Issue 8, p460; Subject Term: HORMESIS; Subject Term: RISK management in business; Subject Term: RISK assessment; Subject Term: PUBLIC health -- United States; Subject Term: UNITED States; Author-Supplied Keyword: hormesis; Author-Supplied Keyword: radiation; Author-Supplied Keyword: risk assessment; Author-Supplied Keyword: risk management; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Lane, J. Charles
T1 - CON...What opponents say: .
JO - Journal of Accountancy
JF - Journal of Accountancy
Y1 - 2001/09//
VL - 192
IS - 3
M3 - Letter
SP - 84
EP - 84
PB - American Institute of Ceritified Public Accountants
SN - 00218448
AB - Presents a letter to the editor about the global business credential proposed by the American Institute of Certified Public Accountants.
KW - ACCOUNTING
KW - LETTERS to the editor
N1 - Accession Number: 5088636; Lane, J. Charles 1; Affiliations: 1: U.S. Nuclear Regulatory Commission Rockville, Maryland.; Issue Info: Sep2001, Vol. 192 Issue 3, p84; Thesaurus Term: ACCOUNTING; Subject Term: LETTERS to the editor; NAICS/Industry Codes: 541219 Other Accounting Services; Number of Pages: 1/4p; Document Type: Letter; Full Text Word Count: 1016
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Sorensen, J.N.
T1 - Safety culture: a survey of the state-of-the-art
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2002/05//
VL - 76
IS - 2
M3 - Article
SP - 189
SN - 09518320
AB - This paper discusses the evolution of the term ‘safety culture’ and the perceived relationship between safety culture and safety of operations in nuclear power generation and other hazardous technologies. There is a widespread belief that safety culture is an important contributor to safety of operations. Empirical evidence that safety culture and other management and organizational factors influence operational safety is more readily available for the chemical process industry than for nuclear power plant operations. The commonly accepted attributes of safety culture include good organizational communications, good organizational learning, and senior management commitment to safety. Safety culture may be particularly important in reducing latent errors in complex, well-defended systems. The role of regulatory bodies in fostering strong safety cultures remains unclear, and additional work is required to define the essential attributes of safety culture and to identify reliable performance indicators. [ABSTRACT FROM AUTHOR]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SAFETY
KW - RELIABILITY (Personality trait)
KW - SAFETY regulations
KW - Human reliability
KW - Safety culture
KW - Safety regulation
N1 - Accession Number: 7806598; Sorensen, J.N. 1; Email Address: jns@nrc.gov; Affiliation: 1: Advisory Committee on Reactor Safeguards, US Nuclear Regulatory Commission, Mail Stop 013 D13, Washington, DC 20555-0001, USA; Source Info: May2002, Vol. 76 Issue 2, p189; Subject Term: SAFETY; Subject Term: RELIABILITY (Personality trait); Subject Term: SAFETY regulations; Author-Supplied Keyword: Human reliability; Author-Supplied Keyword: Safety culture; Author-Supplied Keyword: Safety regulation; NAICS/Industry Codes: 926120 Regulation and Administration of Transportation Programs; Number of Pages: 16p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Schay, Brigitte W.
AU - Beach, Mary Ellen
AU - Caldwell, Jacqueline A.
AU - LaPolice, Christelle
T1 - USING STANDARDIZED OUTCOME MEASURES IN THE FEDERAL GOVERNMENT.
JO - Human Resource Management
JF - Human Resource Management
Y1 - 2002///Fall2002
VL - 41
IS - 3
M3 - Article
SP - 355
SN - 00904848
AB - The article proposes the use of standardized balanced measures for assessing the performance and results of the U.S. federal agencies. Since most federal agencies do not have an easily identifiable bottom line, use of balanced measures provides more realistic information on agency effectiveness, especially when linked to the strategic plans required by the U.S. Government Performance and Results Act. Since government is funded mostly on a program-by-program basis, cost-benefit analysis is frequently used to determine a program's viability. Cost-benefit analysis enumerates all costs and benefits of a specific project and evaluates them in dollar terms. Return on Investment analysis is a more sophisticated version of cost-benefit analysis and takes into account a program's costs and benefits and calculates the amount of return that the program produces. It also considers intangibles produced as a result of the program. The Balanced Scorecard method of measuring organizational effectiveness provides an alternative to more research-oriented approaches, which often include cumbersome models with multiple intervening variables split between a macro-and micro focus.
KW - FEDERAL government
KW - GOVERNMENT agencies
KW - COST effectiveness
KW - RATE of return
KW - STRATEGIC planning
KW - UNITED States
N1 - Accession Number: 13641469; Schay, Brigitte W. 1; Beach, Mary Ellen 2; Caldwell, Jacqueline A. 3; LaPolice, Christelle 3; Affiliations: 1: Director, Assessment Services Division, Personnel Resources & Development Center (PRDC), U.S. Office of Personnel Management (OPM).; 2: Chief, Workforce Planning and Information Management, Office of Human Resources, U.S. Nuclear Regulatory Commission (NRC); 3: Personnel Research Psychologist, Office of Personnel Management (OPM); Issue Info: Fall2002, Vol. 41 Issue 3, p355; Thesaurus Term: FEDERAL government; Thesaurus Term: GOVERNMENT agencies; Thesaurus Term: COST effectiveness; Thesaurus Term: RATE of return; Thesaurus Term: STRATEGIC planning; Subject: UNITED States; NAICS/Industry Codes: 921190 Other General Government Support; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; NAICS/Industry Codes: 911910 Other federal government public administration; NAICS/Industry Codes: 912910 Other provincial and territorial public administration; Number of Pages: 14p; Document Type: Article
L3 - 10.1002/hrm.10046
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Chaychian, Mahnaz
AU - Jones, Cynthia
AU - Poster, Dianne
AU - Silverman, Joseph
AU - Neta, Pedatsur
AU - Huie, Robert
AU - Al-Sheikhly, Mohamad
T1 - Radiolytic dechlorination of polychlorinated biphenyls in transformer oil and in marine sediment
JO - Radiation Physics & Chemistry
JF - Radiation Physics & Chemistry
Y1 - 2002/11//
VL - 65
IS - 4/5
M3 - Article
SP - 473
SN - 0969806X
AB - Radiolytic dechlorination of polychlorinated biphenyls (PCBs) in transformer oil and in marine sediments has been studied. At low PCB concentrations, complete degradation of the PCBs in transformer oil was achieved without degradation of the oil. Addition of an organic base, triethylamine, enhances the radiolytic dechlorination yield. The mechanism of dechlorination has been shown to involve electron transfer to PCBs from various aromatic radical anions formed in the irradiated oil. At high PCB concentrations, large amounts of triethylamine were necessary to achieve complete radiolytic dechlorination. Preliminary results on PCB-contaminated marine sediments demonstrate that addition of 2-propanol to the sediment/water slurry increases the effectiveness of the electron beam treatment. [Copyright &y& Elsevier]
AB - Copyright of Radiation Physics & Chemistry is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - POLYCHLORINATED biphenyls
KW - IONIZING radiation
KW - ELECTRON beams
KW - Electron beam
KW - Gamma radiation
KW - Ionizing radiation
KW - Polychlorinated biphenyls
KW - Sediment
KW - Transformer oil
N1 - Accession Number: 7916563; Chaychian, Mahnaz 1 Jones, Cynthia 2 Poster, Dianne 3 Silverman, Joseph 1 Neta, Pedatsur 3 Huie, Robert 3 Al-Sheikhly, Mohamad 1; Email Address: mohamad@eng.umd.edu; Affiliation: 1: Department of Materials and Nuclear Engineering, University of Maryland, College Park, MD 20742-2115, USA 2: US Nuclear Regulatory Commission, Washington, DC 20555, USA 3: Chemical Science and Technology Laboratory, National Institute of Standard and Technology, Gaithersburg, MD 20899, USA; Source Info: Nov2002, Vol. 65 Issue 4/5, p473; Subject Term: POLYCHLORINATED biphenyls; Subject Term: IONIZING radiation; Subject Term: ELECTRON beams; Author-Supplied Keyword: Electron beam; Author-Supplied Keyword: Gamma radiation; Author-Supplied Keyword: Ionizing radiation; Author-Supplied Keyword: Polychlorinated biphenyls; Author-Supplied Keyword: Sediment; Author-Supplied Keyword: Transformer oil; Number of Pages: 6p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Sun, Xiaodong
AU - Smith, Todd R.
AU - Kim, Seungjin
AU - Ishii, Mamoru
AU - Uhle, Jennifer
T1 - Interfacial area of bubbly flow in a relatively large diameter pipe
JO - Experimental Thermal & Fluid Science
JF - Experimental Thermal & Fluid Science
Y1 - 2002/12//
VL - 27
IS - 1
M3 - Article
SP - 97
SN - 08941777
AB - This paper presents the local measurement results of interfacial parameters in a vertical air–water upward two-phase bubbly flow. The measured parameters are local time-averaged void fraction, interfacial area concentration, bubble Sauter mean diameter, and interfacial velocity. The measurements are performed in a 101.6-mm inner diameter pipe by four-sensor conductivity probes. These data are further used to evaluate the one-dimensional, steady state, one-group interfacial area transport equation (IATE), which can serve as one of the constitutive relations for the two-fluid model. The agreement between the predictions from the transport equation and the experimental measurements is reasonably good. The resulting deviation is carefully examined. As a conclusion, the two-group IATE is recommended for general gas–liquid two-phase flow in various flow regimes. [Copyright &y& Elsevier]
AB - Copyright of Experimental Thermal & Fluid Science is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - PIPE
KW - TWO-phase flow
KW - Bubbly flow
KW - Four-sensor conductivity probe
KW - Interfacial area
KW - Large diameter pipe
KW - Void fraction
N1 - Accession Number: 7920549; Sun, Xiaodong 1; Email Address: xsun@ecn.purdue.edu Smith, Todd R. 1 Kim, Seungjin 1 Ishii, Mamoru 1 Uhle, Jennifer 2; Affiliation: 1: Thermal-hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, West Lafayette, IN 47906, USA 2: US Nuclear Regulatory Commission, Washington DC 20555, USA; Source Info: Dec2002, Vol. 27 Issue 1, p97; Subject Term: PIPE; Subject Term: TWO-phase flow; Author-Supplied Keyword: Bubbly flow; Author-Supplied Keyword: Four-sensor conductivity probe; Author-Supplied Keyword: Interfacial area; Author-Supplied Keyword: Large diameter pipe; Author-Supplied Keyword: Void fraction; NAICS/Industry Codes: 326122 Plastics Pipe and Pipe Fitting Manufacturing; NAICS/Industry Codes: 331210 Iron and Steel Pipe and Tube Manufacturing from Purchased Steel; Number of Pages: 13p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Frye Jr., Roland M.
T1 - THE NUCLEAR REGULATORY COMMISSION IS NOT REQUIRED BY STATUTE TO RELEASE TERRORISM-RELATED PORTIONS OF ENVIRONMENTAL IMPACT STATEMENTS.
JO - Administrative Law Review
JF - Administrative Law Review
Y1 - 2003///Summer2003
VL - 55
IS - 3
M3 - Article
SP - 643
EP - 678
SN - 00018368
AB - Examines the public's right to know about the dangers associated with a terrorist attack on U.S. non-military nuclear facilities. Federal government's duty to protect the public's health, safety and security by ensuring that information useful to terrorists does not enter the public domain; Conflict between the duty of the U.S. Nuclear Regulatory Commission under the National Environmental Policy Act (NEPA) and its duty under the Atomic Energy Act (AEA).
KW - GOVERNMENT information
KW - TERRORISM
KW - NATIONAL security
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 11075937; Frye Jr., Roland M. 1; Affiliations: 1: United States Nuclear Regulatory Commission; Issue Info: Summer2003, Vol. 55 Issue 3, p643; Subject Term: GOVERNMENT information; Subject Term: TERRORISM; Subject Term: NATIONAL security; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 928110 National Security; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 36p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dehmel, Jean-Claude
AU - Schneider, Stewart
T1 - Technical Considerations for Using in situ Gamma Spectroscopy in Conducting Final Status Surveys.
JO - Health Physics
JF - Health Physics
Y1 - 2003/06/04/2003 Supplement 3
VL - 84
M3 - Article
SP - S136
EP - S140
SN - 00179078
AB - Facilities undergoing decommissioning are required to conduct radiological surveys to initially characterize contaminants, guide remediation activities, and demonstrate that cleanup criteria have been met, based on screening or site-specific derived concentration guideline levels. This paper presents a number of technical considerations, not all inclusive, associated with the use of in situ gamma spectroscopy that should be addressed when such a method is proposed for conducting final status surveys. The technical issues identified here do not yet reflect the policy of the NRC on this subject. [ABSTRACT FROM AUTHOR]
AB - Copyright of Health Physics is the property of Lippincott Williams & Wilkins and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - operational topic
KW - radiation, gamma
KW - radioactivity, removal of
KW - spectroscopy, gamma
N1 - Accession Number: 102393186; Dehmel, Jean-Claude; Email Address: jxd3@nrc.gov.; Schneider, Stewart 1; Affiliations: 1: U.S. Nuclear Regulatory Commission, Washington, DC 20555; Issue Info: 2003 Supplement 3, Vol. 84, pS136; Author-Supplied Keyword: operational topic; Author-Supplied Keyword: radiation, gamma; Author-Supplied Keyword: radioactivity, removal of; Author-Supplied Keyword: spectroscopy, gamma; Number of Pages: 5p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Sun, Xiaodong
AU - Ishii, Mamoru
AU - Kelly, Joseph M.
T1 - Modified two-fluid model for the two-group interfacial area transport equation
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
Y1 - 2003/11//
VL - 30
IS - 16
M3 - Article
SP - 1601
SN - 03064549
AB - This paper presents a modified two-fluid model that is ready to be applied in the approach of the two-group interfacial area transport equation. The two-group interfacial area transport equation was developed to provide a mechanistic constitutive relation for the interfacial area concentration in the two-fluid model. In the two-group transport equation, bubbles are categorized into two groups: spherical/distorted bubbles as Group 1 while cap/slug/churn-turbulent bubbles as Group 2. Therefore, this transport equation can be employed in the flow regimes spanning from bubbly, cap bubbly, slug to churn-turbulent flows. However, the introduction of the two groups of bubbles requires two gas velocity fields. Yet it is not practical to solve two momentum equations for the gas phase alone. In the current modified two-fluid model, a simplified approach is proposed. The momentum equation for the averaged velocity of both Group-1 and Group-2 bubbles is retained. By doing so, the velocity difference between Group-1 and Group-2 bubbles needs to be determined. This may be made either based on simplified momentum equations for both Group-1 and Group-2 bubbles or by a modified drift-flux model. [Copyright &y& Elsevier]
AB - Copyright of Annals of Nuclear Energy is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Surface chemistry
KW - Fluids
N1 - Accession Number: 10117509; Sun, Xiaodong 1; Email Address: xsun@ecn.purdue.edu; Ishii, Mamoru 1; Email Address: ishii@ecn.purdue.edu; Kelly, Joseph M. 2; Affiliations: 1: Thermal-hydraulics and Reactor Safety Laboratory, Purdue University, School of Nuclear Engineering, 400 Central Drive, West Lafayette, IN 47907-2017, USA; 2: T10K8, US Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Issue Info: Nov2003, Vol. 30 Issue 16, p1601; Thesaurus Term: Surface chemistry; Subject Term: Fluids; Number of Pages: 22p; Document Type: Article
L3 - 10.1016/S0306-4549(03)00150-6
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Goda, Hiroshi
AU - Hibiki, Takashi
AU - Kim, Seungjin
AU - Ishii, Mamoru
AU - Uhle, Jennifer
T1 - Drift-flux model for downward two-phase flow
JO - International Journal of Heat & Mass Transfer
JF - International Journal of Heat & Mass Transfer
Y1 - 2003/12//
VL - 46
IS - 25
M3 - Article
SP - 4835
SN - 00179310
AB - In view of the practical importance of the drift-flux model for two-phase flow analysis in general and in the analysis of nuclear-reactor transients and accidents in particular, the distribution parameter and the drift velocity have been studied for downward two-phase flows. The constitutive equation that specifies the distribution parameter in the downward flow has been derived by taking into account the effect of the downward mixture volumetric flux on the phase distribution. It was assumed that the constitutive equation for the drift velocity developed by Ishii for a vertical upward churn-turbulent flow determined the drift velocity for the downward flow over all of flow regimes. To evaluate the drift-flux model with newly developed constitutive equations, area-averaged void fraction measurement has been extensively performed by employing an impedance void meter for an adiabatic vertical co-current downward air–water two-phase flow in 25.4-mm and 50.8-mm inner diameter round tubes. The newly developed drift-flux model has been validated by 462 data sets obtained in the present study and literatures under various experimental conditions. These data sets cover extensive experimental conditions such as flow system (air–water and steam–water), channel diameter (16–102.3 mm), pressure (0.1–1.5 MPa), and mixture volumetric flux (−0.45 to −24.6 m/s). An excellent agreement has been obtained between the newly developed drift-flux model and the data within an average relative deviation of ±15.4%. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Heat & Mass Transfer is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - TWO-phase flow
KW - NUCLEAR reactors
KW - TURBULENCE
KW - TRANSIENTS (Dynamics)
KW - Distribution parameter
KW - Downward flow
KW - Drift velocity
KW - Drift-flux model
KW - Gas–liquid flow
KW - Impedance void meter
KW - Multiphase flow
KW - Void fraction
N1 - Accession Number: 10693777; Goda, Hiroshi 1 Hibiki, Takashi 1,2 Kim, Seungjin 1 Ishii, Mamoru 1; Email Address: ishii@ecn.purdue.edu Uhle, Jennifer 3; Affiliation: 1: School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA 2: Research Reactor Institute, Kyoto University, Kumatori, Sennan, Osaka 590-0494, Japan 3: Division of System Analysis and Regulatory Effectiveness Office of Research, US Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Dec2003, Vol. 46 Issue 25, p4835; Subject Term: TWO-phase flow; Subject Term: NUCLEAR reactors; Subject Term: TURBULENCE; Subject Term: TRANSIENTS (Dynamics); Author-Supplied Keyword: Distribution parameter; Author-Supplied Keyword: Downward flow; Author-Supplied Keyword: Drift velocity; Author-Supplied Keyword: Drift-flux model; Author-Supplied Keyword: Gas–liquid flow; Author-Supplied Keyword: Impedance void meter; Author-Supplied Keyword: Multiphase flow; Author-Supplied Keyword: Void fraction; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 10p; Document Type: Article
L3 - 10.1016/S0017-9310(03)00309-0
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Diaz, Nls
T1 - The Decision to Go Forward.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2004/01//Jan/Feb2004
VL - 22
IS - 1
M3 - Article
SP - 31
EP - 35
PB - Presidents & Prime Ministers
SN - 08922055
AB - Discusses highlights of a speech given by U.S. President Dwight Eisenhower on December 8, 1953 regarding atomic energy. Use of the catch phrase 'Atoms for peace' throughout the speech; Description of the capacity of the U.S. and the Soviet Union to devastate each other's countries using atomic weapons; Vision of an international atomic energy agency.
KW - Nuclear energy
KW - Nuclear weapons
KW - American speeches, addresses, etc.
KW - Cold War, 1945-1989
KW - United States
KW - Eisenhower, Dwight D. (Dwight David), 1890-1969
N1 - Accession Number: 12462751; Diaz, Nls 1; Affiliations: 1: Chairman, U.S. Nuclear Regulatory Commission.; Issue Info: Jan/Feb2004, Vol. 22 Issue 1, p31; Thesaurus Term: Nuclear energy; Thesaurus Term: Nuclear weapons; Subject Term: American speeches, addresses, etc.; Subject Term: Cold War, 1945-1989; Subject: United States; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; People: Eisenhower, Dwight D. (Dwight David), 1890-1969; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Hallbert, Bruce
AU - Gertman, David
AU - Lois, Erasmia
AU - Marble, Julie
AU - Blackman, Harold
AU - Byers, James
T1 - The use of empirical data sources in HRA
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2004/02//
VL - 83
IS - 2
M3 - Article
SP - 139
EP - 143
SN - 09518320
AB - This paper presents a review of available information related to human performance to support Human Reliability Analysis (HRA) performed for nuclear power plants (NPPs). A number of data sources are identified as potentially useful. These include NPP licensee event reports, augmented inspection team reports, operator requalification data, results from the literature in experimental psychology, and the Aviation Safety Reporting System. The paper discusses how utilizing such information improves our capability to model and quantify human performance. In particular, the paper discusses how information related to performance shaping factors can be extracted from empirical data to determine their size effect, their relative effects, as well as their interactions. The paper concludes that appropriate use of existing sources can help addressing some of the important issues we are currently facing in HRA. [Copyright &y& Elsevier]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RELIABILITY (Personality trait)
KW - NUCLEAR power plants
KW - HUMAN error
KW - EXPERIMENTAL psychology
KW - PSYCHOLOGY -- Research
KW - Human Reliability Assessment
KW - Performance-shaping factors
KW - Probabilistic risk assessment
N1 - Accession Number: 22237985; Hallbert, Bruce 1; Email Address: hallbp@inel.gov Gertman, David 1 Lois, Erasmia 2 Marble, Julie 1 Blackman, Harold 1 Byers, James 1; Affiliation: 1: Idaho National Engineering and Environmental Laboratory (INEEL), Idaho Falls, ID, USA 2: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, D.C. 20555, USA; Source Info: Feb2004, Vol. 83 Issue 2, p139; Subject Term: RELIABILITY (Personality trait); Subject Term: NUCLEAR power plants; Subject Term: HUMAN error; Subject Term: EXPERIMENTAL psychology; Subject Term: PSYCHOLOGY -- Research; Author-Supplied Keyword: Human Reliability Assessment; Author-Supplied Keyword: Performance-shaping factors; Author-Supplied Keyword: Probabilistic risk assessment; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 541720 Research and Development in the Social Sciences and Humanities; Number of Pages: 5p; Document Type: Article
L3 - 10.1016/j.ress.2003.09.005
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Forester, John
AU - Bley, Dennis
AU - Cooper, Susan
AU - Lois, Erasmia
AU - Siu, Nathan
AU - Kolaczkowski, Alan
AU - Wreathall, John
T1 - Expert elicitation approach for performing ATHEANA quantification
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2004/02//
VL - 83
IS - 2
M3 - Article
SP - 207
EP - 220
SN - 09518320
AB - An expert elicitation approach has been developed to estimate probabilities for unsafe human actions (UAs) based on error-forcing contexts (EFCs) identified through the ATHEANA (A Technique for Human Event Analysis) search process. The expert elicitation approach integrates the knowledge of informed analysts to quantify UAs and treat uncertainty (‘quantification-including-uncertainty’). The analysis focuses on (a) the probabilistic risk assessment (PRA) sequence EFCs for which the UAs are being assessed, (b) the knowledge and experience of analysts (who should include trainers, operations staff, and PRA/human reliability analysis experts), and (c) facilitated translation of information into probabilities useful for PRA purposes. Rather than simply asking the analysts their opinion about failure probabilities, the approach emphasizes asking the analysts what experience and information they have that is relevant to the probability of failure. The facilitator then leads the group in combining the different kinds of information into a consensus probability distribution. This paper describes the expert elicitation process, presents its technical basis, and discusses the controls that are exercised to use it appropriately. The paper also points out the strengths and weaknesses of the approach and how it can be improved. Specifically, it describes how generalized contextually anchored probabilities (GCAPs) can be developed to serve as reference points for estimates of the likelihood of UAs and their distributions. [Copyright &y& Elsevier]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - PROBABILITY theory
KW - HUMAN error
KW - HUMAN behavior
KW - RISK assessment
KW - ERRORS
KW - ATHEANA
KW - Expert elicitation
KW - HRA
KW - Human performance
KW - Human reliability analysis
KW - PRA
KW - Probabilistic risk assessment
KW - Uncertainty
N1 - Accession Number: 22237991; Forester, John 1; Email Address: jafores@sandia.gov Bley, Dennis 2 Cooper, Susan 3 Lois, Erasmia 3 Siu, Nathan 3 Kolaczkowski, Alan 4 Wreathall, John 5; Affiliation: 1: Sandia National Laboratories, P.O. Box 5800, MS0748, Albuquerque, NM 87185-0748, USA 2: Buttonwood Consulting, Inc., Oakton, VA, USA 3: US Nuclear Regulatory Commission, Washington, DC, USA 4: Science Applications International Corporation, San Diego, CA, USA 5: John Wreathall and Co., Dublin, OH, USA; Source Info: Feb2004, Vol. 83 Issue 2, p207; Subject Term: PROBABILITY theory; Subject Term: HUMAN error; Subject Term: HUMAN behavior; Subject Term: RISK assessment; Subject Term: ERRORS; Author-Supplied Keyword: ATHEANA; Author-Supplied Keyword: Expert elicitation; Author-Supplied Keyword: HRA; Author-Supplied Keyword: Human performance; Author-Supplied Keyword: Human reliability analysis; Author-Supplied Keyword: PRA; Author-Supplied Keyword: Probabilistic risk assessment; Author-Supplied Keyword: Uncertainty; Number of Pages: 14p; Document Type: Article
L3 - 10.1016/j.ress.2003.09.011
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Sun, Xiaodong
AU - Paranjape, Sidharth
AU - Ishii, Mamoru
AU - Uhle, Jennifer
T1 - LDA measurement in air–water downward flow
JO - Experimental Thermal & Fluid Science
JF - Experimental Thermal & Fluid Science
Y1 - 2004/03//
VL - 28
IS - 4
M3 - Article
SP - 317
SN - 08941777
AB - Local characteristics of the liquid phase in air–water downward flow were investigated in a 50.8 mm inner-diameter round pipe. A laser Doppler anemometry (LDA) system was used to measure axial liquid velocity and its fluctuations. To reduce the measurement uncertainty, the experiments were performed in flow conditions with low void fraction. Titanium dioxide particles with a mean diameter of 2 μm were used as seeding particles to enhance the data rate. Benchmark experiment in the single-phase liquid flow was first carried out to ensure good performance of the LDA system in the current setup. A total of 13 flow conditions were examined in air–water two-phase experiment. By applying a special setup of the LDA system, it was found that no further signal discrimination process was required to obtain the liquid velocity in the present low void fraction conditions. The comparisons between the liquid flow rates measured by the magnetic flow meter and those obtained from the local measurements showed good agreements, with differences less than 6.0%. The measurement results demonstrated that the presence of the bubbles tended to flatten the liquid velocity radial profile, and the maximum liquid velocity might occur off the pipe centerline, in particular at relatively low flow rates. Furthermore, the axial liquid velocity fluctuations were quite uniform in the radial direction. No significant turbulent reduction in the two-phase downward flow was observed in the current experimental flow conditions. [Copyright &y& Elsevier]
AB - Copyright of Experimental Thermal & Fluid Science is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - ANEMOMETER
KW - FLUID dynamics
KW - SPEED
KW - WATER
KW - Bubbly flow
KW - Downward flow
KW - Laser Doppler anemometry
KW - Liquid velocity
N1 - Accession Number: 12236954; Sun, Xiaodong 1; Email Address: xsun@ecn.purdue.edu Paranjape, Sidharth 1 Ishii, Mamoru 1 Uhle, Jennifer 2; Affiliation: 1: Thermal-hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA 2: US Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Mar2004, Vol. 28 Issue 4, p317; Subject Term: ANEMOMETER; Subject Term: FLUID dynamics; Subject Term: SPEED; Subject Term: WATER; Author-Supplied Keyword: Bubbly flow; Author-Supplied Keyword: Downward flow; Author-Supplied Keyword: Laser Doppler anemometry; Author-Supplied Keyword: Liquid velocity; Number of Pages: 12p; Document Type: Article
L3 - 10.1016/S0894-1777(03)00105-5
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Walker, J. Samuel
T1 - Hanford Site Historic District: History of the Plutonium Production Facilities, 1943-1990 (Book).
JO - Journal of Environmental Quality
JF - Journal of Environmental Quality
Y1 - 2004/03//Mar/Apr2004
VL - 33
IS - 2
M3 - Book Review
SP - 796
EP - 797
SN - 00472425
AB - Reviews the book "Hanford Site Historic District: History of the Plutonium Production Facilities, 1943-1990," by Thomas E. Marceau.
KW - Plutonium
KW - Nonfiction
KW - Marceau, Thomas E.
KW - Hanford Site Historic District: History of the Plutonium Production Facilities, 1943-1990 (Book)
N1 - Accession Number: 12800011; Walker, J. Samuel 1; Email Address: Jsw@nrc.gov; Affiliations: 1: U.S. Nuclear Regulatory Commission Washington, DC; Issue Info: Mar/Apr2004, Vol. 33 Issue 2, p796; Thesaurus Term: Plutonium; Subject Term: Nonfiction; Reviews & Products: Hanford Site Historic District: History of the Plutonium Production Facilities, 1943-1990 (Book); People: Marceau, Thomas E.; Number of Pages: 2p; Document Type: Book Review
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Naus, D.J.
AU - Ellingwood, B.R.
AU - Graves III, H.L.
T1 - Methods for assessing NPP containment pressure boundary integrity
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2004/03//
VL - 228
IS - 1-3
M3 - Article
SP - 55
SN - 00295493
AB - Research is being conducted to address aging of the containment pressure boundary in light-water reactor plants. Objectives of this research are to (1) understand the significant factors relating to corrosion occurrence, efficacy of inspection, and structural capacity reduction of steel containments and of liners of concrete containments; (2) provide the U.S. Nuclear Regulatory Commission (USNRC) reviewers a means of establishing current structural capacity margins or estimating future residual structural capacity margins for steel containments and concrete containments as limited by liner integrity; and (3) provide recommendations, as appropriate, on information to be requested of licensees for guidance that could be utilized by USNRC reviewers in assessing the seriousness of reported incidences of containment degradation. Activities include development of a degradation assessment methodology; reviews of techniques and methods for inspection and repair of containment metallic pressure boundaries; evaluation of candidate techniques for inspection of inaccessible regions of containment metallic pressure boundaries; establishment of a methodology for reliability-based condition assessments of steel containments and liners; and fragility assessments of steel containments with localized corrosion. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - CORROSION & anti-corrosives
KW - LIGHT water reactors
KW - NUCLEAR reactors
KW - NUCLEAR fuels
N1 - Accession Number: 12170396; Naus, D.J. 1; Email Address: nausdj@ornl.gov Ellingwood, B.R. 2 Graves III, H.L. 3; Affiliation: 1: Oak Ridge National Laboratory, Containment and Concrete Technology, P.O. Box 2009, Bldg. 9204-1, Oak Ridge, TN 37831-8056, USA 2: Georgia Institute of Technology, Atlanta, GA 30332-0355, USA 3: U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Source Info: Mar2004, Vol. 228 Issue 1-3, p55; Subject Term: CORROSION & anti-corrosives; Subject Term: LIGHT water reactors; Subject Term: NUCLEAR reactors; Subject Term: NUCLEAR fuels; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 18p; Document Type: Article
L3 - 10.1016/j.nucengdes.2003.06.024
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Braverman, J.I.
AU - Miller, C.A.
AU - Hofmayer, C.H.
AU - Ellingwood, B.R.
AU - Naus, D.J.
AU - Chang, T.Y.
T1 - Degradation assessment of structures and passive components at nuclear power plants
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2004/03//
VL - 228
IS - 1-3
M3 - Article
SP - 283
SN - 00295493
AB - This paper describes a multi-year research program to assess age-related degradation of structures and passive components important to the safe operation of nuclear power plants (NPPs). The purpose of the research effort is to develop the technical basis for the validation and improvement of analytical methods and acceptance criteria which can be used to make risk-informed decisions and to address technical issues related to degradation of structures and passive components. The approach adopted for this research program consists of two phases. In Phase I, specific degradation occurrences at plants were collected and evaluated, existing technical information on aging was reviewed, and a scoping study was performed to identify which structures and components should be studied in the subsequent phases of the research program. Based on the results of the Phase I effort, selected structures and passive components are evaluated in Phase II to assess the effects of age-related degradation using existing and enhanced analytical methods. Fragility analyses are performed for undegraded and degraded structures and passive components. These results can then be used to assess the potential impact of degradation on overall plant risk. The Phase II effort also utilizes the results of the analyses to develop probabilistic degradation acceptance criteria for the structures and passive components studied. These research activities provide useful tools to support the current goals of developing risk-informed and performance-based regulation in the nuclear industry. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NUCLEAR power plants
KW - NUCLEAR industry
KW - THERMAL diffusivity
KW - NUCLEAR reactors
N1 - Accession Number: 12170414; Braverman, J.I. 1; Email Address: braverman@bnl.gov Miller, C.A. 1 Hofmayer, C.H. 1 Ellingwood, B.R. 2 Naus, D.J. 3 Chang, T.Y. 4; Affiliation: 1: Brookhaven National Laboratory, Building 130, P.O. Box 5000, Upton, NY, USA 2: Georgia Institute of Technology, Atlanta, GA, USA 3: Oak Ridge National Laboratory, Oak Ridge, TN, USA 4: United States Nuclear Regulatory Commission, USA; Source Info: Mar2004, Vol. 228 Issue 1-3, p283; Subject Term: NUCLEAR power plants; Subject Term: NUCLEAR industry; Subject Term: THERMAL diffusivity; Subject Term: NUCLEAR reactors; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 22p; Document Type: Article
L3 - 10.1016/j.nucengdes.2003.06.012
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Xu, J.
AU - DeGrassi, G.
AU - Chokshi, N.
T1 - A NRC-BNL benchmark evaluation of seismic analysis methods for non-classically damped coupled systems
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2004/03//
VL - 228
IS - 1-3
M3 - Article
SP - 345
SN - 00295493
AB - Under the auspices of the U.S. Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a comprehensive program to evaluate state-of-the-art methods and computer programs for seismic analysis of typical coupled nuclear power plant (NPP) systems with non-classical damping. In this program, four benchmark models of coupled building-piping/equipment systems with different damping characteristics were developed and analyzed by BNL for a suite of earthquakes. The BNL analysis was carried out by the Wilson-θ time domain integration method with the system-damping matrix computed using a synthesis formulation as presented in a companion paper [Nucl. Eng. Des. (2002)]. These benchmark problems were subsequently distributed to and analyzed by program participants applying their uniquely developed methods and computer programs. This paper is intended to offer a glimpse at the program, and provide a summary of major findings and principle conclusions with some representative results.The participant’s analysis results established using complex modal time history methods showed good comparison with the BNL solutions, while the analyses produced with either complex-mode response spectrum methods or classical normal-mode response spectrum method, in general, produced more conservative results, when averaged over a suite of earthquakes. However, when coupling due to damping is significant, complex-mode response spectrum methods performed better than the classical normal-mode response spectrum method. Furthermore, as part of the program objectives, a parametric assessment is also presented in this paper, aimed at evaluation of the applicability of various analysis methods to problems with different dynamic characteristics unique to coupled NPP systems. It is believed that the findings and insights learned from this program will be useful in developing new acceptance criteria and providing guidance for future regulatory activities involving license applications of these alternate methods to coupled systems. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - LABORATORIES
KW - NUCLEAR power plants
KW - SPECTRUM analysis
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 12170417; Xu, J. 1; Email Address: xu@bnl.gov DeGrassi, G. 1 Chokshi, N. 2; Affiliation: 1: Brookhaven National Laboratory, Upton, NY 11973-5000, USA 2: The United States Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Source Info: Mar2004, Vol. 228 Issue 1-3, p345; Subject Term: LABORATORIES; Subject Term: NUCLEAR power plants; Subject Term: SPECTRUM analysis; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 621511 Medical Laboratories; NAICS/Industry Codes: 541380 Testing Laboratories; NAICS/Industry Codes: 541940 Veterinary Services; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 22p; Document Type: Article
L3 - 10.1016/j.nucengdes.2003.06.019
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Hibiki, Takashi
AU - Goda, Hiroshi
AU - Kim, Seungjin
AU - Ishii, Mamoru
AU - Uhle, Jennifer
T1 - Structure of vertical downward bubbly flow
JO - International Journal of Heat & Mass Transfer
JF - International Journal of Heat & Mass Transfer
Y1 - 2004/04//
VL - 47
IS - 8/9
M3 - Article
SP - 1847
SN - 00179310
AB - In view of the great importance to two-fluid model, structure of downward bubbly flows in vertical pipes has been discussed intensively based on available data sets of local flow parameters including extensive air–water data sets recently measured by the authors. In this study, an approximate radial phase distribution pattern map has been proposed based on available data sets, and radial profiles of local flow parameters such as void fraction, interfacial area concentration, interfacial velocity, and bubble Sauter mean diameter have been discussed in detail. The one-dimensional drift-flux model for a downward two-phase flow and the correlation of the interfacial area concentration have been compared with the downward flow data. The correlations applicable to the predictions of one-dimensional void fraction and interfacial area concentration for a downward bubbly flow have been recommended by the comparison. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Heat & Mass Transfer is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - FLUID mechanics
KW - TURBULENCE
KW - Bubble size
KW - Downward flow
KW - Drift-flux model
KW - Gas–liquid bubbly flow
KW - Interfacial area concentration
KW - Multiphase flow
KW - Void fraction
N1 - Accession Number: 11881615; Hibiki, Takashi 1; Email Address: hibiki@rri.kyoto-u.ac.jp Goda, Hiroshi 2 Kim, Seungjin 2 Ishii, Mamoru 2; Email Address: ishii@ecn.purdue.edu Uhle, Jennifer 3; Affiliation: 1: Research Reactor Institute, Kyoto University, Kumatori, Sennan, Osaka 590-0494, Japan 2: School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA 3: Division of System Analysis and Regulatory Effectiveness Office of Research, US Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Apr2004, Vol. 47 Issue 8/9, p1847; Subject Term: FLUID mechanics; Subject Term: TURBULENCE; Author-Supplied Keyword: Bubble size; Author-Supplied Keyword: Downward flow; Author-Supplied Keyword: Drift-flux model; Author-Supplied Keyword: Gas–liquid bubbly flow; Author-Supplied Keyword: Interfacial area concentration; Author-Supplied Keyword: Multiphase flow; Author-Supplied Keyword: Void fraction; Number of Pages: 16p; Document Type: Article
L3 - 10.1016/j.ijheatmasstransfer.2003.10.027
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Mohanty, Sitakanta
AU - Codell, Richard B.
T1 - Ramifications of Risk Measures in Implementing Quantitative Performance Assessment for the Proposed Radioactive Waste Repository at Yucca Mountain, Nevada, USA.
JO - Risk Analysis: An International Journal
JF - Risk Analysis: An International Journal
Y1 - 2004/06//
VL - 24
IS - 3
M3 - Article
SP - 537
EP - 546
PB - Wiley-Blackwell
SN - 02724332
AB - As part of its preparation to review a potential license application from the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission (NRC) is examining the performance of the proposed Yucca Mountain nuclear waste repository. In this regard, we evaluated postclosure repository performance using Monte Carlo analyses with an NRC-developed system model that has 950 input parameters, of which 330 are sampled to represent system uncertainties. The quantitative compliance criterion for dose was established by NRC to protect inhabitants who might be exposed to any releases from the repository. The NRC criterion limits the peak-of-the-mean dose, which in our analysis is estimated by averaging the potential exposure at any instant in time for all Monte Carlo realizations, and then determining the maximum value of the mean curve within 10,000 years, the compliance period. This procedure contrasts in important ways with a more common measure of risk based on the mean of the ensemble of peaks from each Monte Carlo realization. The NRC chose the former ( peak-of-the-mean) because it more correctly represents the risk to an exposed individual. Procedures for calculating risk in the expected case of slow repository degradation differ from those for low-probability cases of disruption by external forces such as volcanism. We also explored the possibility of risk dilution (i.e., lower calculated risk) that could result from arbitrarily defining wide probability distributions for certain parameters. Finally, our sensitivity analyses to identify influential parameters used two approaches: (1) the ensemble of doses from each Monte Carlo realization at the time of the peak risk (i.e., peak-of-the-mean) and (2) the ensemble of peak doses calculated from each realization within 10,000 years. The latter measure appears to have more discriminatory power than the former for many parameters (based on the greater magnitude of the sensitivity coefficient), but can yield different rankings, especially for parameters that influence the timing of releases. [ABSTRACT FROM AUTHOR]
AB - Copyright of Risk Analysis: An International Journal is the property of Wiley-Blackwell and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radioactive waste sites
KW - Radioactive wastes
KW - Radioactive waste disposal
KW - Yucca Mountain (Nev.)
KW - Nevada
KW - United States
KW - disruptive event
KW - high level waste
KW - Performance assessment
KW - risk analysis
KW - risk dilution
KW - sensitivity analysis
KW - Yucca Mountain
N1 - Accession Number: 13515113; Mohanty, Sitakanta 1; Email Address: smohanty@swri.org; Codell, Richard B. 2; Affiliations: 1: Center for Nuclear Waste Regulatory Analyses, Southwest Re-search Institute®, 6220 Culebra Road, San Antonio, TX 78228, USA; 2: U.S. Nuclear Regulatory Commission, 11544 Rockville Pike, Rockville, MD 20852, USA; Issue Info: Jun2004, Vol. 24 Issue 3, p537; Thesaurus Term: Radioactive waste sites; Thesaurus Term: Radioactive wastes; Thesaurus Term: Radioactive waste disposal; Subject: Yucca Mountain (Nev.); Subject: Nevada; Subject: United States; Author-Supplied Keyword: disruptive event; Author-Supplied Keyword: high level waste; Author-Supplied Keyword: Performance assessment; Author-Supplied Keyword: risk analysis; Author-Supplied Keyword: risk dilution; Author-Supplied Keyword: sensitivity analysis; Author-Supplied Keyword: Yucca Mountain; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 237990 Other Heavy and Civil Engineering Construction; Number of Pages: 10p; Illustrations: 1 Chart, 6 Graphs; Document Type: Article
L3 - 10.1111/j.0272-4332.2004.00457.x
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Dey, M.K.
T1 - An evaluation of risk methods for prioritizing fire protection features: a procedure for fire barrier penetration seals
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2004/08//
VL - 232
IS - 2
M3 - Article
SP - 165
EP - 171
SN - 00295493
AB - This paper generally evaluates risk methods available for prioritizing fire protection features. Risk methods involving both the use of qualitative insights, and quantitative results from a fire probabilistic risk analysis are reviewed. The applicability of these methods to develop a prioritized list of fire barrier penetration seals in a plant based on risk significance is presented as a procedure to illustrate the benefits of the methods. The paper concludes that current fire risk assessment methods can be confidently used to prioritize plant fire protection features, specifically fire barrier penetration seals. Simple prioritization schemes, using qualitative assessments and insights from fire PRA methodology may be implemented without the need for quantitative results. More elaborate prioritization schemes that allow further refinements to the categorization process may be implemented using the quantitative results of the screening processes in good fire PRAs. The use of the quantitative results from good fire PRAs provide several benefits for risk prioritization of fire protection features at plants, mainly from the plant systems analyses conducted for a fire PRA. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RISK assessment
KW - FIRE prevention
KW - RISK
KW - SAFETY
N1 - Accession Number: 14103375; Dey, M.K. 1; Email Address: MKD@nrc.gov; Affiliation: 1: US Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Aug2004, Vol. 232 Issue 2, p165; Subject Term: RISK assessment; Subject Term: FIRE prevention; Subject Term: RISK; Subject Term: SAFETY; Number of Pages: 7p; Document Type: Article
L3 - 10.1016/j.nucengdes.2003.11.035
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Baldwin, Thomas L.
AU - Lewis, Shani A.
T1 - Distribution Load Flow Methods for Shipboard Power Systems.
JO - IEEE Transactions on Industry Applications
JF - IEEE Transactions on Industry Applications
Y1 - 2004/09//Sep/Oct2004
VL - 40
IS - 5
M3 - Article
SP - 1183
EP - 1190
SN - 00939994
AB - With the recent initiatives to modernize large ship power systems, ship builders are integrating technologies with the aim of an all-electric energy system. New control strategies utilizing distribution automation and network reconfiguration provide greater flexibility, reliability, and quality of service. These automated controls require efficient and accurate load flow solutions. A critique of classical and distribution powersflow methods is conducted for shipboard distribution automation. Three classical radial-network power-flow methods are reviewed. A modification of the forward-backward sweep method is presented, which enhances the computation time and solution convergence. Comparative tests are conducted on a new benchmark test system of a ship's distribution network. The results demonstrate that the modified forward-backward sweep method succeeds in being the fastest method with good convergence on networks with low X/R ratios. [ABSTRACT FROM AUTHOR]
AB - Copyright of IEEE Transactions on Industry Applications is the property of IEEE and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - LOAD (Electric power)
KW - POWER resources
KW - QUALITY control
KW - CUSTOMER services
KW - AUTOMATION
KW - ELECTRICITY
KW - Distribution power flow
KW - radial load flow
KW - ship- board power system.
KW - ship- board power system. Distribution power flow
N1 - Accession Number: 14674338; Baldwin, Thomas L. 1; Email Address: tom.baldwin@ieee.org Lewis, Shani A. 2; Email Address: SLLl@nrc.gov; Affiliation: 1: Department of Electrical and Computer Engineering, FAMU-FSU College of Engineering, Tallahassee, FL 32310 USA 2: Region I Office, U.S. Nuclear Regulatory Commission, King of Prussia, PA 19406-1415 USA; Source Info: Sep/Oct2004, Vol. 40 Issue 5, p1183; Subject Term: LOAD (Electric power); Subject Term: POWER resources; Subject Term: QUALITY control; Subject Term: CUSTOMER services; Subject Term: AUTOMATION; Subject Term: ELECTRICITY; Author-Supplied Keyword: Distribution power flow; Author-Supplied Keyword: radial load flow; Author-Supplied Keyword: ship- board power system.; Author-Supplied Keyword: ship- board power system. Distribution power flow; Number of Pages: 8p; Document Type: Article
L3 - 10.1109/TIA.2004.834128
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Welter, K.B.
AU - Wu, Q.
AU - You, Y.
AU - Abel, K.
AU - McCreary, D.
AU - Bajorek, S.M.
AU - Reyes, J.N.
T1 - Experimental investigation and theoretical modeling of liquid entrainment in a horizontal tee with a vertical-up branch
JO - International Journal of Multiphase Flow
JF - International Journal of Multiphase Flow
Y1 - 2004/12//
VL - 30
IS - 12
M3 - Article
SP - 1451
EP - 1484
SN - 03019322
AB - Abstract: This article describes a comprehensive literature review of liquid entrainment in horizontal pipes with vertical-up branches. Deficiencies in the available data and correlations were identified. The Air–water Test Loop for Advanced Thermal–hydraulic Studies (ATLATS) was constructed and entrainment onset and steady-state data were collected for a wide range of flow conditions. Using new insights gained from experimental testing, the authors developed a model for predicting the onset of entrainment and steady-state entrainment rate. Previously published correlations, along with the new model, are compared against all available data. The new model shows very good agreement with the onset data, but is not very good at predicting branch quality at high liquid flow rates. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Multiphase Flow is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - PIPE
KW - STATISTICS
KW - LIQUIDS
KW - FLUIDS
KW - Advanced reactor
KW - Liquid entrainment
KW - LOCA
KW - Phase separation
KW - Tees
N1 - Accession Number: 15446843; Welter, K.B. 1; Email Address: kbw@nrc.gov Wu, Q. 2 You, Y. 2 Abel, K. 2 McCreary, D. 2 Bajorek, S.M. 1 Reyes, J.N. 2; Affiliation: 1: Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission, U.S.A 2: Department of Nuclear Engineering, Oregon State University, U.S.A; Source Info: Dec2004, Vol. 30 Issue 12, p1451; Subject Term: PIPE; Subject Term: STATISTICS; Subject Term: LIQUIDS; Subject Term: FLUIDS; Author-Supplied Keyword: Advanced reactor; Author-Supplied Keyword: Liquid entrainment; Author-Supplied Keyword: LOCA; Author-Supplied Keyword: Phase separation; Author-Supplied Keyword: Tees; NAICS/Industry Codes: 331210 Iron and Steel Pipe and Tube Manufacturing from Purchased Steel; NAICS/Industry Codes: 326122 Plastics Pipe and Pipe Fitting Manufacturing; Number of Pages: 34p; Document Type: Article
L3 - 10.1016/j.ijmultiphaseflow.2004.08.001
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Rudland, D.
AU - Wilkowski, G.
AU - Wang, Y.-Y.
AU - Norris, W.
T1 - Development of circumferential through-wall crack K-solutions for control rod drive mechanism nozzles
JO - International Journal of Pressure Vessels & Piping
JF - International Journal of Pressure Vessels & Piping
Y1 - 2004/12//
VL - 81
IS - 12
M3 - Article
SP - 961
EP - 971
SN - 03080161
AB - The US Nuclear Regulatory Commission (USNRC) has undertaken a program to assess the integrity of control rod drive mechanism nozzles in existing plants that are not immediately replacing their reactor pressure vessel heads. This paper summarizes some of the efforts undertaken on behalf of the USNRC for the development of circumferential crack-driving force solutions to be used in probabilistic determinations of the time from detectable leakage to failure. Detailed three-dimensional elastic–plastic finite element analyses of these nozzles were conducted to determine the effects of operating conditions, tube-to-head interference fit, tube yield strength, and nozzle-to-head angle on the crack-driving force. Three major observations to date are: [Copyright &y& Elsevier]
AB - Copyright of International Journal of Pressure Vessels & Piping is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NOZZLES
KW - PROBABILITY theory
KW - FINITE element method
KW - COMPRESSED air
KW - J-integral
KW - K-solution
KW - Circumferential through-wall cracks
KW - Control rod drive mechanisms
KW - Elastic–plastic fracture
KW - Pressurized water reactor
KW - Stress corrosion cracking
N1 - Accession Number: 14784734; Rudland, D. 1; Email Address: drudland@emc-sq.com Wilkowski, G. 1 Wang, Y.-Y. 1 Norris, W. 2; Affiliation: 1: Engineering Mechanics Corporation of Columbus, 3518 Riverside Dr. Suite 202, Columbus, OH 43026, USA 2: US Nuclear Regulatory Commission, Office of Nuclear Reactor Research, Washington, DC, USA; Source Info: Dec2004, Vol. 81 Issue 12, p961; Subject Term: NOZZLES; Subject Term: PROBABILITY theory; Subject Term: FINITE element method; Subject Term: COMPRESSED air; Author-Supplied Keyword: J-integral; Author-Supplied Keyword: K-solution; Author-Supplied Keyword: Circumferential through-wall cracks; Author-Supplied Keyword: Control rod drive mechanisms; Author-Supplied Keyword: Elastic–plastic fracture; Author-Supplied Keyword: Pressurized water reactor; Author-Supplied Keyword: Stress corrosion cracking; NAICS/Industry Codes: 326198 All other plastic product manufacturing; NAICS/Industry Codes: 326199 All Other Plastics Product Manufacturing; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.ijpvp.2004.04.003
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Bastian, R. K.
AU - Bachmaier, J. T.
AU - Schmidt, D. W.
AU - Salomon, S. N.
AU - Jones, A.
AU - Chiu, W. A.
AU - Setlow, L. W.
AU - Wolbarst, A. B.
AU - Yu, C.
AU - Goodman, J.
AU - Lenhart, T.
T1 - Radioactive Materials in Biosolids: National Survey, Dose Modeling, and Publicly Owned Treatment Works (POTW) Guidance.
JO - Journal of Environmental Quality
JF - Journal of Environmental Quality
Y1 - 2005/01//Jan/Feb2005
VL - 34
IS - 1
M3 - Article
SP - 64
EP - 74
SN - 00472425
AB - Discusses the radioactive materials in biosolids. Availability of three new documents concerning radio active materials in sewage sludge and ash from publicly owned treatment works (POTW); One of the documents which reports the results of a volunteer survey of sewage sludge and ash samples provided by 313 POTW; Second document which is a dose modeling document, using multiple exposure pathway modeling focused on a series of generic scenarios; Third document which is a guidance report providing recommendations on the management of radioactivity in sewage sludge and ash for POTW owners and operators; Explanation of how radioactive materials enter POTWs, provides criteria for evaluating levels of radioactive material in sludge and ash.
KW - Radioactive substances
KW - Hazardous wastes
KW - Sewage disposal
KW - Waste management
KW - Sanitation
KW - Environmental protection
N1 - Accession Number: 15836844; Bastian, R. K. 1; Email Address: bastian.robert@epa.gov; Bachmaier, J. T. 2; Schmidt, D. W. 3; Salomon, S. N. 4; Jones, A. 5; Chiu, W. A. 6; Setlow, L. W. 7; Wolbarst, A. B. 7; Yu, C. 8; Goodman, J. 9; Lenhart, T. 10; Affiliations: 1: USEPA, Office of Wastewater Management (4204M), Room 7220B EPA East, 1200 Pennsylvania Avenue, NW, Washington, DC 20460; 2: U.S. Department of Energy, 1000 Independence Avenue, SW, Washington, DC 20585; 3: U.S. Nuclear Regulatory Commission, NMSS, Washington, DC 20555-0001; 4: U.S. Nuclear Regulatory Commission, OSTP, Washington, DC 20555-0001; 5: U.S. Nuclear Regulatory Commission, RES, Washington, DC 20555-0001; 6: USEPA, Office of Research & Development (8623D), 1200 Pennsylvania Avenue, NW, Washington, DC 20460; 7: USEPA, Office of Radiation & Indoor Air (6680J), 1200 Pennsylvania Avenue, NW, Washington, DC 20460; 8: Argonne National Labs, EA Division, 9700 South Cass Avenue, Argonne, IL 60439; 9: New Jersey Department of Environmental Radiation, Bureau of Environmental Radiation, P.O. Box 415, Trenton, NJ 08625-0415; 10: NE Ohio Regional Sewer District, 3826 Euclid Avenue, Cleveland, OH 44115-2504; Issue Info: Jan/Feb2005, Vol. 34 Issue 1, p64; Thesaurus Term: Radioactive substances; Thesaurus Term: Hazardous wastes; Thesaurus Term: Sewage disposal; Thesaurus Term: Waste management; Thesaurus Term: Sanitation; Thesaurus Term: Environmental protection; NAICS/Industry Codes: 562112 Hazardous Waste Collection; NAICS/Industry Codes: 562110 Waste collection; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562910 Remediation Services; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 562212 Solid Waste Landfill; NAICS/Industry Codes: 562119 Other Waste Collection; Number of Pages: 11p; Illustrations: 3 Diagrams, 9 Charts; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Walker, J. Samuel
T1 - Hanford: A Conversation about Nuclear Waste and Cleanup.
JO - Journal of Environmental Quality
JF - Journal of Environmental Quality
Y1 - 2005/01//Jan/Feb2005
VL - 34
IS - 1
M3 - Book Review
SP - 399
EP - 399
SN - 00472425
AB - Reviews the book "Hanford: A Conversation About Nuclear Waste and Cleanup," by Roy E. Gephart.
KW - Radioactive wastes
KW - Nonfiction
KW - Gephart, Roy E.
KW - Hanford: A Conversation About Nuclear Waste & Cleanup (Book)
N1 - Accession Number: 15836882; Walker, J. Samuel 1; Email Address: Jsw@nrc.gov; Affiliations: 1: United States Nuclear Regulatory Commission, Washington, DC 20555; Issue Info: Jan/Feb2005, Vol. 34 Issue 1, p399; Thesaurus Term: Radioactive wastes; Subject Term: Nonfiction; Reviews & Products: Hanford: A Conversation About Nuclear Waste & Cleanup (Book); NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; People: Gephart, Roy E.; Number of Pages: 1/2p; Document Type: Book Review
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Walker, J. Samuel
AU - Vandervort, Bruce
T1 - Enola Gay and the Court of History.
JO - Journal of Military History
JF - Journal of Military History
Y1 - 2005/01//
VL - 69
IS - 1
M3 - Book Review
SP - 277
EP - 278
SN - 08993718
AB - Reviews the book "Enola Gay and the Court of History," by Robert P. Newman.
KW - ATOMIC bomb
KW - NONFICTION
KW - NEWMAN, Robert P.
KW - ENOLA Gay & the Court of History (Book)
N1 - Accession Number: 15396560; Walker, J. Samuel 1 Vandervort, Bruce 2; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, D.C. 2: Virginia Military Institute; Source Info: Jan2005, Vol. 69 Issue 1, p277; Subject Term: ATOMIC bomb; Subject Term: NONFICTION; Reviews & Products: ENOLA Gay & the Court of History (Book); People: NEWMAN, Robert P.; Number of Pages: 2p; Document Type: Book Review
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Orechwa, Yuri
T1 - Comments on ‘Evaluation of nuclear safety from the outputs of computer codes in the presence of uncertainties’ by W.T. Nutt and G.B. Wallis
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2005/01//
VL - 87
IS - 1
M3 - Article
SP - 133
EP - 135
SN - 09518320
N1 - Accession Number: 14427703; Orechwa, Yuri 1; Email Address: yxo@nrc.gov; Affiliation: 1: US Nuclear Regulatory Commission, 11555 Rockville Pike, Mail Stop: O-10B3, Rockville, MD 20852, USA; Source Info: Jan2005, Vol. 87 Issue 1, p133; Number of Pages: 3p; Document Type: Article
L3 - 10.1016/j.ress.2004.04.002
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Hibiki, Takashi
AU - Goda, Hiroshi
AU - Kim, Seungjin
AU - Ishii, Mamoru
AU - Uhle, Jennifer
T1 - Axial development of interfacial structure of vertical downward bubbly flow
JO - International Journal of Heat & Mass Transfer
JF - International Journal of Heat & Mass Transfer
Y1 - 2005/01/30/
VL - 48
IS - 3/4
M3 - Article
SP - 749
EP - 764
SN - 00179310
AB - Abstract: Accurate prediction of the interfacial area concentration is essential to successful development of the interfacial transfer terms in the two-fluid model. Mechanistic modeling of the interfacial area concentration entirely relies on accurate local flow measurements over extensive flow conditions and channel geometries. From this point of view, accurate measurements of flow parameters such as void fraction, interfacial area concentration, and interfacial velocity were performed by a multi-sensor probe at three axial locations as well as seven radial locations in vertical downward bubbly flows using a 25.4mm-diameter pipe. In the experiment, the superficial liquid velocity and the void fraction ranged from −1.25 to −3.11m/s and from 1.61% to 21.0%, respectively. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Heat & Mass Transfer is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - FLOW meters
KW - DETECTORS
KW - ATTENTION
KW - FLUIDS
KW - Downward bubbly flow
KW - Interfacial area concentration
KW - Interfacial area transport
KW - Multi-phase flow
KW - Resistivity multi-sensor probe
KW - Two-fluid model
N1 - Accession Number: 17152560; Hibiki, Takashi 1,2; Email Address: hibiki@rri.kyoto-u.ac.jp Goda, Hiroshi 2 Kim, Seungjin 2 Ishii, Mamoru 2; Email Address: ishii@ecn.purdue.edu Uhle, Jennifer 3; Affiliation: 1: Research Reactor Institute, Kyoto University, Kumatori, Sennan, Osaka 590-0494, Japan 2: School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA 3: Division of System Analysis and Regulatory Effectiveness Office of Research, US Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Jan2005, Vol. 48 Issue 3/4, p749; Subject Term: FLOW meters; Subject Term: DETECTORS; Subject Term: ATTENTION; Subject Term: FLUIDS; Author-Supplied Keyword: Downward bubbly flow; Author-Supplied Keyword: Interfacial area concentration; Author-Supplied Keyword: Interfacial area transport; Author-Supplied Keyword: Multi-phase flow; Author-Supplied Keyword: Resistivity multi-sensor probe; Author-Supplied Keyword: Two-fluid model; NAICS/Industry Codes: 334514 Totalizing Fluid Meter and Counting Device Manufacturing; Number of Pages: 16p; Document Type: Article
L3 - 10.1016/j.ijheatmasstransfer.2004.07.045
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Jones, Cynthia Gillian
T1 - A REVIEW OF THE HISTORY OF U.S. RADIATION PROTECTION REGULATIONS, RECOMMENDATIONS, AND STANDARDS.
JO - Health Physics
JF - Health Physics
Y1 - 2005/02//
VL - 88
IS - 2
M3 - Article
SP - 105
EP - 124
SN - 00179078
AB - Shortly after the discovery of x rays by Wilhelm Konrad Roentgen in 1895, and the isolation of the element radium by Pierre and Marie Curie three years later, the fascination with and potential for an array of uses of ionizing radiation in medicine, science, and technology was born. As with any new technology, there was a need to balance both the beneficial and potential detrimental effects of uses of these new technologies for the advancement of humankind. In the early days, radiation hazards were not well understood. Over the decades increasing concerns in the scientific community and lay population demanded that standardized guidance and recommendations be developed for the use of ionizing radiation. Today, U.S. radiation protection standards and recommendations to protect the occupational worker, members of the general public, and the environment are numerous and complex. This review summarizes the history of the development and application of radiation protection standards and regulations to assure the safe use of radiation and radioactive materials. The evolution and roles of international and national scientific recommending and regulatory organizations that shape U.S. radiation protection policy are described and discussed. [ABSTRACT FROM AUTHOR]
AB - Copyright of Health Physics is the property of Lippincott Williams & Wilkins and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radiation
KW - Ionizing radiation
KW - Radioactivity
KW - Radiation -- Safety measures
KW - Standards
KW - United States
KW - historical profiles
KW - regulations
KW - reviews
KW - safety standards
N1 - Accession Number: 16052422; Jones, Cynthia Gillian 1; Email Address: cgj@nrc.gov; Affiliations: 1: U.S. Nuclear Regulatory Commission, Office of Nuclear Security and Incident Response, Mail Stop T4-D22A, Washington, DC 20555; Issue Info: Feb2005, Vol. 88 Issue 2, p105; Thesaurus Term: Radiation; Thesaurus Term: Ionizing radiation; Thesaurus Term: Radioactivity; Subject Term: Radiation -- Safety measures; Subject Term: Standards; Subject: United States; Author-Supplied Keyword: historical profiles; Author-Supplied Keyword: regulations; Author-Supplied Keyword: reviews; Author-Supplied Keyword: safety standards; Number of Pages: 20p; Illustrations: 3 Charts; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Yow, Amy
AU - Walters, Brett
AU - Plott, Beth
AU - Laugherty, Ron
AU - Persensky, J.
T1 - Predicting nuclear power-plant operator performance using discrete event simulation.
JO - Cognition, Technology & Work
JF - Cognition, Technology & Work
Y1 - 2005/03//
VL - 7
IS - 1
M3 - Article
SP - 29
EP - 35
SN - 14355558
AB - A study was conducted to evaluate the use of discrete event simulation (DES) to predict human performance in a nuclear power plant control room environment. Computer simulation models of two disturbance scenarios were built using a simulation software program. Micro Saint. In parallel data were also collected at a full-scope training simulator at the Halden man-machine laboratory (HAMMLAB) in Halden, Norway, using crews of commercial nuclear power plant operators from the Loviisa nuclear power plant in Loviisa, Finland. Comparisons were made between predicted operator performance data generated by the simulation models and crew performance in the HAMMLAB experiment to determine the degree of agreement between the simulated data and the data from operators. The models were then used to extrapolate advanced control room conditions and alarm systems that were not tested in the HAMMLAB experiment. This report summarizes these findings and provides recommendations for improvements to the DES approach for use by a regulatory agency. [ABSTRACT FROM AUTHOR]
AB - Copyright of Cognition, Technology & Work is the property of Springer Science & Business Media B.V. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SIMULATION methods & models
KW - NUCLEAR power plant operators
KW - NUCLEAR power plants
KW - PERFORMANCE
KW - HUMAN-machine systems
KW - COMPUTER simulation
KW - COMPUTER software
KW - NORWAY
KW - FINLAND
KW - Modeling
KW - Nuclear
KW - Regulatory
KW - Simulation
KW - Validation
N1 - Accession Number: 17028190; Yow, Amy 1 Walters, Brett 1; Email Address: bwalters@maad.com Plott, Beth 1 Laugherty, Ron 1 Persensky, J. 2; Affiliation: 1: Micro Analysis and Design, Inc., USA 2: Division of Systems Research, U.S. Nuclear Regulatory Commission, USA; Source Info: Mar2005, Vol. 7 Issue 1, p29; Subject Term: SIMULATION methods & models; Subject Term: NUCLEAR power plant operators; Subject Term: NUCLEAR power plants; Subject Term: PERFORMANCE; Subject Term: HUMAN-machine systems; Subject Term: COMPUTER simulation; Subject Term: COMPUTER software; Subject Term: NORWAY; Subject Term: FINLAND; Author-Supplied Keyword: Modeling; Author-Supplied Keyword: Nuclear; Author-Supplied Keyword: Regulatory; Author-Supplied Keyword: Simulation; Author-Supplied Keyword: Validation; NAICS/Industry Codes: 417310 Computer, computer peripheral and pre-packaged software merchant wholesalers; NAICS/Industry Codes: 423430 Computer and Computer Peripheral Equipment and Software Merchant Wholesalers; NAICS/Industry Codes: 443144 Computer and software stores; NAICS/Industry Codes: 511211 Software publishers (except video game publishers); NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 7p; Document Type: Article
L3 - 10.1007/s10111-004-0167-x
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Walker, Samuel J.
T1 - Dr. Walker responds:.
JO - Journal of Military History
JF - Journal of Military History
Y1 - 2005/04//
VL - 69
IS - 2
M3 - Letter
SP - 625
EP - 625
SN - 08993718
AB - Presents a response by J. Samuel Walker to a letter to the editor about his review of the book "Enola Gay and the Court of History."
KW - LETTERS to the editor
KW - BOOKS
KW - REVIEWS
N1 - Accession Number: 16553272; Walker, Samuel J. 1; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, D.C.; Source Info: Apr2005, Vol. 69 Issue 2, p625; Subject Term: LETTERS to the editor; Subject Term: BOOKS; Subject Term: REVIEWS; Number of Pages: 1/5p; Document Type: Letter
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Prince, Robert J.
AU - Bradley, Scott E.
T1 - LIGHT WATER REACTOR HEALTH PHYSICS.
JO - Health Physics
JF - Health Physics
Y1 - 2005/06//
VL - 88
IS - 6
M3 - Article
SP - 665
EP - 675
SN - 00179078
AB - In this article an overview of the historical development of light water reactor health physics programs is presented. Operational health physics programs have developed and matured as experience in operating and maintaining light water reactors has been gained. Initial programs grew quickly in both size and complexity with the number and size of nuclear units under construction and in operation. Operational health physics programs evolved to face various challenges confronted by the nuclear industry, increasing the effectiveness of radiological safety measures. Industry improvements in radiological safety performance have resulted in significant decreases in annual collective exposures from a high value of 790 person-rem in 1980 to 117 person-rem per reactor in 2002. Though significant gains have been made, the continued viability of the nuclear power industry is confronted with an aging workforce, as well as the challenges posed by deregulation and the need to maintain operational excellence. [ABSTRACT FROM AUTHOR]
AB - Copyright of Health Physics is the property of Lippincott Williams & Wilkins and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Light water reactors
KW - Nuclear industry
KW - Industrial safety
KW - Medical physics
KW - Health Physics Society
KW - nuclear
KW - nuclear power plant
KW - reactor
KW - reviews
N1 - Accession Number: 17174407; Prince, Robert J. 1; Email Address: RJP4@nrc.gov; Bradley, Scott E. 2; Affiliations: 1: U.S. Nuclear Regulatory Commission, 475 Allendale Road, King of Prussia, PA 19406; 2: Texas Utilities-Comanche Peak Nuclear Station, P.O. Box 1002, Glen Rose, TX 76043; Issue Info: Jun2005, Vol. 88 Issue 6, p665; Thesaurus Term: Light water reactors; Thesaurus Term: Nuclear industry; Thesaurus Term: Industrial safety; Subject Term: Medical physics; Author-Supplied Keyword: Health Physics Society; Author-Supplied Keyword: nuclear; Author-Supplied Keyword: nuclear power plant; Author-Supplied Keyword: reactor; Author-Supplied Keyword: reviews; NAICS/Industry Codes: 541710 Research and development in the physical, engineering and life sciences; NAICS/Industry Codes: 541712 Research and Development in the Physical, Engineering, and Life Sciences (except Biotechnology); NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 11p; Illustrations: 1 Graph; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Csontos, Aladar A.
AU - Starke, Edgar A.
T1 - The effect of inhomogeneous plastic deformation on the ductility and fracture behavior of age hardenable aluminum alloys
JO - International Journal of Plasticity
JF - International Journal of Plasticity
Y1 - 2005/06//
VL - 21
IS - 6
M3 - Article
SP - 1097
EP - 1118
SN - 07496419
AB - Abstract: The role of alloy composition, grain structure, precipitate microstructure, and precipitate dislocation interactions on the plastic deformation characteristics and the resulting fracture behavior of two isotropic Al–Li–Cu–X alloys designated AF/C-458 (1.8 w/o Li) and AF/C-489 (2.1 w/o Li) was examined. Inhomogeneous deformation due to strain localization from the shearing of the δ′ (Al3Li), θ′ (Al2Cu), and T1 (Al2CuLi) precipitates lead to fine and coarse planar slip for the AF/C-458 and AF/C-489 alloys, respectively. The intensity of this planar slip was predicted through slip intensity calculations using precipitate density measurements, dislocation particle interactions, and grain boundary misorientation-slip continuity statistics. The slip intensity predictions were corroborated through atomic force microscopy (AFM) measured slip height offsets on the polished surface of single aged and 2% plastically strained tensile samples. Our results suggest that the low ductility of AF/C-489 in comparison to AF/C-458 is primarily due to the much larger slip lengths, i.e. grain size, which increased the strain localization and stress concentrations on grain boundaries, thus promoting low-energy intergranular fracture. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Plasticity is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - ALLOYS
KW - DUCTILITY
KW - MICROSCOPY
KW - MEASUREMENT
KW - Age-hardenable aluminum alloys
KW - Aluminum–lithium alloy
KW - Artificial aging
KW - Deformation mechanisms
KW - Fracture
KW - Inhomogeneous plastic deformation
KW - Planar slip
KW - Precipitation hardening
KW - Slip intensity
KW - Strain localization
N1 - Accession Number: 16134466; Csontos, Aladar A. 1 Starke, Edgar A. 2; Affiliation: 1: US Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Two White Flint North M/S T7F3, 11545 Rockville Pike, Rockville, MD 20852-2738, USA 2: Department of Materials Science and Engineering, University of Virginia, 116 Engineer’s Way, P.O. Box 400745, Charlottesville, VA 22904–4745, USA; Source Info: Jun2005, Vol. 21 Issue 6, p1097; Subject Term: ALLOYS; Subject Term: DUCTILITY; Subject Term: MICROSCOPY; Subject Term: MEASUREMENT; Author-Supplied Keyword: Age-hardenable aluminum alloys; Author-Supplied Keyword: Aluminum–lithium alloy; Author-Supplied Keyword: Artificial aging; Author-Supplied Keyword: Deformation mechanisms; Author-Supplied Keyword: Fracture; Author-Supplied Keyword: Inhomogeneous plastic deformation; Author-Supplied Keyword: Planar slip; Author-Supplied Keyword: Precipitation hardening; Author-Supplied Keyword: Slip intensity; Author-Supplied Keyword: Strain localization; Number of Pages: 22p; Document Type: Article
L3 - 10.1016/j.ijplas.2004.03.003
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Joyce, J.A.
AU - Tregoning, R.L.
T1 - Determination of constraint limits for cleavage initiated toughness data
JO - Engineering Fracture Mechanics
JF - Engineering Fracture Mechanics
Y1 - 2005/07//
VL - 72
IS - 10
M3 - Article
SP - 1559
EP - 1579
SN - 00137944
AB - Abstract: The proper constraint limits for cleavage initiated toughness data within the ductile-to-brittle transition regime have been studied extensively using both numerical analysis and analysis of experimental data. Historically, the experimentally based constraint limits have supported less conservative limits. This study conducts analysis of existing and new experimental data developed using data sets targeted to exhibit constraint loss toughness enhancement. Constraint herein is quantified in terms of the scaled specimen deformation level, more commonly known as M. It is expected that data with low M values will exhibit the greatest affect of constraint loss. Large data sets are therefore developed and extracted from the literature that include data with a large range of M levels and at least the required number of uncensored results with M >30 for valid T 0 measurement as per ASTM E1921-02. Differences in the calculated T 0 values using censoring limits of 5–500 are then determined. The onset of T lim differences due to constraint loss is examined by simply increasing the censoring limit, M lim, utilized in determining the indexing temperature, T lim, and evaluating differences between T 0 and the T lim values obtained using higher constraint limits. Bias resulting from this censoring procedure is examined using a Monte-Carlo analysis and shown to be small. Measurement of a high constraint T 0 in bend specimens is shown to require M lim >200. As M lim increases from 30 to 200 in bend specimens, the corresponding T lim can increase by approximately 15°C. Further increases in M lim do not result in substantial increases in T lim. This evolution buttresses previous numerical findings by Dodds and co-workers [Specimen size requirements for fracture toughness testing in the ductile-to-brittle transition regime, J Test Eval 1991;191:123–34; Size and deformation limits to maintain constraint in K Ic and J c testing of bend specimens. In: Kirk M, Ad Bakker, editors. Constraint effects in fracture theory and applications: second volume. ASTM STP 1244, 1995; Numerical investigation of 3-D constraint effects on brittle fracture in SE(B) and C(T) specimens, Int J Fract 1995;74:131–61] and provides a strong justification for changes to ASTM E1921-02 if a conservative, geometry insensitive, and transferable reference temperature, T 0, is to be determined using this standard. Possible short-term changes to ASTM E1921-02 could include raising M lim and requiring an upward shift of SE(B) T 0 values. A more desirable solution is to adjust individual K Jc toughness values before evaluation of T 0 to eliminate specimen geometry bias. [Copyright &y& Elsevier]
AB - Copyright of Engineering Fracture Mechanics is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NUMERICAL analysis
KW - MECHANICS (Physics)
KW - MONTE Carlo method
KW - FRACTURE mechanics
N1 - Accession Number: 17464857; Joyce, J.A. 1; Email Address: jaj@usna.edu Tregoning, R.L. 2; Affiliation: 1: United States Naval Academy, Annapolis, MD 21402, USA 2: Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Source Info: Jul2005, Vol. 72 Issue 10, p1559; Subject Term: NUMERICAL analysis; Subject Term: MECHANICS (Physics); Subject Term: MONTE Carlo method; Subject Term: FRACTURE mechanics; Number of Pages: 21p; Document Type: Article
L3 - 10.1016/j.engfracmech.2004.11.001
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Hsiung, S.M.
AU - Chowdhury, A.H.
AU - Nataraja, M.S.
T1 - Numerical simulation of thermal–mechanical processes observed at the Drift-Scale Heater Test at Yucca Mountain, Nevada, USA
JO - International Journal of Rock Mechanics & Mining Sciences
JF - International Journal of Rock Mechanics & Mining Sciences
Y1 - 2005/07//
VL - 42
IS - 5/6
M3 - Article
SP - 652
EP - 666
SN - 13651609
AB - Abstract: Results from the 4-year-long heating phase of the Drift-Scale Heater Test at the Exploratory Studies Facility at Yucca Mountain, Nevada, USA, provide a basis to evaluate conceptual and numerical models used to simulate thermal–mechanical coupled processes expected to occur at the potential geologic repository at Yucca Mountain. The objectives of the evaluation were to investigate coupled processes associated with (i) temperature effects on mechanical deformation and (ii) effect of thermal–mechanical processes on rock-mass permeability. Two-dimensional numerical models were built to perform the thermal–mechanical analyses. Thermal–mechanical simulations were predicated on a continuum representation of a deformation-permeability relationship based on fracture normal stress. The estimated trend of permeability responses using a normal stress-based deformation-permeability relationship compared reasonably to that measured in the coupled thermal–mechanical analyses. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Rock Mechanics & Mining Sciences is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - GEOLOGY
KW - PERMEABILITY
KW - POROSITY
KW - YUCCA Mountain (Nev.)
KW - NEVADA
KW - Fracture closure
KW - Fracture normal stress
KW - Fracture permeability
KW - Heater Test
KW - Rock-mass permeability
KW - Thermal–mechanical process
KW - Thermally induced mechanical deformation
N1 - Accession Number: 18173104; Hsiung, S.M. 1; Email Address: shsiung@swri.org Chowdhury, A.H. 1 Nataraja, M.S. 2; Affiliation: 1: Center for Nuclear Waste Regulatory Analyses, 6220 Culebra Road, San Antonio, TX 78238, USA 2: US Nuclear Regulatory Commission, USA; Source Info: Jul2005, Vol. 42 Issue 5/6, p652; Subject Term: GEOLOGY; Subject Term: PERMEABILITY; Subject Term: POROSITY; Subject Term: YUCCA Mountain (Nev.); Subject Term: NEVADA; Author-Supplied Keyword: Fracture closure; Author-Supplied Keyword: Fracture normal stress; Author-Supplied Keyword: Fracture permeability; Author-Supplied Keyword: Heater Test; Author-Supplied Keyword: Rock-mass permeability; Author-Supplied Keyword: Thermal–mechanical process; Author-Supplied Keyword: Thermally induced mechanical deformation; Number of Pages: 15p; Document Type: Article
L3 - 10.1016/j.ijrmms.2005.03.006
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Slater, Deb
AU - Habib, Ibrahim
AU - Yelowitz, Jason
AU - Diaz, Nils J.
AU - Carcelle, Yves
T1 - LETTERS.
JO - Time International (Canada Edition)
JF - Time International (Canada Edition)
Y1 - 2005/07/11/
VL - 166
IS - 2
M3 - Letter
SP - 4
EP - 4
PB - Time Inc.
SN - 03158446
AB - Presents letters to the editor in response to articles and topics discussed in previous issues of "Time" Canadian. "Inside the Interrogation of Detainee 063," which looked at the treatment of prisoners at the Guantánamo Bay Naval Base in Cuba; "Are These Towers Safe?" which focused on security measures at nuclear power plants in the U.S.
KW - NUCLEAR power plants
KW - LETTERS to the editor
KW - PRISONERS' rights
KW - INSTITUTIONALIZED persons -- Abuse of
KW - SAFETY measures
KW - SECURITY measures
KW - GUANTANAMO Bay (Cuba)
N1 - Accession Number: 17732765; Slater, Deb; Habib, Ibrahim; Yelowitz, Jason; Diaz, Nils J. 1; Carcelle, Yves 2; Affiliations: 1: Chairman, U.S. Nuclear Regulatory Commission, Rockville, Md.; 2: President, Louis Vuitton Malletier, Paris; Issue Info: 7/11/2005, Vol. 166 Issue 2, p4; Thesaurus Term: NUCLEAR power plants; Subject Term: LETTERS to the editor; Subject Term: PRISONERS' rights; Subject Term: INSTITUTIONALIZED persons -- Abuse of; Subject Term: SAFETY measures; Subject Term: SECURITY measures; Subject: GUANTANAMO Bay (Cuba); NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 1p; Illustrations: 1 Color Photograph; Document Type: Letter; Full Text Word Count: 640
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DP - EBSCOhost
DB - buh
ER -
TY - GEN
AU - Habib, Ibrahim
AU - Yelowitz, Jason
AU - Fouladi, Roya
AU - Wasserman, David
AU - Eberhardt, Al
AU - Abinashi, Ramji
AU - Crotta, Alex
AU - Spencer, Ron
AU - Wildenthal, Bryan H.
AU - Diaz, Nils J.
AU - Long, Harriet C.
AU - Johnpaul, Obienu Ifeanyi
AU - Magtoto, Ernesto Kelly
AU - Vargas, May
AU - Carcelle, Yves
T1 - LETTERS.
JO - Time International (South Pacific Edition)
JF - Time International (South Pacific Edition)
Y1 - 2005/07/11/
IS - 27
M3 - Letter
SP - 4
EP - 8
PB - Time Inc.
SN - 08180628
AB - Several letters to the editor are presented in response to articles in the June 20, 2005 issue including "Inside the Interrogation of Detainee 063," "Are These Towers Safe," and "Bring Them Back."
KW - NUCLEAR power plants
KW - LETTERS to the editor
KW - PRISONERS
KW - POLICE questioning
KW - IRISH
N1 - Accession Number: 23533166; Habib, Ibrahim; Yelowitz, Jason; Fouladi, Roya; Wasserman, David; Eberhardt, Al; Abinashi, Ramji; Crotta, Alex; Spencer, Ron; Wildenthal, Bryan H. 1; Diaz, Nils J. 2; Long, Harriet C.; Johnpaul, Obienu Ifeanyi; Magtoto, Ernesto Kelly; Vargas, May; Carcelle, Yves 3; Affiliations: 1: ASSOCIATE PROFESSOR THOMAS JEFFERSON SCHOOL OF LAW San Diego; 2: CHAIRMAN U.S. NUCLEAR REGULATORY COMMISSION Rockville, Maryland; 3: PRESIDENT LOUIS VUITTON MALLETIER Paris; Issue Info: 7/11/2006, Issue 27, p4; Thesaurus Term: NUCLEAR power plants; Subject Term: LETTERS to the editor; Subject Term: PRISONERS; Subject Term: POLICE questioning; Subject Term: IRISH; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 3p; Illustrations: 1 Color Photograph; Document Type: Letter; Full Text Word Count: 1734
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Sherbini, Sami S.
AU - Decicco, Joseph E.
T1 - THE USE OF RADIATION SURVEYS TO ESTIMATE THE RADIATION EFFECTIVE DOSE TO VISITORS OF HOSPITALIZED PATIENTS--A THEORETICAL STUDY.
JO - Health Physics
JF - Health Physics
Y1 - 2005/09//
VL - 89
IS - 3
M3 - Article
SP - 216
EP - 223
SN - 00179078
AB - Members of the public visiting hospitalized patients undergoing nuclear medicine procedures or brachytherapy are exposed to radiation emanating from the patient. The radiation protection staff at the hospital is responsible for ensuring that the doses to these visitors are kept as low as is reasonably achievable and are maintained below applicable regulatory limits. These limits are normally expressed in terms of the effective dose to the visitor. Direct measurement of the effective dose, however, is not feasible, and the use of a quantity that provides a reasonable estimate, referred to as a surrogate, is required. This study used Monte Carlo radiation transport calculations to examine the feasibility of using bedside survey results, in units of roentgens per hour, as a surrogate for estimating the effective dose to a person who may be present at the survey location. The Monte Carlo code used in this work was MCNP Version 5. In these calculations, both the patient and the visitor were modeled using modified Medical Internal Radiation Dose anthropomorphic phantoms. Radioactive material that emitted monoenergetic photons was located in several of the patient's organs in turn, and the bedside exposure rates and the effective doses at the same location were calculated. The calculations were repeated for several visitor locations, both at bedside along the length of the bed, and at increasing distances from the bed. The ratios of the exposure rates to the effective dose rates at each location gave an indication of the utility of the exposure rate measurements in providing a reasonable estimate of the effective dose. The results indicated that the survey data provided estimates of the effective dose within recommended accuracy for many expo- sure situations, but underestimated the effective dose to the visitor for other situations, especially locations close to bedside and for lower energy radiations. Use of appropriate correction factors based on this work could improve the utility of the survey data for the underestimated situations, and the exposure rate data could still be used to estimate the dose to a visitor within recommended accuracy, provided the estimated dose does not approach too closely to the applicable limit. [ABSTRACT FROM AUTHOR]
AB - Copyright of Health Physics is the property of Lippincott Williams & Wilkins and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radiation -- Safety measures
KW - Hospital patients
KW - Medical radiology
KW - Nuclear medicine
KW - Conferences & conventions
KW - Surveys
KW - effective dose
KW - exposure
KW - population
KW - radiation therapy
KW - surveys
N1 - Accession Number: 18026936; Sherbini, Sami S. 1; Email Address: sxs2@nrc.gov; Decicco, Joseph E. 1; Affiliations: 1: United States Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Division of Industrial and Medical Nuclear Safety, Washington, DC 20555.; Issue Info: Sep2005, Vol. 89 Issue 3, p216; Subject Term: Radiation -- Safety measures; Subject Term: Hospital patients; Subject Term: Medical radiology; Subject Term: Nuclear medicine; Subject Term: Conferences & conventions; Subject Term: Surveys; Author-Supplied Keyword: effective dose; Author-Supplied Keyword: exposure; Author-Supplied Keyword: population; Author-Supplied Keyword: radiation therapy; Author-Supplied Keyword: surveys; NAICS/Industry Codes: 561920 Convention and Trade Show Organizers; NAICS/Industry Codes: 621512 Diagnostic Imaging Centers; Number of Pages: 8p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Wolbarst, Anthony B.
AU - Biwer, Bruce M.
AU - Cady, Ralph
AU - Chen, Shih-Yew
AU - Domotor, Stephen
AU - Egidi, Philip
AU - LePoire, David J.
AU - Mo, Tin
AU - Peterson, Julie
AU - Walker, Stuart
T1 - ISCORS Catalog of References to Parameter Values and Distributions Used in Environmental Pathway Modeling for Cleanup of Sites Contaminated with Radioactivity.
JO - Health Physics
JF - Health Physics
Y1 - 2005/11/02/2005 Supplement
VL - 89
M3 - Article
SP - S91
EP - S99
SN - 00179078
AB - Federal and state regulatory agencies that are concerned with issues of environmental management have adopted approaches toward policy-making that are dose- and risk-informed. To that end they (and others) have developed environmental models and computer codes to mimic the transport of contaminants along air, water, food-chain, and related pathways for estimating potential exposures, doses, and risks to individuals, populations, and ecosystems. Their calculations commonly find application in the planning of remediation, and thereafter in the demonstration of compliance with federal and state cleanup standards. As the models and codes have become more sophisticated, so also have requirements on the accuracy and level of detail of the numerical point values and probability distributions of environmental transfer factors and other parameters that serve as input parameters to them. In response to this growing need, the federal Inter-agency Steering Committee On Radiation Standards (ISCORS) and the Argonne National Laboratory have developed an on-line, national repository of information on parameter values and distributions of known provenance and demonstrated utility. The IS-CORS Catalog of References to Parameter Values and Distributions Used in Environmental Pathway Modeling for Cleanup of Sites Contaminated with Radioactivity is a web-based, indexed compilation of references, compendia, databases, and other sources of peer-reviewed information on parameters. It does not itself contain numerical point values or distributions for any particular parameter, but rather it provides links or directions to sites or other published materials where such information can be obtained. Designed to be user-friendly, easily search. able, and readily up-dateable, the Catalog is being filled, after some initial priming, mainly through on-line submissions of proposed references by the Catalog users themselves. The relevant information on a proposed reference is submitted to ISCORS in a simple, standardized format; it is vetted (with acceptance criteria such as publication in a peer-reviewed technical journal, or appearance in a formally-issued federal agency report) and then added semi-automatically to the Catalog. Built around a relational data- base, the system offers subject- and text-search capabilities, provides information on parameter definitions and methods of measurement, on transport/exposure pathways, and on standard models and codes. The Catalog is intended for use by (and being populated by) the professionals, managers, and others involved or interested in the application of pathway modeling to estimate doses and risks associated with sites contaminated with radioactive or other hazardous materials. [ABSTRACT FROM AUTHOR]
AB - Copyright of Health Physics is the property of Lippincott Williams & Wilkins and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear reactions
KW - Environmental engineering
KW - Radiation
KW - Environmental protection
KW - Radioactive wastes
KW - Radioactivity -- Safety measures
KW - computers
KW - operational topic
KW - peer review
KW - safety standards
N1 - Accession Number: 18794836; Wolbarst, Anthony B. 1; Biwer, Bruce M. 2; Cady, Ralph 3; Chen, Shih-Yew 2; Domotor, Stephen 4; Egidi, Philip 5; LePoire, David J. 2; Mo, Tin 3; Peterson, Julie 6; Walker, Stuart 2; Affiliations: 1: U.S. Environmental Protection Agency, Washington, DC 20460.; 2: Argonne National Laboratory, Argonne, IL 60439.; 3: U.S. Nuclear Regulatory Commission, Washington, DC 20555.; 4: U.S. Department of Energy, Washington, DC 20402.; 5: Colorado Department of Public Health and Environment, Denver, CO 80246.; 6: U.S. Army Corps of Engineers, Omaha, NE 68144.; Issue Info: 2005 Supplement, Vol. 89, pS91; Thesaurus Term: Nuclear reactions; Thesaurus Term: Environmental engineering; Thesaurus Term: Radiation; Thesaurus Term: Environmental protection; Thesaurus Term: Radioactive wastes; Thesaurus Term: Radioactivity -- Safety measures; Author-Supplied Keyword: computers; Author-Supplied Keyword: operational topic; Author-Supplied Keyword: peer review; Author-Supplied Keyword: safety standards; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; Number of Pages: 9p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Jones, Cynthia G.
T1 - Regulatory Control of Radiation Sources.
JO - Health Physics
JF - Health Physics
Y1 - 2005/12//
VL - 89
IS - 6
M3 - Book Review
SP - 692
EP - 692
SN - 00179078
AB - Reviews the book "Regulatory Control of Radiation Sources."
KW - Radiation
KW - Nonfiction
KW - Regulatory Control of Radiation Sources (Book)
N1 - Accession Number: 19024159; Jones, Cynthia G. 1; Email Address: cgj@nrc.gov; Affiliations: 1: U.S. Nuclear Regulatory Commission, Office of Nuclear Security and Incident Response, Mail Stop T4D-22A, Washington, DC 20555.; Issue Info: Dec2005, Vol. 89 Issue 6, p692; Thesaurus Term: Radiation; Subject Term: Nonfiction; Reviews & Products: Regulatory Control of Radiation Sources (Book); Number of Pages: 1/2p; Document Type: Book Review
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Wolbarst, A. B.
AU - Chiu, W. A.
AU - Yu, C.
AU - Aiello, K.
AU - Bachmaier, J. T.
AU - Bastian, R. K.
AU - Cheng, J. -J.
AU - Goodman, J.
AU - Hogan, R.
AU - Jones, A. R.
AU - Kamboj, S.
AU - Lenhartt, T.
AU - Ott, W. R.
AU - Rubin, A.
AU - Salomon, S. N.
AU - Schmidt, D. W.
AU - Setlow, L. W.
T1 - RADIOACTIVE MATERIALS IN BIOSOLIDS: DOSE MODELING.
JO - Health Physics
JF - Health Physics
Y1 - 2006/01//
VL - 90
IS - 1
M3 - Article
SP - 16
EP - 30
SN - 00179078
AB - The Interagency Steering Committee on Radiation Standards (ISCORS) has recently completed a study of the occurrence within the United States of radioactive materials in sewage sludge and sewage incineration ash. One component of that effort was an examination of the possible transport of radioactivity from sludge into the local environment and the subsequent exposure of humans. A stochastic environmental pathway model was applied separately to seven hypothetical, generic sludge-release scenarios, leading to the creation of seven tables of Dose-to-Source Ratios (DSR), which can be used in translating from specific activity in sludge into dose to an individual. These DSR values were then combined with the results of an ISCORS survey of sludge and ash at more than 300 publicly owned treatment works, to explore the potential for radiation exposure of sludge workers and members of the public. This paper provides a brief overview of the pathway modeling methodology employed in the exposure and dose assessments and discusses technical aspects of the results obtained. [ABSTRACT FROM AUTHOR]
AB - Copyright of Health Physics is the property of Lippincott Williams & Wilkins and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radiation exposure
KW - Radiation injuries
KW - Nuclear reactions
KW - Radiation -- Safety measures
KW - Radiation-protective agents
KW - United States
KW - contamination
KW - dose assessment
KW - environmental
KW - environmental assessment
KW - environmental transport
N1 - Accession Number: 19242456; Wolbarst, A. B. 1; Email Address: wolbarst.anthony@epa.gov; Chiu, W. A. 1; Yu, C. 2; Aiello, K. 3; Bachmaier, J. T. 4; Bastian, R. K. 1; Cheng, J. -J. 2; Goodman, J. 5; Hogan, R. 6; Jones, A. R. 6; Kamboj, S. 2; Lenhartt, T. 7; Ott, W. R. 6; Rubin, A. 1; Salomon, S. N. 6; Schmidt, D. W. 6; Setlow, L. W. 1; Affiliations: 1: U.S. Environmental Protection Agency, Washington, DC.; 2: Argonne National Laboratory, Argonne, IL.; 3: Middlesex County Utilities Authority, Sayreville, NJ.; 4: U.S. Department of Energy, Washington, DC.; 5: Department of Environmental Protection, State of NJ.; 6: U.S. Nuclear Regulatory Commission, Washington, DC.; 7: Northeast Ohio Regional Sewer District, NEORSD.; Issue Info: Jan2006, Vol. 90 Issue 1, p16; Thesaurus Term: Radiation exposure; Thesaurus Term: Radiation injuries; Thesaurus Term: Nuclear reactions; Subject Term: Radiation -- Safety measures; Subject Term: Radiation-protective agents; Subject: United States; Author-Supplied Keyword: contamination; Author-Supplied Keyword: dose assessment; Author-Supplied Keyword: environmental; Author-Supplied Keyword: environmental assessment; Author-Supplied Keyword: environmental transport; Number of Pages: 15p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Easton, E. P.
AU - Faille, S.
T1 - Advantages of using standardised review procedures in certifying Type B radioactive material packages.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2006/03//
VL - 17
IS - 1
M3 - Article
SP - 19
EP - 21
PB - Taylor & Francis Ltd
SN - 17465095
AB - This paper presents the advantages of adopting well documented standardised review practices for reviewing Type B package designs. The US experience using standardised review plans and guidance has shown them to be a valuable tool in achieving more consistent and efficient package reviews, in training and qualifying technical reviewers and in enhancing the understanding of the package certification process by the public and industry. In addition, the standardised review practices, as living documents, have proved to be an effective method of incorporating new technical advances into the review process, and have provided a vehicle to make that knowledge widely available to fellow reviewers, the public and industry. Canada implemented a new internal review process in early 2003 to standardise the review of applications for certification of Type B packages. Based on the similarity of these approaches, the USA and Canada have started discussions on a 'North American system' for the unilateral approval of Type B(U) packages. This initiative is looking into how each country is currently reviewing transport package applications to see if agreement can be reached on accepting Type B certifications on a reciprocal basis, i.e. without additional review. Based on the experience in Canada and the USA, the authors believe that the use of standardised review processes, coupled with the knowledge and experience found in the International Atomic Energy Agency's transportation advisory material (TS-G-1·1) and series of TECDOCS, could also be used to develop a standard internationally accepted review process that could enhance the acceptance of unilateral approvals for Type B packages. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Materials handling
KW - Packaging -- Design & construction
KW - Evaluation
KW - United States
KW - Canada
KW - Procedures
KW - TYPE B(U)
KW - UNILATERAL APPROVAL
KW - US
N1 - Accession Number: 21799991; Easton, E. P. 1; Faille, S. 2; Email Address: Failles@cnsc-ccsn.gc.ca; Affiliations: 1: United States Nuclear Regulatory Commission, Washington DC 20555, USA; 2: Canadian Nuclear Safety Commission, P.O. Box 1046, Station B, 280 Slater Street, Ottawa, K1P5S9, Canada; Issue Info: 2006, Vol. 17 Issue 1, p19; Thesaurus Term: Materials handling; Subject Term: Packaging -- Design & construction; Subject Term: Evaluation; Subject: United States; Subject: Canada; Author-Supplied Keyword: Procedures; Author-Supplied Keyword: TYPE B(U); Author-Supplied Keyword: UNILATERAL APPROVAL; Author-Supplied Keyword: US; NAICS/Industry Codes: 561910 Packaging and Labeling Services; NAICS/Industry Codes: 541420 Industrial Design Services; Number of Pages: 3p; Document Type: Article
L3 - 10.1179/174651006X95565
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Dinwiddie, Cynthia L.
AU - Bradbury, Kelly Keighley
AU - McGinnis, Ronald N.
AU - Fedors, Randall W.
AU - Ferrill, David A.
T1 - Fault Zone Deformation Overprints Permeability of Nonwelded Ignimbrite: Chalk Cove Fault, Bishop Tuff, Bishop, California.
JO - Vadose Zone Journal
JF - Vadose Zone Journal
Y1 - 2006/05//
VL - 5
IS - 2
M3 - Article
SP - 8
EP - 8
AB - Deformation-induced secondary heterogeneities associated with a steeply-dipping normal fault in the nonwelded Bishop Tuff were examined in a multidisciplinary study using in situ gas permeability tests, structural mapping, and laboratory analyses as analogs for fault deformation features within the poorly exposed Paintbrush nonwelded hydrogeologic unit at Yucca Mountain, Nevada. Three features of fault-zone deformation were identified that may act to constrain lateral flow in unsaturated nonwelded ignimbrites. First, development of a fault gouge, with a decrease in grain size caused by grain comminution, decreases the permeability of this element with respect to the host rock. Second, long open fractures paralleling the fault have an increased permeability with respect to the host rock. Third, small-scale fractures and grain rotation in adjacent matrix blocks induce an interconnected porosity not seen in host rock. Intrinsic permeability variation beyond what is observed in the host rock reflects the effect of small-scale deformation in the matrix adjacent the fault. These features can reduce the continuity of potential capillary or permeability barriers, and thus limit any redistribution of percolation that would result from lateral flow diversion. [ABSTRACT FROM AUTHOR]
AB - Copyright of Vadose Zone Journal is the property of American Society of Agronomy and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Hydrogeology
KW - Permeability
KW - Fault gouge
KW - Rocks
KW - Matrices
N1 - Accession Number: 21281378; Dinwiddie, Cynthia L. 1,2; Email Address: cdinwiddie@swri.org; Bradbury, Kelly Keighley 3; McGinnis, Ronald N. 1,2; Fedors, Randall W. 1,4; Ferrill, David A. 1,2; Affiliations: 1: Center for Nuclear Waste Regulatory Analyses, Geosciences and Engineering Division of Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238; 2: Dept. of Earth, Material, and Planetary Sciences, Geosciences and Engineering Division of Southwest Research Institute; 3: Utah Faults, Fractures, and Fluids (UF3), Innovation Campus, Utah State Univ., 1770 Research Park Way, Ste. 183, North Logan, UT 84341; 4: U.S. Nuclear Regulatory Commission; Issue Info: May2006, Vol. 5 Issue 2, p8; Thesaurus Term: Hydrogeology; Thesaurus Term: Permeability; Subject Term: Fault gouge; Subject Term: Rocks; Subject Term: Matrices; Number of Pages: 1p; Document Type: Article
L3 - 10.2136/vzj2005.0062
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Ankem, Sreeramamurthy
AU - Margolin, Harold
AU - Greene, Charles A.
AU - Neuberger, Brett W.
AU - Oberson, P. Gregory
T1 - Mechanical properties of alloys consisting of two ductile phases
JO - Progress in Materials Science
JF - Progress in Materials Science
Y1 - 2006/07//
VL - 51
IS - 5
M3 - Article
SP - 632
EP - 709
SN - 00796425
AB - Abstract: A large number of engineering alloys consist of two ductile phases; for example α/β titanium alloys, α/β brasses and dual phase steels. Whenever a material consisting of two or more component phases with different properties is subjected to stress, in general, the phases deform differently. This results in additional interaction stresses and strains and their magnitude depends on such factors as the property difference between phases, and morphology and volume fraction of phases. Due to these complexities, the properties of two-phase materials, in general, cannot be predicted on the basis of simple laws such as the law of mixtures. The aim of this review paper is to describe how the various parameters such as morphology and volume percent of phases affect the mechanical properties of two-phase materials. Such information will be of great use in designing and selecting two-phase materials for various engineering applications. [Copyright &y& Elsevier]
AB - Copyright of Progress in Materials Science is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - TITANIUM alloys
KW - ENGINEERING
KW - METALLIC composites
KW - METALS
KW - PHASE rule & equilibrium
N1 - Accession Number: 20183206; Ankem, Sreeramamurthy 1; Email Address: ankem@umd.edu Margolin, Harold 2 Greene, Charles A. 3 Neuberger, Brett W. 4 Oberson, P. Gregory 1; Affiliation: 1: Department of Materials Science and Engineering, University of Maryland – College Park, College Park, MD 20742-2115, United States 2: Department of Mechanical Engineering, Polytechnic University, Brooklyn, NY 11201, United States 3: United States Nuclear Regulatory Commission, Washington, DC 20555-0001, United States 4: Bettis Atomic Power Laboratory, West Mifflin, PA 15122, United States; Source Info: Jul2006, Vol. 51 Issue 5, p632; Subject Term: TITANIUM alloys; Subject Term: ENGINEERING; Subject Term: METALLIC composites; Subject Term: METALS; Subject Term: PHASE rule & equilibrium; NAICS/Industry Codes: 332810 Coating, engraving, cold and heat treating and allied activities; NAICS/Industry Codes: 332812 Metal Coating, Engraving (except Jewelry and Silverware), and Allied Services to Manufacturers; NAICS/Industry Codes: 332811 Metal Heat Treating; NAICS/Industry Codes: 331490 Non-ferrous metal (except copper and aluminum) rolling, drawing, extruding and alloying; Number of Pages: 78p; Document Type: Article
L3 - 10.1016/j.pmatsci.2005.10.003
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Or, Dani
AU - Fedors, Randall
AU - Stothoff, Stuart
AU - Tuller, Markus
T1 - Reply to comment by Stefan Finsterle on 'Seepage into drifts and tunnels in unsaturated fractured rock'.
JO - Water Resources Research
JF - Water Resources Research
Y1 - 2006/07//
VL - 42
IS - 7
M3 - Article
SP - n/a
EP - n/a
SN - 00431397
KW - fracture and flow
KW - permeability and porosity
KW - transport properties
KW - vadose zone
N1 - Accession Number: 87145157; Or, Dani 1; Fedors, Randall 2; Stothoff, Stuart 3; Tuller, Markus 4; Affiliations: 1: Laboratory of Soil and Environmental Physics, Ecole Polytechnique Federale de Lausanne; 2: U.S. Nuclear Regulatory Commission; 3: Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute; 4: Soil and Land Resources Division, University of Idaho; Issue Info: 2006, Vol. 42 Issue 7, pn/a; Author-Supplied Keyword: fracture and flow; Author-Supplied Keyword: permeability and porosity; Author-Supplied Keyword: transport properties; Author-Supplied Keyword: vadose zone; Number of Pages: 3p; Document Type: Article
L3 - 10.1029/2006WR005008
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - EricksonKirk, Mark
AU - EricksonKirk, Marjorie
T1 - An upper-shelf fracture toughness master curve for ferritic steels
JO - International Journal of Pressure Vessels & Piping
JF - International Journal of Pressure Vessels & Piping
Y1 - 2006/08//
VL - 83
IS - 8
M3 - Article
SP - 571
EP - 583
SN - 03080161
AB - Abstract: When assessing the resistance of a steel structure to failure under load, fracture toughness is a key input variable. Since it is usually not possible to establish a priori if the anticipated service temperature (or temperatures) is in the fracture mode transition or on the upper shelf, it is useful to know the temperature dependence of fracture toughness in both the transition and on the upper shelf. In the transition, the master curve proposed by Wallin defines both the variation of the median value of fracture toughness with temperature and the scatter of fracture toughness about this median value. However, Wallin''s master curve does not quantify fracture toughness on the upper shelf. In this paper we assemble a database of upper shelf fracture toughness data (J Ic) for ferritic steels. These data demonstrate that the temperature dependence of upper J Ic is consistent for all ferritic steels contained in the database and has the same form as the temperature dependence of the flow strength anticipated from dislocation mechanics considerations. This similarity between the temperature dependence of flow strength and the temperature dependence of J Ic is physically expected because both directly depend upon the energy required for dislocation mobility in the ferrite matrix. Both the empirically derived model and the physical basis for the model are described. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Pressure Vessels & Piping is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - STAINLESS steel
KW - NUCLEAR facilities
KW - STEAM generators
KW - FERRITES (Magnetic materials)
KW - Ferritic steels
KW - Fracture toughness
KW - Hardening behaviour
KW - HSLA steel.
KW - Irradiation effects
KW - Master curve
KW - Nuclear reactor pressure vessel steel
KW - Upper shelf
N1 - Accession Number: 22221694; EricksonKirk, Mark 1; Email Address: mtk@nrc.gov EricksonKirk, Marjorie 2; Email Address: erickson.peai@verizon.net; Affiliation: 1: United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Mail Stop T10-E10, 11545 Rockville Pike, Rockville, MD 20852, USA 2: Phoenix Engineering Associates Inc., 979 Day Road, Sykesville, MD 21784, USA; Source Info: Aug2006, Vol. 83 Issue 8, p571; Subject Term: STAINLESS steel; Subject Term: NUCLEAR facilities; Subject Term: STEAM generators; Subject Term: FERRITES (Magnetic materials); Author-Supplied Keyword: Ferritic steels; Author-Supplied Keyword: Fracture toughness; Author-Supplied Keyword: Hardening behaviour; Author-Supplied Keyword: HSLA steel.; Author-Supplied Keyword: Irradiation effects; Author-Supplied Keyword: Master curve; Author-Supplied Keyword: Nuclear reactor pressure vessel steel; Author-Supplied Keyword: Upper shelf; NAICS/Industry Codes: 416120 Plumbing, heating and air-conditioning equipment and supplies merchant wholesalers; NAICS/Industry Codes: 221330 Steam and Air-Conditioning Supply; NAICS/Industry Codes: 423720 Plumbing and Heating Equipment and Supplies (Hydronics) Merchant Wholesalers; NAICS/Industry Codes: 331110 Iron and Steel Mills and Ferroalloy Manufacturing; Number of Pages: 13p; Document Type: Article
L3 - 10.1016/j.ijpvp.2006.05.001
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - ERICKSONKIRK, MARJORIE
AU - ERICKSONKIRK, MARK
T1 - The relationship between the transition and upper-shelf fracture toughness of ferritic steels.
JO - Fatigue & Fracture of Engineering Materials & Structures
JF - Fatigue & Fracture of Engineering Materials & Structures
Y1 - 2006/09//
VL - 29
IS - 9/10
M3 - Article
SP - 672
EP - 684
PB - Wiley-Blackwell
SN - 8756758X
AB - Conventionally, the transition fracture toughness and upper-shelf fracture toughness of ferritic steels are viewed as separate properties: they are measured by tests conducted according to different standards, and neither toughness property can be estimated (except in very qualitative terms) based on knowledge of the other. Information presented in this paper demonstrates that quite the opposite is true: transition fracture toughness and upper-shelf fracture toughness are directly related because the microstructural features responsible for both the temperature dependence of fracture toughness and for the magnitude of fracture toughness at any given temperature are the same in both transition and on the upper shelf (the lattice structure controls the temperature dependence, while the size and distribution of second-phase particles control crack initiation and thus the magnitude of fracture toughness). These features bind the transition fracture toughness and upper-shelf fracture toughness together in a way that is extremely consistent for all ferritic steels. We present empirical evidence of this relationship based on fracture toughness data from a variety of ferritic steels: various heats of nuclear grade pressure vessel steels and welds (both before and after irradiation), copper precipitation hardened steels used in naval ship construction and mild steels used in ship construction. In total, these data span a broad range of T0: from −180 °C to +140 °C. The combination of this theoretically motivated, empirically calibrated relationship between transition and upper-shelf toughness with Wallin's Master Curve (for toughness in fracture mode transition), and EricksonKirk's proposed Master Curve for toughness on the upper shelf, produces a model that predicts the temperature dependence of, and scatter in, fracture toughness of ferritic steels throughout the transition and upper-shelf temperature regimes. As input information, this model needs only the value of T0, which can be estimated by performing fracture toughness tests according to the protocols of ASTM test standard E1921-05. [ABSTRACT FROM AUTHOR]
AB - Copyright of Fatigue & Fracture of Engineering Materials & Structures is the property of Wiley-Blackwell and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - FERRITIC steel
KW - DUCTILITY
KW - STEEL
KW - BRITTLENESS
KW - IRON
KW - TEMPERATURE
KW - ferritic steels
KW - fracture toughness
KW - HSLA steel
KW - master curve
KW - nuclear reactor pressure vessel steel
KW - transition
KW - upper shelf
N1 - Accession Number: 21909953; ERICKSONKIRK, MARJORIE 1; Email Address: erickson.peai@verizon.net ERICKSONKIRK, MARK 2; Email Address: mtk@nrc.gov; Affiliation: 1: President, Phoenix Engineering Associates, Inc., Sykesville, MD 21784 USA 2: Senior Materials Engineer, United States Nuclear Regulatory Commission, Rockville, MD 20852 USA; Source Info: Sep2006, Vol. 29 Issue 9/10, p672; Subject Term: FERRITIC steel; Subject Term: DUCTILITY; Subject Term: STEEL; Subject Term: BRITTLENESS; Subject Term: IRON; Subject Term: TEMPERATURE; Author-Supplied Keyword: ferritic steels; Author-Supplied Keyword: fracture toughness; Author-Supplied Keyword: HSLA steel; Author-Supplied Keyword: master curve; Author-Supplied Keyword: nuclear reactor pressure vessel steel; Author-Supplied Keyword: transition; Author-Supplied Keyword: upper shelf; NAICS/Industry Codes: 331110 Iron and Steel Mills and Ferroalloy Manufacturing; NAICS/Industry Codes: 416210 Metal service centres; NAICS/Industry Codes: 331221 Rolled Steel Shape Manufacturing; Number of Pages: 13p; Illustrations: 3 Charts, 6 Graphs; Document Type: Article
L3 - 10.1111/j.1460-2695.2006.01026.x
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=21909953&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Lomperski, S.
AU - Farmer, M.T.
AU - Basu, S.
T1 - Experimental investigation of corium quenching at elevated pressure
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2006/10//
VL - 236
IS - 19-21
M3 - Article
SP - 2271
EP - 2280
SN - 00295493
AB - Abstract: This paper describes the results of experiments designed to quantify the cooling rate of corium by an overlying water pool. The experiments are intended to provide fundamental information on the ability of water to ingress into cracks and fissures that form in the debris during quench, thereby augmenting the otherwise conduction-limited heat transfer process. This information is being used to assess the effectiveness of a water pool in thermally stabilizing a molten-core/concrete interaction and cooling of ex-vessel core debris. The experiments involved corium inventories of 75kg with a melt depth of 15cm and diameter of 30cm. The corium was composed of UO2/ZrO2/concrete to simulate mixtures of molten reactor core components and either siliceous or limestone/common sand (LCS) concrete. Initial melt temperatures were of the order of 2100°C. The heat transfer rate from the corium was determined through measurements of the vapor production rate from the water pool. The melt was quenched at atmospheric pressure for the first two tests and at 4bar for the two subsequent tests. Preliminary data analysis indicates that the overall heat transfer rate exceeded the conduction-limited rate for the three melts containing 8wt.% concrete, but not for the fourth, which had 23wt.% concrete. Also, the quench rate of the 8wt.% concrete melts did not vary appreciably with pressure. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - HEAT transfer
KW - THERMAL diffusivity
KW - WATER cooled reactors
KW - ATMOSPHERIC pressure
N1 - Accession Number: 21831007; Lomperski, S. 1; Email Address: lomperski@anl.gov Farmer, M.T. 1; Email Address: farmer@anl.gov Basu, S. 2; Affiliation: 1: Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL, USA 2: U.S. Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD, USA; Source Info: Oct2006, Vol. 236 Issue 19-21, p2271; Subject Term: HEAT transfer; Subject Term: THERMAL diffusivity; Subject Term: WATER cooled reactors; Subject Term: ATMOSPHERIC pressure; Number of Pages: 10p; Document Type: Article
L3 - 10.1016/j.nucengdes.2006.03.041
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=21831007&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Paperiello, Carl J.
T1 - CURRENT STATUS OF U.S. NUCLEAR REGULATORY COMMISSION REGULATORY EFFORTS CONTROLLING THE DISPOSITION OF SOLID MATERIALS.
JO - Health Physics
JF - Health Physics
Y1 - 2006/11//
VL - 91
IS - 5
M3 - Article
SP - 523
EP - 525
SN - 00179078
AB - The article presents a discussion of the present status of United States Nuclear Regulatory Commission regulatory efforts controlling the disposition of solid materials. It states that recent efforts of the United States Nuclear Regulatory Commission to develop rules for the disposition of low-activity solid materials and the outcome of United States Nuclear Regulatory Commission rulemaking activities in this area since the late 1990's are described. It mentions that international efforts on the disposition of low-activity solid materials and future plans of the United States Nuclear Regulatory Commission on the subject are also described.
KW - Nuclear energy
KW - Power resources
KW - Radioactive wastes
KW - Radioactive substances
KW - Nuclear physics
KW - Government agencies
KW - Radiochemistry
KW - United States
KW - low-level
KW - National Council on Radiation
KW - Protection and Measurements
KW - radiation
KW - regulatory guides
KW - waste disposal
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 22827413; Paperiello, Carl J. 1; Email Address: drcjp1@aol.com; Affiliations: 1: Director, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC; Issue Info: Nov2006, Vol. 91 Issue 5, p523; Thesaurus Term: Nuclear energy; Thesaurus Term: Power resources; Thesaurus Term: Radioactive wastes; Thesaurus Term: Radioactive substances; Subject Term: Nuclear physics; Subject Term: Government agencies; Subject Term: Radiochemistry; Subject: United States; Author-Supplied Keyword: low-level; Author-Supplied Keyword: National Council on Radiation; Author-Supplied Keyword: Protection and Measurements; Author-Supplied Keyword: radiation; Author-Supplied Keyword: regulatory guides; Author-Supplied Keyword: waste disposal ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 911910 Other federal government public administration; NAICS/Industry Codes: 912910 Other provincial and territorial public administration; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; NAICS/Industry Codes: 921190 Other General Government Support; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562210 Waste treatment and disposal; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=22827413&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Kuran, S.
AU - Xu, Y.
AU - Sun, X.
AU - Cheng, L.
AU - Yoon, H.J.
AU - Revankar, S.T.
AU - Ishii, M.
AU - Wang, W.
T1 - Startup transient simulation for natural circulation boiling water reactors in PUMA facility
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2006/11//
VL - 236
IS - 22
M3 - Article
SP - 2365
EP - 2375
SN - 00295493
AB - Abstract: In view of the importance of instabilities that may occur at low-pressure and -flow conditions during the startup of natural circulation boiling water reactors, startup simulation experiments were performed in the Purdue University Multi-Dimensional Integral Test Assembly (PUMA) facility. The simulations used pressure scaling and followed the startup procedure of a typical natural circulation boiling water reactor. Two simulation experiments were performed for the reactor dome pressures ranging from 55 kPa to 1 MPa, where the instabilities may occur. The experimental results show the signature of condensation-induced oscillations during the single-phase-to-two-phase natural circulation transition. The results also suggest that a rational startup procedure is needed to overcome the startup instabilities in natural circulation boiling water reactor designs. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NUCLEAR reactors
KW - STEAM power plants
KW - PRESSURE
KW - NUCLEAR energy
N1 - Accession Number: 22396307; Kuran, S. 1 Xu, Y. 1 Sun, X. 1 Cheng, L. 1 Yoon, H.J. 1 Revankar, S.T. 1 Ishii, M. 1 Wang, W. 2; Email Address: ishii@ecn.purdue.edu; Affiliation: 1: School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA 2: U.S. Nuclear Regulatory Commission, Mail Stop T10K8, Washington, DC 20555, USA; Source Info: Nov2006, Vol. 236 Issue 22, p2365; Subject Term: NUCLEAR reactors; Subject Term: STEAM power plants; Subject Term: PRESSURE; Subject Term: NUCLEAR energy; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; NAICS/Industry Codes: 221330 Steam and Air-Conditioning Supply; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.nucengdes.2005.11.002
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=22396307&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Walker, J. Samuel
T1 - Proving Grounds: Project Plowshare and the Unrealized Dream of Nuclear Earthmoving.
JO - Journal of American History
JF - Journal of American History
Y1 - 2006/12//
VL - 93
IS - 3
M3 - Book Review
SP - 962
EP - 962
PB - Oxford University Press / USA
SN - 00218723
AB - A review of the book "Proving Grounds: Project Plowshare and the Unrealized Dream of Nuclear Earthmoving" by Scott Kirsch is presented.
KW - NUCLEAR energy -- Research
KW - HISTORY
KW - NONFICTION
KW - KIRSCH, Scott
KW - PROVING Grounds: Project Plowshare & the Unrealized Dream of Nuclear Earthmoving (Book)
N1 - Accession Number: 23507304; Walker, J. Samuel 1; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, D.C.; Source Info: Dec2006, Vol. 93 Issue 3, p962; Subject Term: NUCLEAR energy -- Research; Subject Term: HISTORY; Subject Term: NONFICTION; Reviews & Products: PROVING Grounds: Project Plowshare & the Unrealized Dream of Nuclear Earthmoving (Book); People: KIRSCH, Scott; Number of Pages: 3/4p; Document Type: Book Review
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Walker, J. Samuel
T1 - An "Atomic Garbage Dump" for Kansas.
JO - Kansas History
JF - Kansas History
Y1 - 2006///Winter2006
VL - 29
IS - 4
M3 - Article
SP - 266
EP - 285
SN - 01499114
AB - From 1970 to 1972, the Atomic Energy Commission (AEC) faced opposition from politicians in Kansas over an effort to identify the first permanent site for the disposal of radioactive waste. The AEC's proposal to create a storage facility near Lyons, Kansas, failed politically and technically as the dismissive tone taken from the outset by AEC officials toward scientists and politicians in Kansas led to disillusionment from early supporters and outright opposition from other key Kansans, and as the Lyons site eventually proved to be unsuitable for the burial of radioactive waste. These failures led to diminished public confidence in the AEC.
KW - RADIOACTIVE waste repositories
KW - SCIENTISTS
KW - POLITICIANS
KW - RADIOACTIVE wastes
KW - WORLD War, 1939-1945
KW - PUBLIC opinion
KW - KANSAS
KW - Kansas (Lyons)
KW - U.S. Atomic Energy Commission
N1 - Accession Number: 23780458; Walker, J. Samuel 1; Affiliations: 1 : Historian, U.S. Nuclear Regulatory Commission; Source Info: Winter2006, Vol. 29 Issue 4, p266; Note: Based on the records of the AEC, Washington, D.C., congressional records, correspondence, newspapers, other primary sources, and secondary sources; 9 photos, 2 reproductions, 42 notes.; Historical Period: 1970 to 1972; Subject Term: RADIOACTIVE waste repositories; Subject Term: SCIENTISTS; Subject Term: POLITICIANS; Subject Term: RADIOACTIVE wastes; Subject Term: WORLD War, 1939-1945; Subject Term: PUBLIC opinion; Subject: KANSAS; Number of Pages: 20p; Document Type: Article
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DP - EBSCOhost
DB - ahl
ER -
TY - JOUR
AU - Klein, Dale E.
T1 - Industry's Three Challenges.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2007/01//Jan/Feb2007
VL - 25
IS - 1
M3 - Article
SP - 45
EP - 48
PB - Presidents & Prime Ministers
SN - 08922055
AB - The article focuses on the nuclear industry's challenges presented by Dale Klein, chairman of the National Regulatory Commission in the U.S. According to Klein, the challenges include the industry's regulatory uncertainty, the manufacturing infrastructure and the need of human capital. He claims that he has been delighted of good expectations ahead for the nuclear industry.
KW - Infrastructure (Economics)
KW - Nuclear industry -- Law & legislation
KW - Labor supply
KW - United States
KW - U.S. Nuclear Regulatory Commission
KW - Klein, Dale
N1 - Accession Number: 24447163; Klein, Dale E. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: Jan/Feb2007, Vol. 25 Issue 1, p45; Thesaurus Term: Infrastructure (Economics); Subject Term: Nuclear industry -- Law & legislation; Subject Term: Labor supply; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 561320 Temporary Help Services; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; People: Klein, Dale; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - GEN
AU - Klein, Dale E.
T1 - Three Proposed COLs Expected in 2007.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2007/03//Mar/Apr2007
VL - 25
IS - 2
M3 - Interview
SP - 28
EP - 32
PB - Presidents & Prime Ministers
SN - 08922055
AB - An interview with Dr. Dale Klein, chairman of the U.S. Nuclear Regulatory Commission, is presented. When asked to provide an overview of the new plant activity in the U.S., he said there are nearly 16 entities that are interested in more than 30 reactors. He notes that the local community is very supportive of nuclear power plant. He asserts that the agency is moving up and is expected to hire about 600 people in 2007.
KW - Nuclear industry
KW - Independent regulatory commissions
KW - United States
KW - U.S. Nuclear Regulatory Commission
KW - Klein, Dale -- Interviews
N1 - Accession Number: 25027084; Klein, Dale E. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: Mar/Apr2007, Vol. 25 Issue 2, p28; Thesaurus Term: Nuclear industry; Subject Term: Independent regulatory commissions; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; People: Klein, Dale -- Interviews; Number of Pages: 4p; Document Type: Interview
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Shah, M. J.
AU - Klymyshyn, N. A.
AU - Adkins, H. E.
AU - Koeppel, B. J.
T1 - HI-STAR 100 spent fuel transport cask analytical evaluation for drop events.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2007/03//
VL - 18
IS - 1
M3 - Article
SP - 3
EP - 9
PB - Taylor & Francis Ltd
SN - 17465095
AB - The US Nuclear Regulatory Commission (NRC) is responsible for licensing commercial spent nuclear fuel transported in casks certified by NRC under the Code of Federal Regulations (CFR), Title 10, Part 71. Both the International Atomic Energy Agency (IAEA) regulations for transporting radioactive materials (Ref. 2, paragraph 727) and 10 CFR 71·73 require casks to be evaluated for hypothetical accident conditions, which includes a 9 m (30 feet) drop impact event on a flat, essentially unyielding, horizontal surface, in the most damaging orientation. The present paper examines the behaviour of one of the NRC certified transportation casks, the HI-STAR 100, for drop impact events. The specific area examined is the behaviour of the bolted connections in the 'overpack' top flange and the closure plate, which are significantly loaded during the hypothetical drop impact event. The term 'overpack' refers to the cask that receives and contains a sealed multipurpose canister (MPC) containing spent nuclear fuel. The analytical work to evaluate the NRC certified HI-STAR 100 spent fuel transport cask for a 9 m (30 feet) drop impact event on a flat, unyielding, horizontal surface, was performed using the ANSYS and LS-DYNA finite element analysis codes. The models were sufficiently detailed, in the areas of bolt closure interfaces and containment boundaries, to evaluate the structural integrity of the bolted connections under 9 m (30 feet) free drop hypothetical accident conditions, as specified in 10 CFR 71·73. Evaluation of the cask for puncture, caused by a free drop through a distance of 1 m (40 inch) onto a mild steel bar mounted on a flat, essentially unyielding, horizontal surface, required by 10 CFR 71·73, was not included in the current work. Based on the analyses performed to date, it is concluded that, even though brief separation of the flange and the closure plate surfaces may occur, the seals would close at the end of the drop events, because the materials remain elastic during the duration of the event. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear fuels
KW - Federal regulation
KW - Radioactive substances
KW - Radioactive substance transport
KW - Analytical
KW - Drop events
KW - HI-STAR 100
KW - SPENT FUEL
KW - Transport cask
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 25765460; Shah, M. J. 1; Email Address: mjs3@nrc.gov; Klymyshyn, N. A. 2; Adkins, H. E. 2; Koeppel, B. J. 2; Affiliations: 1: United States Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD 20852, USA; 2: Pacific Northwest National Laboratory, 902 Battelle Boulevard, Richland, WA 99352, USA; Issue Info: 2007, Vol. 18 Issue 1, p3; Thesaurus Term: Nuclear fuels; Thesaurus Term: Federal regulation; Thesaurus Term: Radioactive substances; Subject Term: Radioactive substance transport; Author-Supplied Keyword: Analytical; Author-Supplied Keyword: Drop events; Author-Supplied Keyword: HI-STAR 100; Author-Supplied Keyword: SPENT FUEL; Author-Supplied Keyword: Transport cask ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 484230 Specialized Freight (except Used Goods) Trucking, Long-Distance; Number of Pages: 7p; Illustrations: 3 Diagrams, 2 Charts, 2 Graphs; Document Type: Article
L3 - 10.1179/174651007X191134
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=25765460&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Shah, M. J.
AU - Klymyshyn, N. A.
AU - Adkins, H. E.
AU - Koeppel, B. J.
T1 - TN-68 spent fuel transport cask analytical evaluation for drop events.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2007/03//
VL - 18
IS - 1
M3 - Article
SP - 11
EP - 18
PB - Taylor & Francis Ltd
SN - 17465095
AB - The US Nuclear Regulatory Commission (NRC) is responsible for licensing commercial spent nuclear fuel transported in casks certified by NRC under the Code of Federal Regulations (10 CFR), Title 10, Part 71. Both the International Atomic Energy Agency regulations for transporting radioactive materials, and 10 CFR 71·73 require casks to be evaluated for hypothetical accident conditions, which includes a 9 m (30 ft) drop impact event onto a flat, essentially unyielding, horizontal surface, in the most damaging orientation. This paper examines the behaviour of one of the NRC certified transportation casks, the TN-68, for drop impact events. The specific area examined is the behaviour of the bolted connections in the cask body and the closure lid, which are significantly loaded during the hypothetical drop impact event. Analytical work to evaluate the NRC certified TN-68 spent fuel transport cask for a 9 m (30 ft) drop impact event on a flat, unyielding, horizontal surface, was performed using the ANSYS and LS-DYNA finite element analysis codes. The models were sufficiently detailed, in the areas of bolt closure interfaces and containment boundaries, to evaluate the structural integrity of the bolted connections under 9 m (30 ft) free drop hypothetical accident conditions, as specified in 10 CFR 71·73. Evaluation of the cask for puncture, caused by a free drop through a distance of 1 m (40 in) onto a mild steel bar mounted on a flat, essentially unyielding, horizontal surface, required by 10 CFR 71·73, was not included in the current work. Based on the analyses performed to date, it is concluded that, even though brief separation of the flange and the lid surfaces may occur under some conditions, the seals would close at the end of the drop events, because the materials remain elastic during the duration of the event. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear fuels
KW - Federal regulation
KW - Radioactive substances
KW - Radioactive substance transport
KW - ANALYTICAL
KW - DROP EVENTS
KW - SPENT FUEL
KW - TN-68
KW - TRANSPORT CASK
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 25765459; Shah, M. J. 1,2; Email Address: mjs3@nrc.gov; Klymyshyn, N. A. 1,2; Adkins, H. E. 1,2; Koeppel, B. J. 1,2; Affiliations: 1: United States Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD, 20852, USA; 2: Pacific Northwest National Laboratory, 902 Battelle Boulevard, Richland, WA, 99352, USA; Issue Info: 2007, Vol. 18 Issue 1, p11; Thesaurus Term: Nuclear fuels; Thesaurus Term: Federal regulation; Thesaurus Term: Radioactive substances; Subject Term: Radioactive substance transport; Author-Supplied Keyword: ANALYTICAL; Author-Supplied Keyword: DROP EVENTS; Author-Supplied Keyword: SPENT FUEL; Author-Supplied Keyword: TN-68; Author-Supplied Keyword: TRANSPORT CASK ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 484230 Specialized Freight (except Used Goods) Trucking, Long-Distance; Number of Pages: 8p; Illustrations: 9 Diagrams, 2 Charts; Document Type: Article
L3 - 10.1179/174651007X191125
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Tregoning, Robert Lee
AU - Abramson, Lee Richard
AU - Scott, Paul Michael
AU - Chokshi, Nilesh
T1 - LOCA frequency evaluation using expert elicitation
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2007/07//
VL - 237
IS - 12/13
M3 - Article
SP - 1429
EP - 1436
SN - 00295493
AB - Abstract: The double-ended-guillotine break (DEGB) criterion of the largest primary piping system in the plant, which generally provides the limiting condition for the emergency core cooling system requirements, is widely recognized as an extremely unlikely event. As a result, US Nuclear Regulatory Commission (NRC) staff are currently considering a risk-informed revision of the design-basis break size requirements for commercial nuclear power plants. In support of this effort, loss-of-coolant accident (LOCA) frequency estimates have been developed using an expert elicitation process by consolidating service history data and insights from probabilistic fracture mechanics (PFM) studies with knowledge of plant design, operation, and material performance. Baseline LOCA frequency estimates for the 5th percentile, median, mean and 95th percentile were determined from each panelist''s elicitation responses. Group estimates were determined by aggregating the individual estimates using the geometric mean of the individual estimates for each frequency parameter. Group variability was estimated by calculating 95% confidence bounds for each of the group frequency parameters (i.e., median, mean, and 5th and 95th percentiles). A number of sensitivity analyses were conducted to examine the effects on the quantitative results from varying the assumptions, structure and techniques of the baseline analysis procedure. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NUCLEAR power plants -- Design & construction
KW - POWER resources
KW - FRACTURE mechanics
KW - STRENGTH of materials
N1 - Accession Number: 25322309; Tregoning, Robert Lee 1; Email Address: rtl@nrc.gov Abramson, Lee Richard 1; Email Address: lxa@nrc.gov Scott, Paul Michael 2; Email Address: scottp@battelle.org Chokshi, Nilesh 1; Email Address: ncc1@nrc.gov; Affiliation: 1: United States Nuclear Regulatory Commission, Washington, DC 20555, USA 2: Battelle Memorial Institute, 505 King Avenue, Columbus, OH 43201, USA; Source Info: Jul2007, Vol. 237 Issue 12/13, p1429; Subject Term: NUCLEAR power plants -- Design & construction; Subject Term: POWER resources; Subject Term: FRACTURE mechanics; Subject Term: STRENGTH of materials; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 8p; Document Type: Article
L3 - 10.1016/j.nucengdes.2006.09.036
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=25322309&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Coleman, Neil M.
AU - Dinwiddie, Cynthia L.
AU - Casteel, Kay
T1 - High outflow channels on Mars indicate Hesperian recharge at low latitudes and the presence of Canyon Lakes
JO - ICARUS
JF - ICARUS
Y1 - 2007/08//
VL - 189
IS - 2
M3 - Article
SP - 344
EP - 361
SN - 00191035
AB - Abstract: A number of martian outflow channels were carved by discharges from large dilational fault zones. These channels were sourced by groundwater, not surface water, and when observed on high-standing plateaus they provide indicators of elevated paleo-groundwater levels. We identify three outflow channels of Hesperian age that issued from a 750-km-long fault zone extending from Candor Chasma to Ganges Chasma. Two of these channels, Allegheny Vallis and Walla Walla Vallis, have sources >2500 m above the topographic datum, too high to be explained by discharge from a global aquifer that was recharged solely in the south polar region. The indicated groundwater levels likely required regional sources of recharge at low latitudes. The floodwaters that erupted from Ophir Cavus to form Allegheny Vallis encountered two ridges that restricted the flow, forming temporary lakes. The flow probably breached or overtopped these obstructions quickly, catastrophically draining the lakes and carving several scablands. After the last obstacle had been breached, a single main channel formed that captured all subsequent flow. We performed hydrologic analyses of this intermediate phase of the flooding, prior to incision of the channel to its present depth. Using floodwater depths of 30–60 m, we calculated flow velocities of 6–15 m s−1 and discharges in the range of . Locally higher flow velocities and discharges likely occurred when the transient lakes were drained. Variable erosion at the channel and scabland crossing of MOLA pass 10644 suggests that the upper 25–30 m may consist of poorly consolidated surface materials underlain by more cohesive bedrock. We infer that an ice-covered lake with a surface elevation >2500 m probably existed in eastern Candor Chasma because this canyon is intersected by the Ophir Catenae fault system from which Allegheny Vallis and Walla Walla Vallis originated. We introduce a new hydrology concept for Mars in which the groundwater system was augmented by recharge from canyon lakes that were formed when water was released by catastrophic melting of former ice sheets in Tharsis by effusions of flood basalts. This model could help to reconcile the expected presence of a thick cryosphere during the Hesperian with the abundant evidence for groundwater as a source for some of the circum-Chryse outflow channels. [Copyright &y& Elsevier]
AB - Copyright of ICARUS is the property of Academic Press Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - MARS (Planet)
KW - FAULTS (Geology)
KW - GROUNDWATER
KW - VOLCANISM
KW - SURFACE
KW - Geological processes
KW - Mars
KW - surface ( Mars )
KW - Volcanism
N1 - Accession Number: 25746006; Coleman, Neil M. 1; Email Address: nmcoleman@comcast.net Dinwiddie, Cynthia L. 2 Casteel, Kay 3; Affiliation: 1: US Nuclear Regulatory Commission, Mail Stop T2E26, Washington, DC 20555, USA 2: Department of Earth, Material, and Planetary Sciences, Southwest Research Institute®, 6220 Culebra Road, San Antonio, TX 78238-5166, USA 3: Mercersburg, PA 17236, USA; Source Info: Aug2007, Vol. 189 Issue 2, p344; Subject Term: MARS (Planet); Subject Term: FAULTS (Geology); Subject Term: GROUNDWATER; Subject Term: VOLCANISM; Subject Term: SURFACE; Author-Supplied Keyword: Geological processes; Author-Supplied Keyword: Mars; Author-Supplied Keyword: surface ( Mars ); Author-Supplied Keyword: Volcanism; Number of Pages: 18p; Document Type: Article
L3 - 10.1016/j.icarus.2007.01.020
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=25746006&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Easton, E. P.
AU - Bajwa, C. S.
T1 - Effects of tunnel fires on behaviour of spent nuclear fuel casks.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2007/09//
VL - 18
IS - 3
M3 - Article
SP - 131
EP - 141
PB - Taylor & Francis Ltd
SN - 17465095
AB - As part of the Nuclear Regulatory Commission's (NRC) overall review of the performance of transportation casks under severe accident conditions, the NRC has undertaken a number of initiatives, including an examination of the Baltimore rail tunnel fire in 2001, and the Caldecott road tunnel fire in Oakland, California, in 1982. The NRC, working with the National Transportation Safety Board (NTSB), the National Institute of Standards and Technology (NIST), and Pacific Northwest National Laboratory (PNNL), performed analyses to evaluate the potential for a release of radioactive material from the transportation casks analysed for the Baltimore and Caldecott tunnel fire scenarios. Full details on this work have been published in NUREG/CR-6886, Rev. 1, 'Spent fuel transportation package response to the Baltimore Tunnel Fire Scenario' and NUREG/CR-6894, Rev. 1, 'Spent fuel transportation package response to the Caldecott Tunnel Fire Scenario'. This paper contains a summary of the results of these analyses. Most significantly, the staff found that for both tunnel fire events, a release of radioactive material from any of the casks analysed is unlikely, and that any potential release would be very small – less than an A2 for radionuclides of greatest concern. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radioisotopes
KW - Transportation -- Safety measures
KW - Independent regulatory commissions
KW - United States
KW - Accident
KW - Fire
KW - SPENT NUCLEAR FUEL
KW - TRANSPORTATION
KW - TUNNEL
KW - U.S. Nuclear Regulatory Commission
KW - United States. National Transportation Safety Board
N1 - Accession Number: 27530171; Easton, E. P. 1; Bajwa, C. S. 1; Email Address: csb1@nrc.gov; Affiliations: 1: US Nuclear Regulatory Commission, 301-492-3307, USA; Issue Info: 2007, Vol. 18 Issue 3, p131; Thesaurus Term: Radioisotopes; Subject Term: Transportation -- Safety measures; Subject Term: Independent regulatory commissions; Subject: United States; Author-Supplied Keyword: Accident; Author-Supplied Keyword: Fire; Author-Supplied Keyword: SPENT NUCLEAR FUEL; Author-Supplied Keyword: TRANSPORTATION; Author-Supplied Keyword: TUNNEL ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: United States. National Transportation Safety Board; NAICS/Industry Codes: 926120 Regulation and Administration of Transportation Programs; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 488999 All Other Support Activities for Transportation; NAICS/Industry Codes: 488990 Other support activities for transportation; Number of Pages: 11p; Illustrations: 4 Color Photographs, 1 Black and White Photograph, 5 Diagrams, 10 Charts, 5 Graphs; Document Type: Article
L3 - 10.1179/174651007X220230
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - He, X.
AU - Dunn, D.S.
AU - Csontos, A.A.
T1 - Corrosion of similar and dissimilar metal crevices in the engineered barrier system of a potential nuclear waste repository
JO - Electrochimica Acta
JF - Electrochimica Acta
Y1 - 2007/10/10/
VL - 52
IS - 27
M3 - Article
SP - 7556
EP - 7569
SN - 00134686
AB - Abstract: Crevice corrosion is considered possible if the corrosion potential (E corr) exceeds the repassivation potential for crevice corrosion (E rcrev). In this study, potentiodynamic polarization and potentiostatic hold were used to determine the E rcrev of similar and dissimilar metal crevices in the engineered barrier system of the potential Yucca Mountain repository in 0.5M NaCl, 4M NaCl, and 4M MgCl2 solutions at 95°C. The results were compared with data previously obtained using crevices formed between Alloy 22 and polytetrafluoroethylene. It was observed that, except for Type 316L stainless steel, all other metal-to-metal crevices were less susceptible to crevice corrosion than the corresponding metal-to-polytetrafluoroethylene crevices. Measurements of galvanic coupling were used to evaluate the crevice corrosion propagation behavior in 5M NaCl solution at 95°C. The crevice specimens were coupled to either an Alloy 22 or a Titanium Grade 7 plate using metal or polytetrafluoroethylene crevice washers. Crevice corrosion of Type 316L stainless steel propagated without repassivation. For all the tests using a polytetrafluoroethylene crevice washer, crevice corrosion of Alloy 22 was initiated at open circuit potential by the addition of CuCl2 as an oxidant, whereas no crevice corrosion of Alloy 22 was initiated for all the tests using Alloy 22 or Titanium Grade 7 metals as crevice washer. However, crevice corrosion propagation was found to be very limited under such test conditions. [Copyright &y& Elsevier]
AB - Copyright of Electrochimica Acta is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - STEEL -- Corrosion
KW - RADIOACTIVE wastes
KW - STEEL alloys
KW - CORROSION resistant alloys
KW - 316L stainless steel
KW - Alloy 22
KW - Crevice corrosion
KW - Crevice corrosion repassivation potential
KW - Titanium Grade 7
N1 - Accession Number: 26249717; He, X. 1,2; Email Address: xhe@swri.org Dunn, D.S. 2 Csontos, A.A. 3; Affiliation: 1: Center for Nuclear Waste Regulatory Analyses, San Antonio, TX, USA 2: Southwest Research Institute®, San Antonio, TX, USA 3: U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC, USA; Source Info: Oct2007, Vol. 52 Issue 27, p7556; Subject Term: STEEL -- Corrosion; Subject Term: RADIOACTIVE wastes; Subject Term: STEEL alloys; Subject Term: CORROSION resistant alloys; Author-Supplied Keyword: 316L stainless steel; Author-Supplied Keyword: Alloy 22; Author-Supplied Keyword: Crevice corrosion; Author-Supplied Keyword: Crevice corrosion repassivation potential; Author-Supplied Keyword: Titanium Grade 7; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562210 Waste treatment and disposal; Number of Pages: 14p; Document Type: Article
L3 - 10.1016/j.electacta.2006.12.077
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Kim, Seungjin
AU - Park, Jung Han
AU - Kojasoy, Gunol
AU - Kelly, Joseph M.
AU - Marshall, Shawn O.
T1 - Geometric effects of 90-degree Elbow in the development of interfacial structures in horizontal bubbly flow
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2007/11//
VL - 237
IS - 20/21
M3 - Article
SP - 2105
EP - 2113
SN - 00295493
AB - Abstract: Present study investigates the geometric effects of flow obstruction on the distribution of local two-phase flow parameters and their transport characteristics in horizontal bubbly flow. The round glass tubes of 50.3mm in inner diameter are employed as test sections, along which a 90-degree Elbow is located at L/D =206.6 from the two-phase mixture inlet. In total, 15 different flow conditions are examined within the air–water bubbly flow regime. The detailed local two-phase flow parameters are acquired by the double-sensor conductivity probe at four different axial locations. The effect of elbow is found to be evident in both the distribution of local parameters and their development. The elbow clearly promotes bubble interactions resulting in significant changes in interfacial area concentration. It is also found that the elbow-effect propagates to be more significant further downstream (L/D =250) than immediate downstream (L/D =225) of the elbow. Furthermore, it is shown that the elbow induces significant oscillations in the flow in both vertical and horizontal directions of the tube cross-section. Characteristic geometric effects due to the existence of elbow are also shown clearly in the transport of one-dimensional interfacial area concentration and void fraction along the flow. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - FLUID dynamics
KW - MULTIPHASE flow
KW - FLUCTUATIONS (Physics)
KW - STOCHASTIC processes
N1 - Accession Number: 26844782; Kim, Seungjin 1; Email Address: kimsj@umr.edu Park, Jung Han 2 Kojasoy, Gunol 2 Kelly, Joseph M. 3 Marshall, Shawn O. 3; Affiliation: 1: Nuclear Engineering, 1870 Miner Circle, University of Missouri-Rolla, Rolla, MO 65401, United States 2: Department of Mechanical Engineering, University of Wisconsin-Milwaukee, Milwaukee, WI 53201, United States 3: US Nuclear Regulatory Commission, Mail Stop T10 K08, 11545 Rockville Pike, Washington, DC 20555, United States; Source Info: Nov2007, Vol. 237 Issue 20/21, p2105; Subject Term: FLUID dynamics; Subject Term: MULTIPHASE flow; Subject Term: FLUCTUATIONS (Physics); Subject Term: STOCHASTIC processes; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.nucengdes.2007.02.007
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Chen, Dong
AU - Howe, Kerry J.
AU - Dallman, Jack
AU - Letellier, Bruce C.
AU - Klasky, Marc
AU - Leavitt, Janet
AU - Jain, Bhagwat
T1 - Experimental analysis of the aqueous chemical environment following a loss-of-coolant accident
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2007/11//
VL - 237
IS - 20/21
M3 - Article
SP - 2126
EP - 2136
SN - 00295493
AB - Abstract: Five different 30-day tests were conducted to simulate the chemical environment in a pressurized water reactor containment water pool after a loss-of-coolant accident (LOCA). All chemical environments within the test apparatus included boric acid, lithium hydroxide, and hydrochloric acid. In addition, trisodium phosphate, sodium hydroxide, and sodium tetraborate were used to control pH in separate tests. Materials tested within this environment included representative amounts of submerged and unsubmerged metal coupons, concrete, insulation debris samples, concrete particulate, and latent debris. Visible changes were seen on the both submerged and unsubmerged metal coupons in each test because of corrosion. The tests with calcium silicate (cal-sil) insulation had considerably more sediment than the other tests with fiberglass insulation. Particulate deposits were found only on the exterior surfaces of the fiberglass bundles. The most particulate deposits were found on the fiberglass exterior from the test that involved cal-sil insulation and trisodium phosphate (TSP). In addition, snow-like white precipitates were found on top of the sediment in that test, that were rich in calcium and phosphorus. Precipitates were also present in the solutions of two tests when the solution was cooled to room temperature. These precipitates have high contents of aluminum and boron with small amounts of sodium and calcium. The presence of insulation debris, precipitates, and sediments is significant because of the impact they may have on the ECCS recirculation process. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - MATERIALS -- Testing
KW - NUCLEAR reactors
KW - PRESSURIZED water reactors
KW - CALCIUM silicates
N1 - Accession Number: 26844785; Chen, Dong 1 Howe, Kerry J. 1; Email Address: howe@unm.edu Dallman, Jack 2 Letellier, Bruce C. 2 Klasky, Marc 2 Leavitt, Janet 2 Jain, Bhagwat 3; Affiliation: 1: Department of Civil Engineering, The University of New Mexico, Albuquerque, NM 87131, United States 2: Los Alamos National Laboratory, Nuclear Design and Risk Analysis Group (D-5), Los Alamos, NM 87545, United States 3: The United States Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD 20852, United States; Source Info: Nov2007, Vol. 237 Issue 20/21, p2126; Subject Term: MATERIALS -- Testing; Subject Term: NUCLEAR reactors; Subject Term: PRESSURIZED water reactors; Subject Term: CALCIUM silicates; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.nucengdes.2007.02.010
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Cygan, Randall T.
AU - Stevens, Caroline T.
AU - Puls, Robert W.
AU - Yabusaki, Steven B.
AU - Wauchope, Robert D.
AU - McGrath, Christian J.
AU - Curtis, Gary P.
AU - Siegel, Malcolm D.
AU - Veblen, Linda A.
AU - Turner, David R.
T1 - Research Activities at U.S. Government Agencies in Subsurface Reactive Transport Modeling.
JO - Vadose Zone Journal
JF - Vadose Zone Journal
Y1 - 2007/12//
VL - 6
IS - 4
M3 - Article
SP - 2
EP - 2
AB - The fate of contaminants in the environment is controlled by both chemical reactions and transport phenomena in the subsurface. Our ability to understand the significance of these processes over time requires an accurate conceptual model that incorporates the various mechanisms of coupled chemical and physical processes. Adsorption, desorption, ion exchange, precipitation, dissolution, growth, solid solution, redox, microbial activity, and other processes are often incorporated into reactive transport models for the prediction of contaminant fate and transport. U.S. federal agencies use such models to evaluate contaminant transport and provide guidance to decision makers and regulators for treatment issues. We provide summaries of selected research projects and programs to demonstrate the level of activity in various applications and to present examples of recent advances in subsurface reactive transport modeling. [ABSTRACT FROM AUTHOR]
AB - Copyright of Vadose Zone Journal is the property of American Society of Agronomy and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Pollutants
KW - Adsorption
KW - Chemical reactions
KW - Ion exchange (Chemistry)
KW - Precipitation (Chemistry)
KW - United States
N1 - Accession Number: 27887498; Cygan, Randall T. 1; Email Address: rtcygan@sandia.gov; Stevens, Caroline T. 2; Puls, Robert W. 3; Yabusaki, Steven B. 4; Wauchope, Robert D. 5; McGrath, Christian J. 6; Curtis, Gary P. 7; Siegel, Malcolm D. 1; Veblen, Linda A. 8; Turner, David R. 9; Affiliations: 1: Sandia National Lab., Albuquerque, NM 87185-0754; 2: U.S. Environmental Protection Agency, Athens, GA 30605; 3: U.S. Environmental Protection Agency, Ada, OK 74820; 4: Pacific Northwest National Lab., Richland, WA 99352; 5: U.S. Department of Agriculture, Tifton, GA 31793; 6: U.S. Army Engineer Research and Development Center, Vicksburg, MS 39180-6199; 7: U.S. Geological Survey, Menlo Park, CA 94025; 8: U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; 9: Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, TX 78228-0510; Issue Info: Dec2007, Vol. 6 Issue 4, p2; Thesaurus Term: Pollutants; Thesaurus Term: Adsorption; Subject Term: Chemical reactions; Subject Term: Ion exchange (Chemistry); Subject Term: Precipitation (Chemistry); Subject: United States; Number of Pages: 1p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Munyon, W. J.
AU - Reilly, D. W.
AU - Webb, J.
T1 - AGHCF GASEOUS-EFFLUENT TRITIUM SAMPLING SYSTEM: DESIGN CONSIDERATIONS AND PERFORMANCE TESTING RESULTS.
JO - Health Physics
JF - Health Physics
Y1 - 2008/01//
VL - 94
IS - 1
M3 - Article
SP - 75
EP - 85
SN - 00179078
AB - Performance testing results involving the operation of a gaseous-effluent tritium sampling system are presented. The sampling technique is based on using ethylene glycol bubblers for collecting tritiated entrained as vapor for a nitrogen purge gas from a hot cell facility. For a single bubbler, the tritium collection efficiency was determined to be 98.3 percent. For purposes of comparison the performance of water-filled bubblers was evaluated. Then two such bubblers were placed in series, their performance was a still satisfactory 95 percent, although some water loss was visible.
KW - RESEARCH
KW - Hydrogen isotopes
KW - Tritium
KW - Isotopes -- Equipment & supplies
KW - Radioisotopes -- Safety measures
KW - Nuclear engineering -- Instruments
KW - air sampling
KW - effluents
KW - operational topics
KW - tritium
N1 - Accession Number: 28025554; Munyon, W. J. 1; Email Address: wjmunyon@anl.gov; Reilly, D. W. 1; Webb, J. 2; Affiliations: 1: Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439; 2: U.S. Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD 20852; Issue Info: Jan2008, Vol. 94 Issue 1, p75; Thesaurus Term: RESEARCH; Subject Term: Hydrogen isotopes; Subject Term: Tritium; Subject Term: Isotopes -- Equipment & supplies; Subject Term: Radioisotopes -- Safety measures; Subject Term: Nuclear engineering -- Instruments; Author-Supplied Keyword: air sampling; Author-Supplied Keyword: effluents; Author-Supplied Keyword: operational topics; Author-Supplied Keyword: tritium; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; Number of Pages: 11p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - CHAP
ID - 2008-05673-009
AN - 2008-05673-009
AU - Burbach, Rodney
ED - Simon, Robert I.
ED - Tardiff, Kenneth
ED - Simon, Robert I., (Ed)
ED - Tardiff, Kenneth, (Ed)
T1 - Substance abuse disorders.
T2 - Textbook of violence assessment and management.
Y1 - 2008///
SP - 141
EP - 160
CY - Arlington, VA, US
PB - American Psychiatric Publishing, Inc.
SN - 978-1-58562-314-3
N1 - Accession Number: 2008-05673-009. Partial author list: First Author & Affiliation: Burbach, Rodney; U.S. Nuclear Regulatory Commission, Washington, DC, US. Release Date: 20080602. Correction Date: 20151207. Publication Type: Book (0200), Edited Book (0280). Format Covered: Print. Document Type: Chapter. Book Type: Textbook/Study Guide. ISBN: 978-1-58562-314-3, Hardcover. Language: English. Major Descriptor: Drug Abuse; Drug Addiction; Measurement; Treatment; Violence. Minor Descriptor: Alcohol Abuse; Drug Therapy; Psychotherapy; Volunteers. Classification: Substance Abuse & Addiction (3233); Health & Mental Health Treatment & Prevention (3300). Population: Human (10). Intended Audience: Psychology: Professional & Research (PS). References Available: Y. Page Count: 20.
AB - Alcohol and other drugs of addiction, interacting with personality and circumstances, often increase the likelihood of violence. Alcohol is the most widely used of addictive chemicals, and it is the chemical most likely to induce aggression; therefore it has the largest role in violence. Patients often do not volunteer information about their drinking or drug use. Every patient should be asked at least the single screening question: How often in the past year have you had five or more drinks in a day? (four or more drinks for a woman). Even a single such day is reason for further evaluation. Addictions treatment is effective. It should be tailored to each patient, using supportive therapies (12-Step meetings, individual therapy), counseling and cognitive-behavioral therapies, and pharmacotherapy. (PsycINFO Database Record (c) 2016 APA, all rights reserved)
KW - substance abuse
KW - alcohol abuse
KW - addiction
KW - violence
KW - patient violence
KW - treatment
KW - psychotherapies
KW - drug therapy
KW - measurement
KW - violence assessment
KW - 2008
KW - Drug Abuse
KW - Drug Addiction
KW - Measurement
KW - Treatment
KW - Violence
KW - Alcohol Abuse
KW - Drug Therapy
KW - Psychotherapy
KW - Volunteers
KW - 2008
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DP - EBSCOhost
DB - psyh
ER -
TY - GEN
AU - Fuhrmann, Mark
AU - Schwartzman, Adam L.
T1 - CORRECTED Kd VALUES FOR SELENIUM.
JO - Health Physics
JF - Health Physics
Y1 - 2008/02//
VL - 94
IS - 2
M3 - Letter
SP - 192
EP - 192
SN - 00179078
AB - A letter to the editor is presented in response to the article “Default soil solid/liquid partition coefficients, Kds, for four major soil types: a compendium,” by M. Sheppard and D.H. Thibault in the volume 59, 1990 issue of Health Physics.
KW - Letters to the editor
KW - Partition coefficient (Chemistry)
N1 - Accession Number: 28452816; Fuhrmann, Mark 1; Schwartzman, Adam L. 1; Affiliations: 1: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Rockville, MD 20850; Issue Info: Feb2008, Vol. 94 Issue 2, p192; Subject Term: Letters to the editor; Subject Term: Partition coefficient (Chemistry); Number of Pages: 2/3p; Document Type: Letter
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Ammerman, D.
AU - Kalan, B.
AU - Cook, J. R.
AU - Murphy, A.
T1 - Recent assessments in USA of Type B packages to impacts beyond regulatory package test standards.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2008/03//
VL - 19
IS - 1
M3 - Article
SP - 3
EP - 9
PB - Taylor & Francis Ltd
SN - 17465095
AB - The regulatory driven design of radioactive material transportation packages leads packaging vendors to perform analyses that demonstrate the package's ability to meet the regulatory requirements. However, for risk assessment and communication, the response of packages to impacts that are more severe than the regulatory impact is required. Traditionally, in the USA, the task of performing assessments of package response to impacts more severe than the regulatory ones has been performed by the US Department of Energy (DOE) national laboratories. These assessments have been both experimental and analytical. This paper provides a brief history of extraregulatory package impacts and then focuses on recent analyses performed by Sandia National Laboratories for the US Nuclear Regulatory Commission (NRC) and the US DOE. The analyses have been primarily in support of two large studies: 'Re-examination of spent fuel shipment risk estimates' and 'Package performance study'. The first of these examined the response of four generic spent fuel casks to impacts onto rigid targets at speeds up to 536 m s–1 (120 mph). The second examined the response of two certified spent fuel cask designs to impacts up to 335 m s–1 (75 mph). Analyses have been performed for closure end impacts, closure end CG over corner impacts and side-on impacts. The analyses and testing of packages to beyond regulatory impact standards have shown that the packages have a considerable margin of safety against release of radioactive material. This fact reinforces the adequacy of the packaging requirements of the US NRC and International Atomic Energy Agency (IAEA) and the methods currently used to certify that spent fuel casks meet these requirements. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radioactive substance transport
KW - Hazardous substances -- Packaging
KW - Testing
KW - United States
KW - EXTRAREGULATORY IMPACTS
KW - Finite element analysis
KW - Impact analysis
KW - Risk assessment
KW - United States. Dept. of Energy
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 32175394; Ammerman, D. 1; Email Address: djammer@sandia.gov; Kalan, B. 1; Cook, J. R. 2; Murphy, A. 2; Affiliations: 1: Sandia National Laboratories{, Albuquerque, NM, USA.; 2: US Nuclear Regulatory Commission, Washington, DC, USA.; Issue Info: 2008, Vol. 19 Issue 1, p3; Subject Term: Radioactive substance transport; Subject Term: Hazardous substances -- Packaging; Subject Term: Testing; Subject: United States; Author-Supplied Keyword: EXTRAREGULATORY IMPACTS; Author-Supplied Keyword: Finite element analysis; Author-Supplied Keyword: Impact analysis; Author-Supplied Keyword: Risk assessment ; Company/Entity: United States. Dept. of Energy ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 484230 Specialized Freight (except Used Goods) Trucking, Long-Distance; NAICS/Industry Codes: 926110 Administration of General Economic Programs; Number of Pages: 7p; Illustrations: 2 Color Photographs, 10 Diagrams, 2 Charts; Document Type: Article
L3 - 10.1179/174651008X278975
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Guber, A.K.
AU - Gish, T.J.
AU - Pachepsky, Y.A.
AU - van Genuchten, M.T.
AU - Daughtry, C.S.T.
AU - Nicholson, T.J.
AU - Cady, R.E.
T1 - Temporal stability in soil water content patterns across agricultural fields
JO - CATENA
JF - CATENA
Y1 - 2008/03/15/
VL - 73
IS - 1
M3 - Article
SP - 125
EP - 133
SN - 03418162
AB - Abstract: When a field or a small watershed is repeatedly surveyed for soil water content, locations can often be identified where soil water contents are either consistently larger or consistently less than the study area average. This phenomenon has been called temporal stability, time stability, temporal persistence, or rank stability in spatial patterns of soil water contents. Temporal stability is of considerable interest in terms of facilitating upscaling of observed soil water contents to obtain average values across the observation area, improving soil water monitoring strategies, and correcting the monitoring results for missing data. The objective of this work was to contribute to the existing knowledge base on temporal stability in soil water patterns using frequent multi-depth measurements with Multisensor Capacitance Probes (MCPs) installed in a coarse-texture soil under multi-year corn production. Water contents at 10, 30, 50, and 80 cm depths were measured every 10 min for 20 months of continuous observation from May 2001 to December 2002. The MCPs revealed temporal stability in soil water content patterns. Temporal stability was found to increase with depth. The statistical hypothesis could not be rejected (P <0.0001) that data collected each 10 min, each 2 h, each day, and each week had the same temporal stability. The locations that were best for estimating the average water contents were different for different depths. The best three locations for the whole observation period were the same as the best locations for a month of observations in about 60% of the cases. Temporal stability for a specific location and depth could serve as a good predictor of the utility of this location for estimating the area-average soil water content for that depth. Temporal stability could be efficiently used to correct area-average water contents for missing data. Soil water contents can be upscaled and efficiently monitored using the temporal stability of soil water content patterns. [Copyright &y& Elsevier]
AB - Copyright of CATENA is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Watersheds
KW - Mountain watersheds
KW - Landscapes
KW - Landforms
KW - Measurement frequency
KW - Multisensor capacitance probe
KW - Soil water content
KW - Spatial pattern
KW - Temporal stability
KW - Upscaling
N1 - Accession Number: 30860552; Guber, A.K. 1,2; Gish, T.J. 2; Pachepsky, Y.A. 3; Email Address: ypachepsky@anri.barc.usda.gov; van Genuchten, M.T. 4; Daughtry, C.S.T. 2; Nicholson, T.J. 5; Cady, R.E. 5; Affiliations: 1: Department of Environmental Sciences, University of California, Riverside, United States; 2: Hydrology and Remote Sensing Laboratory, USDA, ARS, Beltsville, MD, United States; 3: Environmental Microbial Safety Laboratory, USDA, ARS, Beltsville, MD, United States; 4: U.S. Salinity Laboratory, USDA, ARS, Riverside, CA, United States; 5: U.S. Nuclear Regulatory Commission, US NRC-ORR, Rockville, MD, United States; Issue Info: Mar2008, Vol. 73 Issue 1, p125; Thesaurus Term: Watersheds; Thesaurus Term: Mountain watersheds; Thesaurus Term: Landscapes; Subject Term: Landforms; Author-Supplied Keyword: Measurement frequency; Author-Supplied Keyword: Multisensor capacitance probe; Author-Supplied Keyword: Soil water content; Author-Supplied Keyword: Spatial pattern; Author-Supplied Keyword: Temporal stability; Author-Supplied Keyword: Upscaling; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.catena.2007.09.010
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - dos Santos, Ticiano J. Saraiva
AU - Fetter, Allen H.
AU - Hackspacher, P.C.
AU - Van Schmus, W.R.
AU - Nogueira Neto, J.A.
T1 - Neoproterozoic tectonic and magmatic episodes in the NW sector of Borborema Province, NE Brazil, during assembly of Western Gondwana
JO - Journal of South American Earth Sciences
JF - Journal of South American Earth Sciences
Y1 - 2008/05//
VL - 25
IS - 3
M3 - Article
SP - 271
EP - 284
SN - 08959811
AB - Abstract: The Médio Coreaú domain of NE Brazil is located along the northwest margin of Borborema Province, the western branch of a Brasiliano/Pan-African collisional belt that formed during the assembly of Western Gondwana. The early Paleoproterozoic basement of the Médio Coreaú domain is composed of migmatitic gneisses and juvenile granulites, overlain by late Paleoproterozoic and Neoproterozoic rocks intruded by syn- to post-tectonic Brasiliano granitoids. According to integrated structural and geochronological data (U–Pb zircon and monazite ages), the Neoproterozoic tectonic evolution of the Médio Coreaú is characterized by low-angle thrusting and transcurrent deformation. U–Pb geochronological data from plutons intruded during this compressional regime indicate the collisional evolution began at approximately 622Ma and continued until about 591Ma. The continuation of convergence until approximately 560Ma resulted in the formation of NE–SW and E–W shear zones within the Borborema Province and adjoining West African provinces. The final stage of the ductile tectonism was characterized by uplift and high-angle fault generation between approximately 560 and 545Ma. The last tectonic event was an extensional phase, resulting in the formation of the Jaibaras graben and intrusion of post-orogenic granites at around 532Ma. (English) [Copyright &y& Elsevier]
AB - Resumo: O domínio Médio Coreaú representa a margem noroeste da Província Borborema, compreendendo um cinturão colisional Brasiliano/Panafricano formado durante a aglutinação do Gondwana oeste. O embasamento paleoproterozóico é composto de gnaisses migmatíticos e granulitos de caráter juvenil, que estão cobertos por rochas do Paleoproterozóico tardio e Neoproterozóico, intrudidas por granitos sin a pós-tectônicos. Com base em dados estruturais e geocronológicos (idades U–Pb em zircão e monazita), é discutida a evolução tectônica do Domínio Médio Coreaú durante o Neoproterozóico. Esta tectônica é caracterizada por zonas de cavalgamento de baixo ângulo e falhas transcorrentes, originando extensas estruturas compressionais. Dados U–Pb dos plutons posicionados durante essa compressão indicam que a tectônica de baixo ângulo iniciou-se por volta de 622Ma e continuou até aproximadamente 591Ma. A contínua convergência foi responsável pelo surgimento de zonas transcorrentes há aproximadamente 560Ma, originando extensas zonas de cisalhamento NE–SW e E–W na Província Borborema e na correspondente província Oeste Africana. O estágio final da evolução da deformação dúctil caracterizou-se pelo soerguimento e formação de falhas de alto ângulo, inferidas de terem ocorrido entre ca. 560 e 545Ma. O último evento tectônico é caracterizado por pulsos extensionais, resultando na formação do graben de Jaibaras e intrusão de granitos pós-orogênicos há ca. 532Ma. ~2 wt.%) of dissolved water (Wet Magma), as is anticipated for this region, at or near its liquidus temperature and saturated with water at 200 MPa is at a temperature near or below the 1-atm solidus temperature. Isentropic ascent from this near liquidus temperature promotes extensive solidification and/or glassification. Exsolving water with approach to the surface promotes rapid vesiculation leading to fragmentation and tephra production. With continued ascent the still water-saturated magma traverses the solidification phase field and undergoes a combination of rapid crystallization and quenching, becoming a glassy highly viscous (~108 Pa s) mass of greatly reduced mobility. This immobility is reflected in the high effective viscosity regulating flows from nearby cinder cones associated with wet basalt. This also matches well with the experimentally determined rheology of dry basalt glass. This rheology greatly restricts the mobility of basalt within repository drifts, amounting to <10 m per day. Magma in this state quenches rapidly (~10 cm/min) on waste packages. Wet basalt is explosive, but relatively immobile as lava. Dry Magma is not explosive, but highly mobile as lava. Previous studies have tended to use an inconsistent set of mixed magma properties involving both extremes. The net effect of our results is that the portion of a repository hypothetically affected by invading magma is likely to be minimal and the number of waste packages affected may be very small. Moreover, the waste packages and/or waste materials affected will most likely be encased in quenched magma. [Copyright &y& Elsevier]
AB - Copyright of Journal of Volcanology & Geothermal Research is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - LAVA flows
KW - VOLCANOLOGY
KW - RADIOACTIVE waste repositories
KW - RHEOLOGY
KW - VOLCANIC ash, tuff, etc.
KW - YUCCA Mountain (Nev.)
KW - NEVADA
KW - magma
KW - nuclear repository
KW - Yucca Mountain
N1 - Accession Number: 37574330; Marsh, Bruce D. 1; Email Address: bmarsh@jhu.edu Coleman, Neil M. 2; Affiliation: 1: M.K. Blaustein Department of Earth and Planetary Sciences, Johns Hopkins University, Baltimore, MD, USA 2: U.S. Nuclear Regulatory Commission (NRC), Advisory Committee on Reactor Safeguards, Washington, DC, USA; Source Info: May2009, Vol. 182 Issue 1/2, p76; Subject Term: LAVA flows; Subject Term: VOLCANOLOGY; Subject Term: RADIOACTIVE waste repositories; Subject Term: RHEOLOGY; Subject Term: VOLCANIC ash, tuff, etc.; Subject Term: YUCCA Mountain (Nev.); Subject Term: NEVADA; Author-Supplied Keyword: magma; Author-Supplied Keyword: nuclear repository; Author-Supplied Keyword: Yucca Mountain; NAICS/Industry Codes: 212399 All Other Nonmetallic Mineral Mining; NAICS/Industry Codes: 212398 All other non-metallic mineral mining and quarrying; NAICS/Industry Codes: 212319 Other Crushed and Broken Stone Mining and Quarrying; NAICS/Industry Codes: 212316 Marble mining and quarrying; NAICS/Industry Codes: 212311 Dimension Stone Mining and Quarrying; Number of Pages: 21p; Document Type: Article
L3 - 10.1016/j.jvolgeores.2009.01.029
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Walker, J. Samuel
T1 - Nuclear Implosions: The Rise and Fall of the Washington Public Power Supply System.
JO - Pacific Historical Review
JF - Pacific Historical Review
Y1 - 2009/05//
VL - 78
IS - 2
M3 - Book Review
SP - 317
EP - 318
SN - 00308684
AB - The article reviews the book "Nuclear Implosions: The Rise and Fall of the Washington Public Power Supply System," by Daniel Pope.
KW - POWER resources
KW - NONFICTION
KW - UNITED States
KW - POPE, Daniel
KW - NUCLEAR Implosions: The Rise & Fall of the Washington Public Power Supply System (Book)
N1 - Accession Number: 39794538; Walker, J. Samuel 1; Affiliation: 1: U.S. Nuclear Regulatory Commission; Source Info: May2009, Vol. 78 Issue 2, p317; Subject Term: POWER resources; Subject Term: NONFICTION; Subject Term: UNITED States; Reviews & Products: NUCLEAR Implosions: The Rise & Fall of the Washington Public Power Supply System (Book); People: POPE, Daniel; Number of Pages: 2p; Document Type: Book Review
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Tae-Woong Kim
AU - Hosung Ahn
T1 - Spatial rainfall model using a pattern classifier for estimating missing daily rainfall data.
JO - Stochastic Environmental Research & Risk Assessment
JF - Stochastic Environmental Research & Risk Assessment
Y1 - 2009/05//
VL - 23
IS - 4
M3 - Article
SP - 367
EP - 376
SN - 14363240
AB - Missing data in daily rainfall records are very common in water engineering practice. However, they must be replaced by proper estimates to be reliably used in hydrologic models. Presented herein is an effort to develop a new spatial daily rainfall model that is specifically intended to fill in gaps in a daily rainfall dataset. The proposed model is different from a convectional daily rainfall generation scheme in that it takes advantage of concurrent measurements at the nearby sites to increase the accuracy of estimation. The model is based on a two-step approach to handle the occurrence and the amount of daily rainfalls separately. This study tested four neural network classifiers for a rainfall occurrence processor, and two regression techniques for a rainfall amount processor. The test results revealed that a probabilistic neural network approach is preferred for determining the occurrence of daily rainfalls, and a stepwise regression with a log-transformation is recommended for estimating daily rainfall amounts. [ABSTRACT FROM AUTHOR]
AB - Copyright of Stochastic Environmental Research & Risk Assessment is the property of Springer Science & Business Media B.V. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - ENGINEERING
KW - RAINFALL anomalies
KW - HYDROLOGICAL stations
KW - RAIN & rainfall
KW - RAINFALL intensity duration frequencies
KW - Daily rainfall model
KW - Missing data
KW - Neural network
KW - Pattern classification
KW - Stochastic process
N1 - Accession Number: 36227594; Tae-Woong Kim 1; Email Address: twkim72@hanyang.ac.kr Hosung Ahn 2; Email Address: HXA1@nrc.gov; Affiliation: 1: Department of Civil and Environmental System Engineering, Hanyang University, Gyeonggi-do 426-791, Korea 2: US Nuclear Regulatory Commission, Mail Stop O9E3, Washington, DC 20555, USA; Source Info: May2009, Vol. 23 Issue 4, p367; Subject Term: ENGINEERING; Subject Term: RAINFALL anomalies; Subject Term: HYDROLOGICAL stations; Subject Term: RAIN & rainfall; Subject Term: RAINFALL intensity duration frequencies; Author-Supplied Keyword: Daily rainfall model; Author-Supplied Keyword: Missing data; Author-Supplied Keyword: Neural network; Author-Supplied Keyword: Pattern classification; Author-Supplied Keyword: Stochastic process; Number of Pages: 10p; Illustrations: 2 Diagrams, 6 Charts, 1 Graph, 1 Map; Document Type: Article
L3 - 10.1007/s00477-008-0223-9
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Hakan Başağaoğlu
AU - Sauro Succi
AU - Chandrika Manepally
AU - Randall Fedors
AU - Danielle Wyrick
T1 - Sensitivity of the active fracture model parameter to fracture network orientation and injection scenarios.
JO - Hydrogeology Journal
JF - Hydrogeology Journal
Y1 - 2009/09//
VL - 17
IS - 6
M3 - Article
SP - 1347
EP - 1358
SN - 14312174
AB - Abstract Active fractures refer to the portions of unsaturated, connected fractures that actively conduct water. The active fracture model parameter accounts for the reduction in the number of fractures carrying water and in the fracture–matrix interface area in field-scale simulations of flow and transport in unsaturated fractured rocks. One example includes the numerical analyses of the fault test results at the Yucca Mountain site, Nevada (USA). In such applications, the active fracture model parameter is commonly used as a calibration parameter without relating it to fracture network orientations and infiltration rates. A two-dimensional, multiphase lattice-Boltzmann model was used in this study to investigate the sensitivity of the active fracture model parameter to fracture network orientation and injection scenarios for an unsaturated, variable dipping, and geometrically simple fracture network. The active fracture model parameter differed by as much as 0.11–0.44 when the effects of fracture network orientation, injection rate, and injection mode were included in the simulations. Hence, the numerical results suggest that the sensitivity of the active fracture model parameter to fracture network orientation, injection rates, and injection modes should be explored at the field-scale to strengthen the technical basis and range of applicability of the active fracture model. [ABSTRACT FROM AUTHOR]
AB - Copyright of Hydrogeology Journal is the property of Springer Science & Business Media B.V. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Numerical analysis
KW - Fracture mechanics
KW - Geological modeling
KW - Interfaces (Physical sciences)
KW - Sensitivity analysis
KW - Calibration
KW - Lattice Boltzmann methods
KW - Yucca Mountain (Nev.)
KW - Nevada
N1 - Accession Number: 44133482; Hakan Başağaoğlu 1; Sauro Succi 2; Chandrika Manepally 1; Randall Fedors 3; Danielle Wyrick 4; Affiliations: 1: Southwest Research Institute Center for Nuclear Waste Regulatory Analyses 6220 Culebra Rd. San Antonio TX 78238 USA; 2: Instituto Applicazioni Calcolo, CNR-IAC Viale del Policlinico 137 00161 Rome Italy; 3: US Nuclear Regulatory Commission, MS T-7F27 Washington, DC 20555 USA; 4: Southwest Research Institute Department of Earth, Material, and Planetary Sciences 6220 Culebra Rd. San Antonio TX 78238 USA; Issue Info: Sep2009, Vol. 17 Issue 6, p1347; Thesaurus Term: Numerical analysis; Subject Term: Fracture mechanics; Subject Term: Geological modeling; Subject Term: Interfaces (Physical sciences); Subject Term: Sensitivity analysis; Subject Term: Calibration; Subject Term: Lattice Boltzmann methods; Subject: Yucca Mountain (Nev.); Subject: Nevada; Number of Pages: 12p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - MarkIey, C. T.
AU - Miller, H.
AU - Kneeshaw, T.
AU - Herbert, B. E.
T1 - The Relationship Between Instructors' Conceptions of Geoscience Learning and Classroom Practice at a Research University.
JO - Journal of Geoscience Education
JF - Journal of Geoscience Education
J1 - Journal of Geoscience Education
PY - 2009/09//
Y1 - 2009/09//
VL - 57
IS - 4
M3 - Article
SP - 264
EP - 274
SN - 10899995
AB - Reform of undergraduate science education will need to be supported with effective professional development for current and future faculty. The professional development programs will need to address the knowledge, skills and beliefs of higher education faculty so that they can implement the kind of effective practices that results in the intended learning and meets the needs of diverse learners. To support the design of these programs, this research characterized the relationships between faculty's conceptions of teaching and learning on their teaching practices. Teaching faculty at a Doctoral/Research University were randomly interviewed to assess conceptions with respect to: 1) individual faculty learning, 2) student learning based on academic level, 3) how teaching is valued by the organization and 4) course goals. Additionally, classroom observations were conducted to determine the level of student-teacher interaction and cognitive engagement of the instructor and students with graphical and symbolic representations, as well as other manipulatives. Observations indicated teacher-centered classes across all academic levels. These data contrasted the subject's conceptions that cognitive and technical skill development is best achieved through self-directed learning. Analysis of the interviews and observations suggested the contradiction between learning practices the subject viewed as effective and the utilized teaching methods resulted from two major barriers: 1) the instructors' conceptions on the evolution of student learning and 2) an institutional reward structure that doesn't support the development of effective teaching practices. [ABSTRACT FROM AUTHOR]
AB - Copyright of Journal of Geoscience Education is the property of National Association of Geoscience Teachers, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - TEACHER-student communication
KW - SCIENCE -- Study & teaching
KW - GEOLOGY -- Study & teaching
KW - LEARNING
KW - EDUCATION
KW - OBSERVATION (Educational method)
KW - COGNITIVE ability in science
KW - RESEARCH universities & colleges
N1 - Accession Number: 47723477; Source Information: Sep2009, Vol. 57 Issue 4, p264; Subject Term: TEACHER-student communication; Subject Term: SCIENCE -- Study & teaching; Subject Term: GEOLOGY -- Study & teaching; Subject Term: LEARNING; Subject Term: EDUCATION; Subject Term: OBSERVATION (Educational method); Subject Term: COGNITIVE ability in science; Subject Term: RESEARCH universities & colleges; Subject Term: ; Number of Pages: 11p; ; Document Type: Article;
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DP - EBSCOhost
DB - trh
ER -
TY - JOUR
AU - Gallucci, Raymond
T1 - Thirty-three Years of Regulating Fire Protection at Commercial U.S. Nuclear Power Plants: Dousing the Flames of Controversy**.
JO - Fire Technology
JF - Fire Technology
Y1 - 2009/12//
VL - 45
IS - 4
M3 - Article
SP - 355
EP - 380
PB - Springer Science & Business Media B.V.
SN - 00152684
AB - This article focuses on what have been, and may continue to be, the more controversial aspects of fires at commercial nuclear power plants regulated by the U.S. Nuclear Regulatory Commission. Examining what has transpired in fire protection regulation since the 1975 fire at Browns Ferry Unit 1, which first focused attention on the potential hazard of fire at commercial nuclear power plants, we offer a personal perspective as to whether or not the “the flames of controversy” have been “doused.” We show that significant progress has been made while speculating whether these “flames” may ever truly be extinguished, or only kept under control. No core damage accident has ever occurred at a commercial nuclear power plant due to fire. [ABSTRACT FROM AUTHOR]
AB - Copyright of Fire Technology is the property of Springer Science & Business Media B.V. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear power plants
KW - Fire management
KW - Fire -- Safety measures
KW - Safety regulations
KW - United States
KW - fire protection
KW - history
KW - nuclear power plants
KW - regulation
KW - safety
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 41779788; Gallucci, Raymond 1; Email Address: gallucci@localnet.com; Affiliations: 1: Office of Nuclear Reactor Regulation/Fire Protection Branch, US Nuclear Regulatory Commission, 8956 Amelung St. Frederick 21704 USA; Issue Info: Dec2009, Vol. 45 Issue 4, p355; Thesaurus Term: Nuclear power plants; Thesaurus Term: Fire management; Subject Term: Fire -- Safety measures; Subject Term: Safety regulations; Subject: United States; Author-Supplied Keyword: fire protection; Author-Supplied Keyword: history; Author-Supplied Keyword: nuclear power plants; Author-Supplied Keyword: regulation; Author-Supplied Keyword: safety ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 926120 Regulation and Administration of Transportation Programs; Number of Pages: 26p; Document Type: Article
L3 - 10.1007/s10694-008-0052-x
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Bahn, Chi Bum
AU - Kasza, Ken E.
AU - Shack, William J.
AU - Natesan, Ken
AU - Klein, Paul
T1 - Evaluation of precipitates used in strainer head loss testing. Part I. Chemically generated precipitates
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2009/12//
VL - 239
IS - 12
M3 - Article
SP - 2981
EP - 2991
SN - 00295493
AB - Abstract: The purpose of the current program was to evaluate the properties of chemical precipitates proposed by industry that have been used in sump strainer head loss testing. Specific precipitates that were evaluated included aluminum oxyhydroxide (AlOOH) and sodium aluminum silicate (SAS) prepared according to the procedures in WCAP-16530-NP, along with precipitates formed from injecting chemicals into the test loop according to the procedure used by one sump strainer test vendor for U.S. pressurized water reactors. The settling rates of the surrogate precipitates are strongly dependent on their particle size and are reasonably consistent with those expected from Stokes’ Law or colloid aggregation models. Head loss tests showed that AlOOH and SAS surrogates are quite effective in increasing the head loss across a perforated pump inlet strainer that has an accumulated fibrous debris bed. The characteristics of aluminum hydroxide precipitate using sodium aluminate were dependent on whether it was formed in high-purity or ordinary tap water and whether excess silicate was present or not. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - PRECIPITATION (Chemistry)
KW - ALUMINUM compounds
KW - ALUMINUM silicates
KW - PRESSURIZED water reactors
KW - STOKES equations
KW - CLUSTERING of particles
KW - UNITED States
N1 - Accession Number: 45422806; Bahn, Chi Bum 1; Email Address: bahn@anl.gov Kasza, Ken E. 1 Shack, William J. 1 Natesan, Ken 1 Klein, Paul 2; Affiliation: 1: Argonne National Laboratory, Argonne, IL 60439, USA 2: The United States Nuclear Regulatory Commission, Rockville, MD 20852, USA; Source Info: Dec2009, Vol. 239 Issue 12, p2981; Subject Term: PRECIPITATION (Chemistry); Subject Term: ALUMINUM compounds; Subject Term: ALUMINUM silicates; Subject Term: PRESSURIZED water reactors; Subject Term: STOKES equations; Subject Term: CLUSTERING of particles; Subject Term: UNITED States; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.nucengdes.2009.09.023
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Bajwa, Christopher S.
AU - Piotter, Jason
AU - Cuta, Judith
AU - Adkins, Harold
AU - Klymyshyn, Nicholas
AU - Fort, James
AU - Suffield, Sarah
T1 - Best Practices for Finite Element Analysis of Spent Nuclear Fuel Transfer, Storage, and Transportation Systems.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - 12
PB - Institute of Nuclear Materials Management
AB - Storage casks and transportation packages for spent nuclear fuel (SNF) are designed to confine SNF in sealed canisters or casks, provide structural integrity during accidents, and remove decay through a storage or transportation overpack. The transfer, storage, and transportation of SNF in dry storage casks and transport packages is regulated under 10 CFR Part 72 and 10 CFR Part 71, respectively. Finite Element Analysis (FEA) is used with increasing frequency in Safety Analysis Reports and other regulatory technical evaluations related to SNF casks and packages and their associated systems. Advances in computing power have made increasingly sophisticated FEA models more feasible, and as a result, the need for careful review of such models has also increased. This paper identifies best practice recommendations that stem from recent NRC review experience. The scope covers issues common to all commercially available FEA software, and the recommendations are applicable to any FEA software package. Three specific topics are addressed: general FEA practices, issues specific to thermal analyses, and issues specific to structural analyses. General FEA practices covers appropriate documentation of the model and results, which is important for an efficient review process. The thermal analysis best practices are related to cask analysis for steady state conditions and transient scenarios. The structural analysis best practices are related to the analysis of casks and associated payload during standard handling and drop scenarios. The best practices described in this paper are intended to identify FEA modeling issues and provide insights that can help minimize associated uncertainties and errors, in order to facilitate the NRC licensing review process. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear fuels
KW - Radioactive substance transport
KW - Radioactive waste canisters
KW - Finite element method
KW - Thermal analysis
KW - Structural analysis (Engineering)
N1 - Accession Number: 58108569; Bajwa, Christopher S. 1; Piotter, Jason 1; Cuta, Judith 2; Adkins, Harold 2; Klymyshyn, Nicholas 2; Fort, James 2; Suffield, Sarah 2; Affiliations: 1: US Nuclear Regulatory Commission, Rockville, MD, USA; 2: Pacific Northwest National Laboratory, Richland, WA, USA; Issue Info: 2010, p1; Thesaurus Term: Nuclear fuels; Subject Term: Radioactive substance transport; Subject Term: Radioactive waste canisters; Subject Term: Finite element method; Subject Term: Thermal analysis; Subject Term: Structural analysis (Engineering); NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 484230 Specialized Freight (except Used Goods) Trucking, Long-Distance; Number of Pages: 12p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - DeMuth, Scott
AU - Lockwood, Dunbar
AU - Grice, Thomas
T1 - SAFEGUARDS BY DESIGN - INDUSTRY ENGAGEMENT FOR NEW URANIUM ENRICHMENT FACILITIES IN THE UNITED STATES.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - 8
PB - Institute of Nuclear Materials Management
AB - The United States Department of Energy's (DOE's) Office of Nonproliferation and International Security (NA-24) has initiated a Safeguards by Design (SBD) effort to encourage the incorporation of international (IAEA) safeguards features early in the design phase of a new nuclear facility in order to avoid the need to redesign or retrofit the facility at a later date. The main goals of Safeguards by Design are to (1) make the implementation of international safeguards at new civil nuclear facilities more effective and efficient, (2) avoid costly and time-consuming re-design work or retrofits at such facilities and (3) design such facilities in a way that makes proliferation as technically difficult, as time-consuming, and as detectable as possible. The U.S. Nuclear Regulatory Commission (NRC) has recently hosted efforts to facilitate the use of Safeguards by Design for new uranium enrichment facilities currently being planned for construction in the U.S. While SBD is not a NRC requirement, the NRC is aiding the implementation of SBD by coordinating discussions between DOE's NA-24 and industry's facility design teams. More specifically, during their normal course of licensing discussions the NRC has offered industry the opportunity to engage with NA-24 regarding SBD. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Uranium -- Government policy
KW - National security
KW - Nuclear facilities -- Security measures
KW - United States
KW - United States. Dept. of Energy
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 58108496; DeMuth, Scott 1; Lockwood, Dunbar 2; Grice, Thomas 3; Affiliations: 1: Los Alamos National Laboratory P.O. Box 1663, Los Alamos, NM 87545; 2: National Nuclear Security Administration (NNSA) Office of Nuclear Safeguards 1000 Independence Ave SW, Washington DC 20585-1615; 3: United States Nuclear Regulatory Commission Washington, DC 20555; Issue Info: 2010, p1; Subject Term: Uranium -- Government policy; Subject Term: National security; Subject Term: Nuclear facilities -- Security measures; Subject: United States ; Company/Entity: United States. Dept. of Energy ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 928110 National Security; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 926110 Administration of General Economic Programs; NAICS/Industry Codes: 213119 Other support activities for mining; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; Number of Pages: 8p; Illustrations: 2 Diagrams; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Grice, Thomas A.
T1 - The Status of the U.S. Nuclear Regulatory Commission's Implementation of the U.S./IAEA Additional Protocol.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - 3
PB - Institute of Nuclear Materials Management
AB - On January 6, 2009 the U.S. submitted the instrument of ratification for the "Protocol Additional to the Agreement between the United States of America and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in the United States of America" (U.S./IAEA Additional Protocol) to the IAEA, bringing the U.S./IAEA Additional Protocol treaty into force. Entry-into-force of the U.S./IAEA Additional Protocol demonstrates the ongoing commitment by the United States to promote universal adherence to the IAEA Additional Protocol (AP). The AP is designed to supplement the Nonproliferation Treaty by increasing the authority and expanding the activities of the IAEA to strengthen the IAEA's ability to detect nuclear material diversion and clandestine nuclear weapons development activities in non-nuclear weapon states. The AP requires information about nuclear fuel cycle-related research and development activities that do not involve nuclear material (and therefore are not reported under traditional safeguards) as well as information about manufacture and exports of certain equipment and material especially designed or prepared for nuclear use, additional information about nuclear sites already declared under comprehensive safeguards agreements, and information about mines and depleted and natural uranium. Since the ratification of the U.S./IAEA Additional Protocol, the Nuclear Regulatory Commission has focused on working with NRC and Agreement State licensees to ensure appropriate reporting of information as required by the AP. This paper provides an updated status of the U.S. Nuclear Regulatory Commission's Implementation of the U.S./IAEA Additional Protocol, the impact on licensees and lessons learned during the first year of implementation. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear weapons
KW - Uranium
KW - United States
KW - U.S. Nuclear Regulatory Commission
KW - International Atomic Energy Agency
KW - Treaty on the Non-proliferation of Nuclear Weapons (1968)
N1 - Accession Number: 58108667; Grice, Thomas A. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission, Washington, D.C., USA; Issue Info: 2010, p1; Thesaurus Term: Nuclear weapons; Thesaurus Term: Uranium; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: International Atomic Energy Agency; Reviews & Products: Treaty on the Non-proliferation of Nuclear Weapons (1968); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 213119 Other support activities for mining; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 3p; Illustrations: 1 Chart; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Lindsay, Haile
AU - Garcia - Santos, Norma
AU - Saverot, Pierre
AU - Day, Neil
AU - Sotomayor - Rivera, Alexis
AU - Vechioli, Lucieann
AU - Waters, Michael
T1 - KNOWLEDGE MANAGEMENT INITIATIVES TO MAINTAIN REGULATORY EXPERTISE IN TRANSPORTATION OF RADIOACTIVE MATERIALS.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - 7
PB - Institute of Nuclear Materials Management
AB - The NRC was established in 1974 to regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health, safety, and the environment, and promote the common defense and security. Approximately half (49%) of the workforce at the United States (U.S.) Nuclear Regulatory Commission (NRC) (the Agency) has been with the Agency for less than six years. The NRC program responsible for the regulatory oversight of the transportation of radioactive materials has experienced a significant level of staff attrition that has resulted in several combined years of transportation expertise leaving the transportation program. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within the Agency to support recent growth of NRC in reactor program areas. Several knowledge management (KM) strategies and activities have been implemented within the Agency, including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team facilitates the capture, transfer, and documentation of regulatory knowledge for newer staff to effectively perform their safety oversight of transportation of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71. Other KM Strategies that have been implemented in the SFST area include: (1) development of a SFST Qualification Journal Community of Practice (CoP) and a Packaging and Storing Radioactive Material CoP in the on-line NRC Knowledge Center (NKC); (2) an electronic library containing documentation related to the licensing of packages to transport radioactive materials and spent nuclear fuel (SNF); (3) implementation of a SFST seminar program; (4) technical discipline group programs to share knowledge within specialty areas; (5) development of written guidance to capture "administrative and technical" knowledge (e.g., office procedures, standard review plans); and (6) use of mentoring strategies for experienced staff to train new staff members. This paper will describe and discuss the success and challenges in implementing these KM strategies at the NRC, especially in the area of transportation of spent nuclear fuel. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear fuels
KW - Radioactive substances
KW - Knowledge management
KW - United States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 58108439; Lindsay, Haile 1; Garcia - Santos, Norma 1; Saverot, Pierre 1; Day, Neil 1; Sotomayor - Rivera, Alexis 1; Vechioli, Lucieann 1; Waters, Michael 1; Affiliations: 1: United States Nuclear Regulatory Commission Mail Stop EBB-03D-02M, 6003 Executive Boulevard, Rockville, MD 20852; Issue Info: 2010, p1; Thesaurus Term: Nuclear fuels; Thesaurus Term: Radioactive substances; Subject Term: Knowledge management; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 7p; Illustrations: 3 Color Photographs, 1 Chart; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Matula, Thomas O.
T1 - U.S. NUCLEAR REGULATORY COMMISSION STAFF INTEGRATING SPENT NUCLEAR FUEL REGULATORY ACTIVITIES.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - A4
PB - Institute of Nuclear Materials Management
AB - The staff of the U.S. Nuclear Regulatory Commission (NRC staff) is implementing a systematic process for integrating regulatory activities to address future challenges related to the management of spent nuclear fuel (SNF) and high-level waste (HLW). This process is intended to assist the NRC staff in addressing ongoing changes in the national strategy for managing SNF and HLW and protecting public health and safety and the environment. This process will assure that the NRC staff treats SNF and HLW regulation as interrelated activities so that decisions made about one component or area of the back end of the nuclear fuel cycle adequately consider and integrate related components or areas. Treating the interrelated systems and activities involved in the regulation of SNF and HLW as one integrated system can be more efficient and effective than regulating them individually. By coordinating the regulation of SNF or HLW storage, transportation, reprocessing, and disposal, the NRC staff can help improve the efficiency and effectiveness of NRC regulatory processes and provide stability and predictability for stakeholders in a dynamic environment. In addition, the process provides an organized approach for sharing information and perspectives among, and collaborating with, internal stakeholders; other Federal agencies; State, local, and tribal governments; international partners; the industry; the public; and other interested stakeholders. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear fuels
KW - Public health
KW - Public safety
KW - United States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 58108684; Matula, Thomas O. 1; Affiliations: 1: Senior Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards; Issue Info: 2010, p1; Thesaurus Term: Nuclear fuels; Thesaurus Term: Public health; Subject Term: Public safety; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 525120 Health and Welfare Funds; Number of Pages: 8p; Illustrations: 1 Diagram, 2 Charts; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Solis, Jorge
AU - Zigh, Ghani
T1 - BEST PRACTICE GUIDELINES FOR THE USE OF CFD IN DRY CASK APPLICATIONS.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - 8
PB - Institute of Nuclear Materials Management
AB - Dry casks are designed to confine spent nuclear fuel in sealed canisters and complex CFD models are used to analyze decay heat removal. Deficiencies and inaccuracies of CFD analyses can be caused by a variety of errors and uncertainties. Validation of heat transfer and fluid flow phenomena in dry casks are used to reduce uncertainties. Discussion of modeling uncertainties focuses on turbulence models which greatly influence the predicted results if not applied correctly. Several approaches to model turbulence are investigated and compared to experimental data and CFD best practice guidelines to minimize turbulence modeling uncertainties for dry cask analysis are given. Discussion also focuses on application uncertainties which are introduced because the application is complex and precise data is not always available. The discussion focuses on the inlet and outlet boundary conditions of ventilated dry storage casks. As cooling air is naturally induced in ventilated dry casks, pressure boundaries are the preferred choice at the inlet and outlet ducts. The pressure gradient in the air flow channel affects the magnitude of the potential buoyancy forces due to spent fuel decay heat and as such, the pressure boundary conditions are very crucial to the simulation uncertainties. Pressure boundary conditions are investigated and compared to experimental data to minimize application uncertainties. Guidelines to avoid uncertainties in the specification of the pressure boundary conditions are given. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear fuels
KW - Radioactive substances
KW - Guidelines
KW - Heat transfer
KW - Wine barrels
N1 - Accession Number: 58108431; Solis, Jorge 1; Zigh, Ghani 1; Affiliations: 1: U.S. Nuclear Regulatory Commission 11555 Rockville Pike, Rockville, MD 20852; Issue Info: 2010, p1; Thesaurus Term: Nuclear fuels; Thesaurus Term: Radioactive substances; Subject Term: Guidelines; Subject Term: Heat transfer; Subject Term: Wine barrels; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 8p; Illustrations: 1 Chart, 8 Graphs; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Ward, Steven L.
AU - Pham, Thomas N.
T1 - The U.S. Nuclear Regulatory Commission's Rulemaking Process and the Part 74 Rulemaking.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - 4
PB - Institute of Nuclear Materials Management
AB - The Atomic Energy Act of 1954, as amended, empowers the U.S. Nuclear Regulatory Commission (NRC) to establish by rule or order, and to enforce, standards to govern civilian uses of nuclear materials in order to protect health and safety and minimize danger to life or property. The NRC issues regulations in Title 10 Code of Federal Regulations (10 CFR). NRC Regulations govern the construction and operation of nuclear power plants and fuel cycle facilities as well as the use of radioactive materials. The NRC's rulemaking process is governed by the Administrative Procedures Act. NRC regulations are created and updated in an open environment, providing opportunities for the public to provide input to the regulations multiple times. The rulemaking process includes coordination between the NRC, its licensees, the public, and other interested parties. NRC develops, documents, and implements policies and procedures for developing effective, coherent, consistent, and understandable regulations. NRC staff prepare regulatory analyses, including cost analysis on the impact of proposed regulatory activities and the risk significance of its regulations. NRC also creates rulemaking schedules to ensure that rules are developed in time frames specified by Commission guidance. This paper will provide an overview of the NRC's rulemaking process. NRC staff are currently revising 10 CFR Part 74: Material Control and Accounting for Special Nuclear Material. This section details the requirements for material control and accounting (MC&A) of special nuclear material (SNM) for fuel cycle facilities and other licensees possessing SNM. The revision includes relocating some MC&A requirements from other 10 CFR chapters to consolidate MC&A requirements in Part 74. Additional changes include revision of general performance objectives, addition of definitions, revision of MC&A exemptions, and enhancement of tamper-indicating device programs. This paper will discuss the proposed changes to 10 CFR Part 74 and opportunities for public involvement during the remainder of the rulemaking process. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Delegated legislation
KW - Radioactive wastes
KW - Nuclear power plants -- Accidents -- United States
KW - United States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 58108665; Ward, Steven L. 1; Pham, Thomas N. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: 2010, p1; Thesaurus Term: Delegated legislation; Thesaurus Term: Radioactive wastes; Subject Term: Nuclear power plants -- Accidents -- United States; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Ward, Steven L.
T1 - The Status of the Series 5 Regulatory Guide Revisions.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - 4
PB - Institute of Nuclear Materials Management
AB - The U.S. Nuclear Regulatory Commission sets forth regulations for licensees in Title 10 Code of Federal Regulations (10 CFR). To assist licensees and the public in understanding how to comply with the regulations, the NRC issues guidance documents known as regulatory guides. Regulatory guides contain acceptable methods for licensees to comply with NRC regulations. These guides only provide suggestions and do not contain any new or additional requirements beyond what is contained in 10 CFR. Regulatory guides provide guidance to licensees, applicants, and stakeholders on (1) implementing specific parts of the NRC's regulations, (2) techniques used by the NRC staff for evaluating specific problems or postulated accidents, (3) data needed by the NRC staff for review of applications for permits or licenses, and (4) the preferred standard format and content for information submitted for NRC's approval of a specific program, license, permit, or certificate. During development, regulatory guides undergo extensive reviews by NRC staff, stakeholders, the public, and as appropriate, advisory committees to the NRC. NRC staff are currently revising all regulatory guides relating to material control and accounting (MC&A) of special nuclear material (SNM). This process will make the guides current to reflect both current technology and the current threat environment. The MC&A regulatory guides will also be consolidated into 11 guides covering all aspects of MC&A to provide licensees and the public with concise, understandable, and accurate information on complying with MC&A regulations. This paper will provide an overview of the current revision process and information on opportunities for public involvement throughout the process. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Federal regulation
KW - Licenses
KW - Stakeholders
KW - Accounting -- Law & legislation
KW - United States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 58108666; Ward, Steven L. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: 2010, p1; Thesaurus Term: Federal regulation; Subject Term: Licenses; Subject Term: Stakeholders; Subject Term: Accounting -- Law & legislation; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 541219 Other Accounting Services; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Whaley, Sheena A.
AU - Ward, Steven L.
T1 - An Overview of the U.S. Nuclear Regulatory Commission.
JO - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
JF - Proceedings of the Institute of Nuclear Materials Management Annual Meeting
Y1 - 2010/01//
M3 - Article
SP - 1
EP - 5
PB - Institute of Nuclear Materials Management
AB - This paper provides an overview of the NRC organization and its activities. The U.S. Nuclear Regulatory Commission (NRC) was created by The Energy Reorganization Act of 1974 and began operations on January 19, 1975. NRC is an independent regulatory agency, led by a five member, politically-appointed commission. The agency's mission is to "protect people and the environment." The NRC mission covers three main areas; reactors, materials, and waste. The NRC is responsible for overseeing the construction and operation of civilian nuclear reactors in the United States and regulating the safe use of radioactive materials for civilian purposes. This includes medical, industrial, and academic settings and facilities that produce nuclear fuel, as well as the waste. The NRC is responsible for all aspects of the nuclear fuel cycle including mining, milling, conversion, enrichment, fuel fabrication, operating power reactors, storage of spent fuel, long-term disposal of waste, and decommissioning of nuclear facilities. NRC works with the U.S. Department of Energy, the International Atomic Energy Agency, and other government and international organizations to promote the safe use of nuclear materials throughout the world. The NRC engages in extensive public outreach activities and encourages public involvement in its regulatory activities. [ABSTRACT FROM AUTHOR]
AB - Copyright of Proceedings of the Institute of Nuclear Materials Management Annual Meeting is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear reactors -- Design & construction
KW - Outreach programs
KW - United States
KW - U.S. Nuclear Regulatory Commission
KW - International Atomic Energy Agency
N1 - Accession Number: 58108661; Whaley, Sheena A. 1; Ward, Steven L. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: 2010, p1; Subject Term: Nuclear reactors -- Design & construction; Subject Term: Outreach programs; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: International Atomic Energy Agency; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; NAICS/Industry Codes: 624110 Child and Youth Services; Number of Pages: 5p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Zhao, Jack Y.
T1 - The Advanced Digital Fieldbus Option for Nuclear Plants.
JO - Power
JF - Power
Y1 - 2010/02//
VL - 154
IS - 2
M3 - Article
SP - 32
EP - 36
PB - Access Intelligence LLC
SN - 00325929
AB - The article offers information on the advanced digital fieldbus technology in nuclear power plants. The technology works as a local area network for control systems of power plants. It is being used in oil and gas, paper, and petrochemical industries. It discusses how the technology helps to reduce the cost. It states the example of water system in nuclear power which explains how the technology is beneficial. It highlights that the technology has been approved by the International Electrotechnical Commission (IEC).
KW - PROFIBUS (Computer bus)
KW - NUCLEAR power plants
KW - DIGITAL control systems
KW - PETROLEUM chemicals industry
KW - LOCAL area networks (Computer networks)
N1 - Accession Number: 49042964; Zhao, Jack Y. 1; Email Address: jack.zhao@nrc.gov; Affiliation: 1: Senior electronics engineer (digital l&C) for the U.S. Nuclear Regulatory Commission in the Instrumentation, Controls, and Electrical Engineering Branch No. 2 Division in Rockville, Md.; Source Info: Feb2010, Vol. 154 Issue 2, p32; Subject Term: PROFIBUS (Computer bus); Subject Term: NUCLEAR power plants; Subject Term: DIGITAL control systems; Subject Term: PETROLEUM chemicals industry; Subject Term: LOCAL area networks (Computer networks); NAICS/Industry Codes: 541514 Computer systems design and related services (except video game design and development); NAICS/Industry Codes: 541512 Computer Systems Design Services; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 324110 Petroleum Refineries; NAICS/Industry Codes: 325110 Petrochemical Manufacturing; Number of Pages: 4p; Illustrations: 2 Charts; Document Type: Article; Full Text Word Count: 2953
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Doctor, S. R.
AU - Bond, L. J.
AU - Cumblidge, S. E.
AU - Bruemmer, S. M.
AU - Taylor, W. B.
AU - Carpenter, C. E.
AU - Hull, A. B.
AU - Malik, S. N.
T1 - AGING MANAGEMENT USING PROACTIVE MANAGEMENT OF MATERIALS DEGRADATION.
JO - AIP Conference Proceedings
JF - AIP Conference Proceedings
Y1 - 2010/02/22/
VL - 1211
IS - 1
M3 - Article
SP - 1876
EP - 1883
PB - American Institute of Physics
SN - 0094243X
AB - The U.S. Nuclear Regulatory Commission (NRC) has undertaken a program to lay the technical foundations for defining proactive actions to manage degradation of materials in light water reactors. The current focus is existing plants; however, if applied to new construction, there is potential to better monitor and manage plants throughout their life cycle. This paper discusses the NRC’s Proactive Management of Materials Degradation program and its application to nuclear power plant structures, systems, and components. [ABSTRACT FROM AUTHOR]
AB - Copyright of AIP Conference Proceedings is the property of American Institute of Physics and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - ELECTRIC power production
KW - NUCLEAR facilities
KW - ELECTRIC utilities
KW - UNITED States
KW - Diagnostics
KW - In-service Inspection
KW - Light Water Reactors
KW - Materials Aging
KW - Nondestructive Evaluation
KW - Nuclear Power Plants
KW - Proactive Management of Materials Degradation
KW - Prognostics
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 48429462; Doctor, S. R. 1 Bond, L. J. 1 Cumblidge, S. E. 1 Bruemmer, S. M. 1 Taylor, W. B. 1 Carpenter, C. E. 2 Hull, A. B. 2 Malik, S. N. 2; Affiliation: 1: Pacific Northwest National Laboratory, Richland, WA 99352. 2: U.S. Nuclear Regulatory Commission, Washington D.C. 20555-0001.; Source Info: 2/22/2010, Vol. 1211 Issue 1, p1876; Subject Term: ELECTRIC power production; Subject Term: NUCLEAR facilities; Subject Term: ELECTRIC utilities; Subject Term: UNITED States; Author-Supplied Keyword: Diagnostics; Author-Supplied Keyword: In-service Inspection; Author-Supplied Keyword: Light Water Reactors; Author-Supplied Keyword: Materials Aging; Author-Supplied Keyword: Nondestructive Evaluation; Author-Supplied Keyword: Nuclear Power Plants; Author-Supplied Keyword: Proactive Management of Materials Degradation; Author-Supplied Keyword: Prognostics; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 221112 Fossil Fuel Electric Power Generation; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 221121 Electric Bulk Power Transmission and Control; NAICS/Industry Codes: 221118 Other Electric Power Generation; NAICS/Industry Codes: 221111 Hydroelectric Power Generation; NAICS/Industry Codes: 221122 Electric Power Distribution; NAICS/Industry Codes: 221114 Solar Electric Power Generation; NAICS/Industry Codes: 221115 Wind Electric Power Generation; NAICS/Industry Codes: 221116 Geothermal Electric Power Generation; NAICS/Industry Codes: 221117 Biomass Electric Power Generation; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 8p; Illustrations: 2 Diagrams; Document Type: Article
L3 - 10.1063/1.3362326
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - CROSTON, SEAN D.
T1 - CONGRESS AND THE COURTS CLOSE THEIR EYES: THE CONTINUING ABDICATION OF THE DUTY TO REVIEW AGENCIES' NONCOMPLIANCE WITH THE CONGRESSIONAL REVIEW ACT.
JO - Administrative Law Review
JF - Administrative Law Review
Y1 - 2010///Summer2010
VL - 62
IS - 3
M3 - Article
SP - 907
EP - 918
SN - 00018368
AB - The article focuses on the U.S. federal agencies' noncompliance with the Act [2] of the U.S. Congressional Review Act (CRA). The act states that the agency promulgating such rule shall submit to the U.S. Congress and to the Comptroller General several items which include a copy of the rule and a concise statement explaining if it is a major CRA rule. It discusses a report issued by the U.S. Congressional Research Service (CRS) in 2009 on federal agencies' compliance with the CRA.
KW - GOVERNMENT agencies
KW - NONCOMPLIANCE
KW - COMPTROLLERS
KW - RULES & practice
KW - LEGISLATORS -- United States
KW - UNITED States
KW - UNITED States. Congress
KW - LIBRARY of Congress. Congressional Research Service
N1 - Accession Number: 55551475; CROSTON, SEAN D. 1; Affiliations: 1: Attorney at the United States Nuclear Regulatory Commission; Issue Info: Summer2010, Vol. 62 Issue 3, p907; Thesaurus Term: GOVERNMENT agencies; Thesaurus Term: NONCOMPLIANCE; Thesaurus Term: COMPTROLLERS; Subject Term: RULES & practice; Subject Term: LEGISLATORS -- United States; Subject: UNITED States ; Company/Entity: UNITED States. Congress ; Company/Entity: LIBRARY of Congress. Congressional Research Service; NAICS/Industry Codes: 921120 Legislative Bodies; Number of Pages: 12p; Document Type: Article; Full Text Word Count: 4562
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Boring, Ronald L.
AU - Hendrickson, Stacey M.L.
AU - Forester, John A.
AU - Tran, Tuan Q.
AU - Lois, Erasmia
T1 - Issues in benchmarking human reliability analysis methods: A literature review
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2010/06//
VL - 95
IS - 6
M3 - Article
SP - 591
EP - 605
SN - 09518320
AB - Abstract: There is a diversity of human reliability analysis (HRA) methods available for use in assessing human performance within probabilistic risk assessments (PRA). Due to the significant differences in the methods, including the scope, approach, and underlying models, there is a need for an empirical comparison investigating the validity and reliability of the methods. To accomplish this empirical comparison, a benchmarking study comparing and evaluating HRA methods in assessing operator performance in simulator experiments is currently underway. In order to account for as many effects as possible in the construction of this benchmarking study, a literature review was conducted, reviewing past benchmarking studies in the areas of psychology and risk assessment. A number of lessons learned through these studies is presented in order to aid in the design of future HRA benchmarking endeavors. [Copyright &y& Elsevier]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RELIABILITY (Personality trait)
KW - RISK assessment
KW - EMPIRICAL research
KW - PSYCHOLOGY
KW - BENCHMARKING (Management)
KW - LITERATURE reviews
KW - Benchmark
KW - Comparison
KW - Human reliability analysis
N1 - Accession Number: 48891889; Boring, Ronald L. 1 Hendrickson, Stacey M.L. 1 Forester, John A. 1; Email Address: jafores@sandia.gov Tran, Tuan Q. 2 Lois, Erasmia 3; Affiliation: 1: Risk and Reliability Analysis Department, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185-0748, United States 2: Human Factors and Instrumentation and Control Systems Department, Idaho National Laboratory, PO Box 1624, MS 3605, Idaho Falls, ID 83404-3605, United States 3: Human Factors and Reliability Branch, US Nuclear Regulatory Commission, Mail Stop C4A07M, Washington, DC 20555-0001, United States; Source Info: Jun2010, Vol. 95 Issue 6, p591; Subject Term: RELIABILITY (Personality trait); Subject Term: RISK assessment; Subject Term: EMPIRICAL research; Subject Term: PSYCHOLOGY; Subject Term: BENCHMARKING (Management); Subject Term: LITERATURE reviews; Author-Supplied Keyword: Benchmark; Author-Supplied Keyword: Comparison; Author-Supplied Keyword: Human reliability analysis; Number of Pages: 15p; Document Type: Article
L3 - 10.1016/j.ress.2010.02.002
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Harris, T.
AU - Layton, M.
T1 - Overview of U.S. Nuclear Regulatory Commission Security Activities.
JO - Journal of the Institute of Nuclear Materials Management
JF - Journal of the Institute of Nuclear Materials Management
Y1 - 2010///Summer2010
VL - 38
IS - 4
M3 - Article
SP - 36
EP - 39
PB - Institute of Nuclear Materials Management
SN - 08936188
AB - The U.S. Nuclear Regulatory Commission (NRC) regulates both the safety and security of special nuclear material and by-product materials. As such, it has a well developed and robust safety and security regulatory framework. Following the events of September 11, 2001, security was enhanced in a graded risk-informed manner for NRC licensees. Significant activities include issuing an order that required licensees to enhance security, updating design basis threats for radiological sabotage and theft/diversion, updating security regulations for nuclear power plants and developing security regulations for by-product materials. Today, NRC-regulated nuclear facilities are among the most secure in the nation's critical infrastructure. [ABSTRACT FROM AUTHOR]
AB - Copyright of Journal of the Institute of Nuclear Materials Management is the property of Institute of Nuclear Materials Management and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Industrial safety
KW - Nuclear facilities -- Government policy
KW - Nuclear power plants -- Security measures
KW - United States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 52526841; Harris, T. 1; Layton, M. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission, Office of Nuclear Security and Incident Response, Washington, DC USA; Issue Info: Summer2010, Vol. 38 Issue 4, p36; Thesaurus Term: Industrial safety; Subject Term: Nuclear facilities -- Government policy; Subject Term: Nuclear power plants -- Security measures; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Garrick, B. John
AU - Stetkar, John W.
AU - Bembia, Paul J.
T1 - Quantitative Risk Assessment of the New York State Operated West Valley Radioactive Waste Disposal Area.
JO - Risk Analysis: An International Journal
JF - Risk Analysis: An International Journal
Y1 - 2010/08//
VL - 30
IS - 8
M3 - Article
SP - 1219
EP - 1230
PB - Wiley-Blackwell
SN - 02724332
AB - This article is based on a quantitative risk assessment (QRA) that was performed on a radioactive waste disposal area within the Western New York Nuclear Service Center in western New York State. The QRA results were instrumental in the decision by the New York State Energy Research and Development Authority to support a strategy of in-place management of the disposal area for another decade. The QRA methodology adopted for this first of a kind application was a scenario-based approach in the framework of the triplet definition of risk (scenarios, likelihoods, consequences). The measure of risk is the frequency of occurrence of different levels of radiation dose to humans at prescribed locations. The risk from each scenario is determined by (1) the frequency of disruptive events or natural processes that cause a release of radioactive materials from the disposal area; (2) the physical form, quantity, and radionuclide content of the material that is released during each scenario; (3) distribution, dilution, and deposition of the released materials throughout the environment surrounding the disposal area; and (4) public exposure to the distributed material and the accumulated radiation dose from that exposure. The risks of the individual scenarios are assembled into a representation of the risk from the disposal area. In addition to quantifying the total risk to the public, the analysis ranks the importance of each contributing scenario, which facilitates taking corrective actions and implementing effective risk management. Perhaps most importantly, quantification of the uncertainties is an intrinsic part of the risk results. This approach to safety analysis has demonstrated many advantages of applying QRA principles to assessing the risk of facilities involving hazardous materials. [ABSTRACT FROM AUTHOR]
AB - Copyright of Risk Analysis: An International Journal is the property of Wiley-Blackwell and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Risk assessment
KW - Radioactive wastes
KW - Radioactive waste disposal
KW - Radiation
KW - Hazardous substances
KW - Dilution
KW - New York (State)
KW - Quantitative risk assessment (QRA)
KW - radioactive waste
KW - risk triplet
KW - scenarios
KW - West Valley
KW - New York State Energy Research & Development Authority
N1 - Accession Number: 52949383; Garrick, B. John 1; Email Address: bjgarrick@aol.com; Stetkar, John W. 2; Bembia, Paul J. 3; Affiliations: 1: Independent Consultant and Chairman, U.S. Nuclear Waste Technical Review Board, USA; 2: Independent Consultant and Member of USNRC Advisory Committee on Reactor Safeguards, USA; 3: West Valley Site Management Program, New York State Energy Research and Development Authority, USA; Issue Info: Aug2010, Vol. 30 Issue 8, p1219; Thesaurus Term: Risk assessment; Thesaurus Term: Radioactive wastes; Thesaurus Term: Radioactive waste disposal; Thesaurus Term: Radiation; Thesaurus Term: Hazardous substances; Subject Term: Dilution; Subject: New York (State); Author-Supplied Keyword: Quantitative risk assessment (QRA); Author-Supplied Keyword: radioactive waste; Author-Supplied Keyword: risk triplet; Author-Supplied Keyword: scenarios; Author-Supplied Keyword: West Valley ; Company/Entity: New York State Energy Research & Development Authority; NAICS/Industry Codes: 562112 Hazardous Waste Collection; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562210 Waste treatment and disposal; Number of Pages: 12p; Illustrations: 1 Color Photograph, 1 Diagram, 3 Graphs, 1 Map; Document Type: Article
L3 - 10.1111/j.1539-6924.2010.01418.x
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Yakirevich, A.
AU - Gish, T. J.
AU - Simunek, J.
AU - van Genuchten, M. Th.
AU - Pachepsky, Y. A.
AU - Nicholson, T. J.
AU - Cady, R. E.
T1 - Potential Impact of a Seepage Face on Solute Transport to a Pumping Well.
JO - Vadose Zone Journal
JF - Vadose Zone Journal
Y1 - 2010/08//
VL - 8
IS - 3
M3 - Article
SP - 686
EP - 696
AB - To develop predictive models for solute transport in the subsurface, the mechanisms governing transport must be understood and quantified. In this study, we used the HYDRUS-2D variably saturated flow and transport model to describe the observed mass flux breakthrough curves (BTCs) of three surface-applied tracers--Br-, Cl-, and pentafluorobenzoic acid (PFBA)--to a single well from which the tracers were pumped. Axisymmetrical transport simulations of the data indicated the presence of an active seepage face along the soil-well interface near the water table. The calculated cumulative water flux to the well through the seepage face was found to be 120% of the variable flux boundary into the well through the submerged zone. In addition, calculated mass fluxes of Br, Cl, and PFBA through the seepage interface were approximately 8, 4, and 11 times, respectively, those through the variable flux boundary. Calculations suggest that a seepage face may be responsible for causing the early arrival of the solutes and the overall shape of the BTCs. Our study indicates the potentially important role a seepage face along the soil-well interface may have in modeling water flow and chemical transport to wells in variably saturated, unconfined aquifers. [ABSTRACT FROM AUTHOR]
AB - Copyright of Vadose Zone Journal is the property of American Society of Agronomy and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Groundwater tracers
KW - Aquifers
KW - Benzoic acid
KW - Seepage
KW - Water vapor transport
N1 - Accession Number: 57197517; Yakirevich, A. 1; Gish, T. J. 2; Email Address: Timothy.Gish@ARS.USDA.GOV; Simunek, J. 3; van Genuchten, M. Th. 4; Pachepsky, Y. A. 5; Nicholson, T. J. 6; Cady, R. E. 6; Affiliations: 1: Zuckerberg Inst. for Water Science and Technology, J. Blaustein Inst. for Desert Research, Ben Gurion Univ. of the Negev, Sede Boqer Campus, 84990, Israel; 2: USDA-ARS Hydrology and Remote Sensing Lab., Beltsville, MD 20705; 3: Dep. of Environmental Science, Univ. of California, Riverside, CA 92521; 4: Dep. of Mechanical Engineering, COPPE/LTTC, Federal Univ. of Rio de Janeiro, UFRJ, Rio de Janeiro, 21945-970 RJ, Brazil; 5: USDA-ARS Environmental Microbial and Food Safety Lab., Beltsville, MD 20705; 6: U.S. Nuclear Regulatory Commission, US NRC-ORR, Rockville, MD; Issue Info: Aug2010, Vol. 8 Issue 3, p686; Thesaurus Term: Groundwater tracers; Thesaurus Term: Aquifers; Subject Term: Benzoic acid; Subject Term: Seepage; Subject Term: Water vapor transport; NAICS/Industry Codes: 325190 Other basic organic chemical manufacturing; NAICS/Industry Codes: 325194 Cyclic Crude, Intermediate, and Gum and Wood Chemical Manufacturing; Number of Pages: 1p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Rawl, R. R.
AU - Leggett, R. W.
AU - Cook, J. R.
T1 - Transport of low-level NORM - a case for consistency and practicality.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2010/09//
VL - 21
IS - 3
M3 - Article
SP - 152
EP - 157
PB - Taylor & Francis Ltd
SN - 17465095
AB - In 1996 the International Atomic Energy Agency (IAEA) adopted a system for exemption of lowlevel radioactive material from transport regulations based on the principle that exemption values should be commensurate with the risk posed by the material as represented by the maximum potential radiation dose to individuals. For many naturally occurring radionuclides the derived dose-based, radionuclide-specific exemption concentrations were substantially lower than the previous radionuclide-independent definition of radioactive material (70 Bq g-1) [1900 pCi g-1] due to the stringent dose criterion applied. It was recognised that this would bring large quantities of previously unregulated naturally occurring radioactive material (NORM) handled in industry into the scope of the transport regulations. To minimise the economic impact of the dose-based values, a special provision was included to provide for a 10-fold increase in exemption values for radionuclides in natural material provided the material is not intended to be, and has not previously been, processed for recovery of its radionuclides (the wording regarding previous use was added in 2003). This '10 times' or '10×' provision for certain natural material reflects a second concept underlying IAEA guidance, namely, that a dose criterion may be relaxed within cautious bounds to achieve a balance between practical issues and radiological concerns. On the other hand, restriction of the provision on the basis of past or intended use of the material is inconsistent with the basic principle underlying the Transport Regulations in that there is no risk basis for assigning different exemption values to identical materials on the basis of their past or anticipated use. In fact, the same material can move in and out of the scope of regulatory control as its anticipated use changes. As a practical matter, safety guidelines for potentially hazardous material should be based on measurable properties of the material and not the whims of human intentions. To improve the practicality as well as the consistency of the Transport Regulations as applied to NORM, the 10× provision should be revised to apply to all natural materials, regardless of their intended use. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Transportation
KW - Radioactive substances
KW - Radiation
KW - Radioisotopes
KW - EXEMPTION
KW - NORM
KW - ORES
KW - radium
KW - uranium
KW - International Atomic Energy Agency
N1 - Accession Number: 55031496; Rawl, R. R. 1; Email Address: rawlconsult@comcast.net; Leggett, R. W. 2; Cook, J. R. 3; Affiliations: 1: Consultant, Transportation Security and Safety, Oak Ridge, TN, USA.; 2: Oak Ridge National Laboratory, Oak Ridge, TN, USA.; 3: US Nuclear Regulatory Commission, Rockville, MD, USA.; Issue Info: 2010, Vol. 21 Issue 3, p152; Thesaurus Term: Transportation; Thesaurus Term: Radioactive substances; Thesaurus Term: Radiation; Thesaurus Term: Radioisotopes; Author-Supplied Keyword: EXEMPTION; Author-Supplied Keyword: NORM; Author-Supplied Keyword: ORES; Author-Supplied Keyword: radium; Author-Supplied Keyword: uranium ; Company/Entity: International Atomic Energy Agency; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 488990 Other support activities for transportation; NAICS/Industry Codes: 488999 All Other Support Activities for Transportation; Number of Pages: 6p; Illustrations: 1 Diagram, 4 Charts; Document Type: Article
L3 - 10.1179/174650910X12820499053545
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=55031496&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Bjorkman, G.
T1 - Buckling of fuel rods under inertia loading.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2010/09//
VL - 21
IS - 3
M3 - Article
SP - 165
EP - 168
PB - Taylor & Francis Ltd
SN - 17465095
AB - The buckling analysis of fuel rods during an end drop impact of a spent fuel transportation cask has traditionally been performed to demonstrate the structural integrity of the fuel rod cladding or the integrity of the fuel geometry in criticality evaluations for a cask drop event. The actual calculation of the fuel rod buckling load, however, has been the subject of some controversy, with estimates of the critical buckling load differing by as much as a factor of 5. Typically, in the buckling analysis of a fuel rod, assumptions are made regarding the percentage of fuel mass that is bonded to or that participates with the cladding during the buckling process, with estimates ranging from 0 to 100%. The greater the percentage of fuel mass that is assumed to be bonded to the cladding, the higher the inertia loads on the cladding, and, therefore, the lower the 'g' value at which buckling occurs. However, these solutions do not consider displacement compatibility between the fuel and the cladding during the buckling process. By invoking displacement compatibility between the fuel column and the cladding column, this paper presents an exact solution for the buckling of fuel rods under inertia loading. The results show that the critical inertia load magnitude for the buckling of a fuel rod depends on the weight of the cladding and the total weight of the fuel, regardless of the percentage of fuel mass that is assumed to be attached to or participate with the cladding in the buckling process. Therefore, 100% of the fuel always participates in the buckling of a fuel rod under inertia loading. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear reactors -- Buckling
KW - Nuclear fuel rods
KW - Geometry
KW - Inertia (Mechanics)
KW - Nuclear fuel claddings
KW - Buckling
KW - Concentric columns
KW - Fuel rod
KW - IMPACT
KW - INERTIA LOADING
N1 - Accession Number: 55031494; Bjorkman, G. 1; Email Address: gordon.bjorkman@nrc.gov; Affiliations: 1: U.S. Nuclear Regulatory Commission, Mail stop EBB-3D-02M, Washington, DC 20555-0001.; Issue Info: 2010, Vol. 21 Issue 3, p165; Subject Term: Nuclear reactors -- Buckling; Subject Term: Nuclear fuel rods; Subject Term: Geometry; Subject Term: Inertia (Mechanics); Subject Term: Nuclear fuel claddings; Author-Supplied Keyword: Buckling; Author-Supplied Keyword: Concentric columns; Author-Supplied Keyword: Fuel rod; Author-Supplied Keyword: IMPACT; Author-Supplied Keyword: INERTIA LOADING; Number of Pages: 4p; Illustrations: 2 Diagrams; Document Type: Article
L3 - 10.1179/174650910X12802398378394
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Markley, Christopher T.
AU - Herbert, Bruce E.
T1 - Modeling Phosphate Influence on Arsenate Reduction Kinetics by a Freshwater Cyanobacterium.
JO - Environmental Modeling & Assessment
JF - Environmental Modeling & Assessment
Y1 - 2010/10//
VL - 15
IS - 5
M3 - Article
SP - 361
EP - 368
PB - Springer Science & Business Media B.V.
SN - 14202026
AB - enic speciation in natural surface-water systems can be highly impacted through biological processes that result in non-thermodynamically predicted species to dominate the system. In laboratory experiments, arsenate reduction by a freshwater cyanobacterium exhibited saturation kinetics increasingly inhibited by elevating solution phosphate concentrations. Approximately 100% arsenate reduction occurred by days 4, 7, and 10 in the low (0.35 µm), middle (3.5 µm), and high (35 µm) phosphate treatments, respectively, with maximum arsenate reduction rates ranged from 0.013 μmol As g C day in the high-phosphate treatment to 0.398 μmol As g C day in the low-phosphate treatment. Saturation kinetic models were utilized to evaluate the impact of cell growth and arsenate-phosphate uptake competition on arsenate reduction rates by the cyanobacterium. Results showed reduced arsenicals dominate arsenic speciation once growth reached steady state, indicating reduced arsenicals may dominate natural systems, even when considering conservatively high, abiotic arsenic reoxidation. [ABSTRACT FROM AUTHOR]
AB - Copyright of Environmental Modeling & Assessment is the property of Springer Science & Business Media B.V. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Arsenic
KW - Cyanobacteria
KW - Water -- Purification
KW - Phytoplankton
KW - Biotransformation (Metabolism)
KW - Phosphates
KW - Biotransformation
KW - Kinetics
N1 - Accession Number: 53480227; Markley, Christopher T. 1; Email Address: christopher.markley@nrc.gov; Herbert, Bruce E. 2; Affiliations: 1: US Nuclear Regulatory Commission, MS: EBB 2-BO2, Washington 20555-0001, U.S.A.; 2: Department of Geology and Geophysics, Texas A&M University, College Station 77843-3115, U.S.A.; Issue Info: Oct2010, Vol. 15 Issue 5, p361; Thesaurus Term: Arsenic; Thesaurus Term: Cyanobacteria; Thesaurus Term: Water -- Purification; Thesaurus Term: Phytoplankton; Thesaurus Term: Biotransformation (Metabolism); Thesaurus Term: Phosphates; Author-Supplied Keyword: Biotransformation; Author-Supplied Keyword: Kinetics; NAICS/Industry Codes: 212393 Other Chemical and Fertilizer Mineral Mining; NAICS/Industry Codes: 212398 All other non-metallic mineral mining and quarrying; NAICS/Industry Codes: 221310 Water Supply and Irrigation Systems; Number of Pages: 8p; Illustrations: 2 Charts, 4 Graphs; Document Type: Article
L3 - 10.1007/s10666-009-9212-8
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DP - EBSCOhost
DB - eih
ER -
TY - GEN
AU - Jaczko, Gregory B.
T1 - Nuclear Materials: Current and Future Regulatory Challenges.
JO - Journal of the Institute of Nuclear Materials Management
JF - Journal of the Institute of Nuclear Materials Management
Y1 - 2010///Fall2010
VL - 39
IS - 1
M3 - Speech
SP - 11
EP - 13
PB - Institute of Nuclear Materials Management
SN - 08936188
AB - The article presents a speech by Gregory Jazcko, chairman of the U.S. Nuclear Regulatory Commission, delivered at the Institute of Nuclear Materials Management (INMM) Annual Meeting held in Baltimore, Maryland, July 12, 2010, in which he discussed the NRC's domestic safeguards program which aims to ensure that special nuclear material within the country is not stolen or diverted from civilian facilities for nefarious purposes.
KW - Nuclear engineering
KW - Industrial management
KW - Materials management
KW - Jazcko, Gregory
N1 - Accession Number: 57268316; Jaczko, Gregory B. 1; Affiliations: 1: Chair, U.S. Nuclear Regulatory Commission; Issue Info: Fall2010, Vol. 39 Issue 1, p11; Thesaurus Term: Nuclear engineering; Subject Term: Industrial management; Subject Term: Materials management; NAICS/Industry Codes: 541614 Process, Physical Distribution, and Logistics Consulting Services; People: Jazcko, Gregory; Number of Pages: 3p; Document Type: Speech
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Aldemir, T.
AU - Guarro, S.
AU - Mandelli, D.
AU - Kirschenbaum, J.
AU - Mangan, L.A.
AU - Bucci, P.
AU - Yau, M.
AU - Ekici, E.
AU - Miller, D.W.
AU - Sun, X.
AU - Arndt, S.A.
T1 - Probabilistic risk assessment modeling of digital instrumentation and control systems using two dynamic methodologies
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2010/10//
VL - 95
IS - 10
M3 - Article
SP - 1011
EP - 1039
SN - 09518320
AB - Abstract: The Markov/cell-to-cell mapping technique (CCMT) and the dynamic flowgraph methodology (DFM) are two system logic modeling methodologies that have been proposed to address the dynamic characteristics of digital instrumentation and control (I&C) systems and provide risk-analytical capabilities that supplement those provided by traditional probabilistic risk assessment (PRA) techniques for nuclear power plants. Both methodologies utilize a discrete state, multi-valued logic representation of the digital I&C system. For probabilistic quantification purposes, both techniques require the estimation of the probabilities of basic system failure modes, including digital I&C software failure modes, that appear in the prime implicants identified as contributors to a given system event of interest. As in any other system modeling process, the accuracy and predictive value of the models produced by the two techniques, depend not only on the intrinsic features of the modeling paradigm, but also and to a considerable extent on information and knowledge available to the analyst, concerning the system behavior and operation rules under normal and off-nominal conditions, and the associated controlled/monitored process dynamics. The application of the two methodologies is illustrated using a digital feedwater control system (DFWCS) similar to that of an operating pressurized water reactor. This application was carried out to demonstrate how the use of either technique, or both, can facilitate the updating of an existing nuclear power plant PRA model following an upgrade of the instrumentation and control system from analog to digital. Because of scope limitations, the focus of the demonstration of the methodologies was intentionally limited to aspects of digital I&C system behavior for which probabilistic data was on hand or could be generated within the existing project bounds of time and resources. The data used in the probabilistic quantification portion of the process were gathered partially from fault injection experiments with the DFWCS, separately conducted under conservative assumptions, partially from operating experience, and partially from generic data bases. The purpose of the quantification portion of the process was, purely to demonstrate the PRA-updating use and application of the methodologies, without making any particular claim regarding the specific validity and predictive value of the data utilized to illustrate the quantitative risk calculations produced from the qualitative information analytically generated by the models. A comparison of the results obtained from the Markov/CCMT and DFM regarding the event sequences leading to DFWCS failure modes show qualitative and quantitative consistency for the risk scenarios and sequences under consideration. The study also shows that: (a) the risk significance of the timing of system component failures may depend on factors that include the actual variability of initiating conditions of a dynamic transient, even within the nominal control range and (b) the range of dynamic outcomes may also be dependent on the choice of the assumed basic system-component failure modes included in the models, regardless of whether some of these would or would not be considered to have direct safety implications according to the traditional safety/non-safety equipment classifications. [Copyright &y& Elsevier]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RISK assessment
KW - PROBABILITY theory
KW - DIGITAL instrumentation
KW - CONTROL theory (Mathematics)
KW - MARKOV processes
KW - NUMERICAL analysis
KW - FLOWGRAPHS
KW - NUCLEAR power plants
KW - Cell-to-cell-mapping technique
KW - Digital systems
KW - Dynamic flowgraph methodology
KW - Dynamic methodologies
KW - Markov
KW - PRA
N1 - Accession Number: 51844393; Aldemir, T. 1; Email Address: aldemir.1@osu.edu Guarro, S. 2 Mandelli, D. 1 Kirschenbaum, J. 3 Mangan, L.A. 1 Bucci, P. 3 Yau, M. 2 Ekici, E. 4 Miller, D.W. 1 Sun, X. 1 Arndt, S.A. 5; Affiliation: 1: The Ohio State University, Nuclear Engineering Program, Columbus, OH 43210, USA 2: ASCA, Inc., 1720 S. Catalina Avenue, Suite 220, Redondo Beach, CA 90277-5501, USA 3: The Ohio State University, Department of Computer Science and Engineering, Columbus, OH 43210, USA 4: The Ohio State University, Department of Electrical and Computer Engineering, Columbus, OH 43210, USA 5: U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Source Info: Oct2010, Vol. 95 Issue 10, p1011; Subject Term: RISK assessment; Subject Term: PROBABILITY theory; Subject Term: DIGITAL instrumentation; Subject Term: CONTROL theory (Mathematics); Subject Term: MARKOV processes; Subject Term: NUMERICAL analysis; Subject Term: FLOWGRAPHS; Subject Term: NUCLEAR power plants; Author-Supplied Keyword: Cell-to-cell-mapping technique; Author-Supplied Keyword: Digital systems; Author-Supplied Keyword: Dynamic flowgraph methodology; Author-Supplied Keyword: Dynamic methodologies; Author-Supplied Keyword: Markov; Author-Supplied Keyword: PRA; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 29p; Document Type: Article
L3 - 10.1016/j.ress.2010.04.011
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Young, Ann Marshall
T1 - Ex Parte communications and the exclusive record Provision of the 2010 MSAPA.
JO - Administrative & Regulatory Law News
JF - Administrative & Regulatory Law News
Y1 - 2011///Winter2011
VL - 36
IS - 2
M3 - Article
SP - 8
EP - 9
SN - 15441547
AB - In this article, the author discusses the ex-parte communications and the exclusive record provision of the 2010 Revised Model State Administrative Procedure Act (2010 MSAPA). This mandates that the hearing record constitutes the exclusive basis for agency action in a contested case. In her view, if this were to be permitted, proceedings could not be held out as respecting the rights of the parties to respond to any evidence or as reaching decisions based solely on the record.
KW - EX parte communications
KW - PROCEDURE (Law)
KW - ADMINISTRATIVE procedure
KW - ACTIONS & defenses (Law)
KW - CRIMINAL procedure
KW - EVIDENCE
N1 - Accession Number: 78113023; Young, Ann Marshall 1; Affiliation: 1: Administrative Judge, U.S. Nuclear Regulatory Commission; Source Info: Winter2011, Vol. 36 Issue 2, p8; Subject Term: EX parte communications; Subject Term: PROCEDURE (Law); Subject Term: ADMINISTRATIVE procedure; Subject Term: ACTIONS & defenses (Law); Subject Term: CRIMINAL procedure; Subject Term: EVIDENCE; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Lyons, Peter B.
T1 - SIXTH WARREN K. SINCLAIR KEYNOTE ADDRESS: THE ROLE OF A STRONG REGULATOR IN SAFE AND SECURE NUCLEAR ENERGY.
JO - Health Physics
JF - Health Physics
Y1 - 2011/01//
VL - 100
IS - 1
M3 - Speech
SP - 5
EP - 11
SN - 00179078
AB - The article presents the keynote address delivered by Nuclear Regulatory Commissioner Peter B. Lyons titled "The Role of a Strong Regulator in Safe and Secure Nuclear Energy" at the 2009 annual meeting of the National Council on Radiation Protection and Measurements (NCRP). He reviewed nuclear regulation history, the current licensing process and status of applications and the industry's challenges including modular construction and digital controls. Lyons also discussed the crucial area in safety culture and its importance.
KW - Automation
KW - Nuclear facilities
KW - Radiation -- Safety measures
KW - National Council on Radiation Protection and Measurements
KW - nuclear power industry
KW - nuclear workers
KW - regulations
KW - Lyons, Peter B.
N1 - Accession Number: 57524084; Lyons, Peter B. 1; Email Address: peter.lyons@hg.doe.gov; Affiliations: 1: Past Honorable Commissioner of U.S. Nuclear Regulatory Commission, Department of Energy, Office of Nuclear Energy; Washington, DC 20585-0001; Issue Info: Jan2011, Vol. 100 Issue 1, p5; Thesaurus Term: Automation; Thesaurus Term: Nuclear facilities; Subject Term: Radiation -- Safety measures; Author-Supplied Keyword: National Council on Radiation Protection and Measurements; Author-Supplied Keyword: nuclear power industry; Author-Supplied Keyword: nuclear workers; Author-Supplied Keyword: regulations; People: Lyons, Peter B.; Number of Pages: 7p; Document Type: Speech
L3 - 10.1097/HP.0b013e3181f6e76e
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=57524084&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Cheung, F.B.
AU - Bajorek, S.M.
T1 - Dynamics of droplet breakup through a grid spacer in a rod bundle
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2011/01//
VL - 241
IS - 1
M3 - Article
SP - 236
EP - 244
SN - 00295493
AB - Abstract: The dynamics of droplet breakup associated with the flow of a dispersed two-phase mixture through a rod bundle grid spacer during a reflood transient in a pressurized water reactor is studied theoretically. By considering the conservation of liquid mass and the kinetic as well as the surface energies of the droplets, an expression is derived for the ratio of the Sauter mean diameters of the droplets downstream and upstream of the grid. It is found that the Sauter mean diameter could decrease appreciably as a result of the shattering of the droplets when flowing through the grid spacer, thus increasing the interfacial heat transfer surface area. The decrease in the droplet size is dependent upon the Weber number of the incoming droplets, the blockage ratio of the grid spacer, and the fraction of the kinetic energy of the incoming droplets required to convert to the surface energy of the newly generated droplets during the breakup process. Comparisons of the theoretical results are made with the experimental data obtained at the rod bundle heat transfer test facility as well as with other relevant data in the literature and found to be good. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - HEAT transfer
KW - SURFACE energy
KW - DROPS
KW - TWO-phase flow
KW - EXPERIMENTS
KW - CHEMICAL processes
N1 - Accession Number: 57080179; Cheung, F.B. 1; Email Address: fxc4@psu.edu Bajorek, S.M. 2; Affiliation: 1: Department of Mechanical & Nuclear Engineering, Pennsylvania State University, University Park, PA 16802, United States 2: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,Washington, DC 20555, United States; Source Info: Jan2011, Vol. 241 Issue 1, p236; Subject Term: HEAT transfer; Subject Term: SURFACE energy; Subject Term: DROPS; Subject Term: TWO-phase flow; Subject Term: EXPERIMENTS; Subject Term: CHEMICAL processes; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.nucengdes.2010.10.017
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Chopra, O.K.
AU - Rao, A.S.
T1 - A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2011/02/28/
VL - 409
IS - 3
M3 - Article
SP - 235
EP - 256
SN - 00223115
AB - Abstract: Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to neutron irradiation for extended periods changes the microstructure (radiation hardening) and microchemistry (radiation-induced segregation) of these steels, and degrades their fracture properties. Irradiation-assisted stress corrosion cracking (IASCC) is another degradation process that affects LWR internal components exposed to neutron radiation. The existing data on irradiated austenitic SSs were reviewed to evaluate the effects of key parameters such as material composition, irradiation dose, and water chemistry on IASCC susceptibility and crack growth rates of these materials in LWR environments. The significance of microstructural and microchemistry changes in the material on IASCC susceptibility is also discussed. The results are used to determine (a) the threshold fluence for IASCC and (b) the disposition curves for cyclic and IASCC growth rates for irradiated SSs in LWR environments. [Copyright &y& Elsevier]
AB - Copyright of Journal of Nuclear Materials is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - LIGHT water reactors
KW - IRRADIATION
KW - AUSTENITIC stainless steel
KW - NUCLEAR pressure vessels
KW - MICROSTRUCTURE
KW - MICROCHEMISTRY
KW - STRESS corrosion cracking
KW - FRACTURE mechanics
N1 - Accession Number: 58099343; Chopra, O.K. 1; Email Address: okc@anl.gov Rao, A.S. 2; Affiliation: 1: Environmental Science Division, Argonne National Laboratory, Argonne, IL 60439, United States 2: Division of Engineering, US Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Feb2011, Vol. 409 Issue 3, p235; Subject Term: LIGHT water reactors; Subject Term: IRRADIATION; Subject Term: AUSTENITIC stainless steel; Subject Term: NUCLEAR pressure vessels; Subject Term: MICROSTRUCTURE; Subject Term: MICROCHEMISTRY; Subject Term: STRESS corrosion cracking; Subject Term: FRACTURE mechanics; NAICS/Industry Codes: 334517 Irradiation Apparatus Manufacturing; Number of Pages: 22p; Document Type: Article
L3 - 10.1016/j.jnucmat.2010.12.001
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - CROSTON, SEAN
T1 - RECENT DEVELOPMENTS.
JO - Administrative Law Review
JF - Administrative Law Review
Y1 - 2011///Spring2011
VL - 63
IS - 2
M3 - Article
SP - 381
EP - 399
SN - 00018368
AB - The article focuses on the guidance documents, published by federal agencies in the U.S. It informs about various formats of guidance documents including video and audio tapes and interactive web-based software. It also informs about recommendations made by the Administrative Conference of the U.S. (ACUS) in 1992 regarding guidance documents. It further describes several challenges faced by petitioners with respect to their standing in the court, final agency action, the ripeness and timing.
KW - GOVERNMENT agencies
KW - LEGAL documents
KW - RIPENESS (Law)
KW - LOCUS standi
KW - UNITED States
KW - ADMINISTRATIVE Conference of the United States
N1 - Accession Number: 63308405; CROSTON, SEAN 1; Affiliations: 1: Attorney at the U.S. Nuclear Regulatory Commission; Issue Info: Spring2011, Vol. 63 Issue 2, p381; Thesaurus Term: GOVERNMENT agencies; Subject Term: LEGAL documents; Subject Term: RIPENESS (Law); Subject Term: LOCUS standi; Subject: UNITED States ; Company/Entity: ADMINISTRATIVE Conference of the United States; Number of Pages: 19p; Document Type: Article; Full Text Word Count: 7395
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Talley, Justin D.
AU - Kim, Seungjin
AU - Mahaffy, John
AU - Bajorek, Stephen M.
AU - Tien, Kirk
T1 - Implementation and evaluation of one-group interfacial area transport equation in TRACE
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2011/03//
VL - 241
IS - 3
M3 - Article
SP - 865
EP - 873
SN - 00295493
AB - Abstract: The present study implements the one-dimensional interfacial area transport equation into the TRACE code, being developed by the U.S. Nuclear Regulatory Commission. The interfacial area transport equation replaces the conventional flow regime dependent correlations and the regime transition criteria for furnishing the interfacial area concentration in the two-fluid model. This approach allows dynamic tracking of the interfacial area concentration by mechanistically modeling bubble coalescence and disintegration mechanisms. Thus, it eliminates potential artificial bifurcations or numerical oscillations stemming from the use of conventional static correlations. To implement the interfacial area transport equation, a three-field version of TRACE is utilized, which is capable of tracking both the continuous liquid and gas fields as well as a dispersed gas field. To demonstrate the feasibility of the present approach, the steady-state one-group interfacial area transport equation applicable to adiabatic air–water bubbly two-phase flow is first tested in the present study. Data obtained in 18 different flow conditions from two vertical co-current upward air–water bubbly two-phase flow experiments performed in round pipes (25.4mm and 48.3mm) are used to help evaluate the implementation. Results obtained from TRACE with the interfacial area transport equation (TRACE-T) and those from TRACE without the transport equation (TRACE-NT) are compared to demonstrate the enhancement in prediction accuracy. The predictions made by TRACE-T agree well with the data with an average percent difference of approximately ±8%. It is also evident from the results that while TRACE-T accounts for dynamic interaction of bubbles along the flow field, the predictions made by TRACE-NT are attributed primarily to the pressure change. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - PARTIAL differential equations
KW - TRANSPORT theory (Mathematics)
KW - COMPUTER software
KW - INTERFACES (Physical sciences)
KW - TWO-phase flow
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 59329212; Talley, Justin D. 1 Kim, Seungjin 1; Email Address: skim@psu.edu Mahaffy, John 1 Bajorek, Stephen M. 2 Tien, Kirk 2; Affiliation: 1: Department of Mechanical and Nuclear Engineering, 230 Reber Building, The Pennsylvania State University, University Park, PA 16802, United States 2: The U.S. Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Mar2011, Vol. 241 Issue 3, p865; Subject Term: PARTIAL differential equations; Subject Term: TRANSPORT theory (Mathematics); Subject Term: COMPUTER software; Subject Term: INTERFACES (Physical sciences); Subject Term: TWO-phase flow; Subject Term: UNITED States; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 511211 Software publishers (except video game publishers); NAICS/Industry Codes: 443144 Computer and software stores; NAICS/Industry Codes: 423430 Computer and Computer Peripheral Equipment and Software Merchant Wholesalers; NAICS/Industry Codes: 417310 Computer, computer peripheral and pre-packaged software merchant wholesalers; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.nucengdes.2010.12.008
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=59329212&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Mintz, T. S.
AU - Adams, G.
AU - Necsoiu, M.
AU - Mancillas, J.
AU - Bajwa, C.
AU - Easton, E.
T1 - Analyses of historical rail accidents to identify accident parameters impacting transport of spent nuclear fuel.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2011/03//
VL - 22
IS - 1
M3 - Article
SP - 20
EP - 26
PB - Taylor & Francis Ltd
SN - 17465095
AB -
As a regulatory authority for the transportation of spent nuclear fuel (SNF) in the USA, the Nuclear Regulatory Commission requires that SNF transportation packages be designed to endure a fully engulfing fire with an average temperature of 800°C (1475°F) for 30 min, as prescribed in Title 10 of the Code of Federal Regulations Part 71. The work described in this paper was performed to support the Nuclear Regulatory Commission in determining the types of accident parameters that could produce a severe fire with the potential to fully engulf an SNF transportation package. This paper describes the process that was used to characterise the important features of rail accidents that would potentially lead to an SNF transport package being involved in a severe fire. Historical rail accidents involving all hazardous material (i.e. all nine classes of hazardous material) and long duration fires in the USA have been analysed using data from the Federal Railroad Administration and the Pipeline and Hazardous Materials Safety Administration. Parameters that were evaluated from these data include, but were not limited to, class of track where the accident occurred, class of hazardous material that was being transported and number of railcars involved in the fire. The data analysis revealed that in the past 34 years of rail transport, roughly 1800 accidents have led to the release of hazardous materials, resulting in a frequency of roughly one accident per 10 million freight train miles (Because all of the data were obtained in the USA, which still uses distance measured in miles, and the primary source is an extensive database from the Federal Railroad Administration that is also in reported in miles, the data in this paper are reported in miles rather than kilometres. Conversion of miles to kilometres is by multiplication of 1·61.). In the last 12 years, there have only been 20 accidents involving multiple car hazardous material releases that led to a fire. This results in an accident rate of 0·003 accidents per million freight train miles that involved multiple car releases and a fire. Out of all the accidents analysed, only one involved a railcar carrying class 7 (i.e. radioactive) hazardous material. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear fuels
KW - Radioactive substances -- Safety regulations
KW - Hazardous substances -- Accidents -- Investigation
KW - United States
KW - Accident
KW - Fire
KW - Railroad
KW - Spent nuclear fuel
KW - Transportation
KW - U.S. Nuclear Regulatory Commission
KW - United States. Federal Railroad Administration
N1 - Accession Number: 59763511; Mintz, T. S. 1; Adams, G. 1; Necsoiu, M. 1; Mancillas, J. 1; Bajwa, C. 2; Email Address: Chris.Bajwa@nrc.gov; Easton, E. 2; Affiliations: 1: Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, TX, USA; 2: US Nuclear Regulatory Commission, Washington, DC, USA; Issue Info: 2011, Vol. 22 Issue 1, p20; Thesaurus Term: Nuclear fuels; Thesaurus Term: Radioactive substances -- Safety regulations; Subject Term: Hazardous substances -- Accidents -- Investigation; Subject: United States; Author-Supplied Keyword: Accident; Author-Supplied Keyword: Fire; Author-Supplied Keyword: Railroad; Author-Supplied Keyword: Spent nuclear fuel; Author-Supplied Keyword: Transportation ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: United States. Federal Railroad Administration; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 7p; Illustrations: 5 Charts, 6 Graphs; Document Type: Article
L3 - 10.1179/1746510910Y.0000000009
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=59763511&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Burbank, Malcolm B.
AU - Weaver, Thomas J.
AU - Green, Tonia L.
AU - Williams, Barbara C.
AU - Crawford, Ronald L.
T1 - Precipitation of Calcite by Indigenous Microorganisms to Strengthen Liquefiable Soils.
JO - Geomicrobiology Journal
JF - Geomicrobiology Journal
Y1 - 2011/05//
VL - 28
IS - 4
M3 - Article
SP - 301
EP - 312
PB - Taylor & Francis Ltd
SN - 01490451
AB - Enrichments for indigenous microorganisms capable of hydrolyzing urea in the presence of CaCl2 were performed on potentially liquefiable saturated soils in both the laboratory and in situ. Following enrichment, treatment of soils with nutrients, CaCl2 and urea resulted in significant in situ precipitation of calcite, even at depth, by indigenous microorganisms. The biomineralized soils showed properties that indicate calcite precipitation increased their resistance to seismic-induced liquefaction. [ABSTRACT FROM AUTHOR]
AB - Copyright of Geomicrobiology Journal is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - CALCITE
KW - BIOMINERALIZATION
KW - SOIL sampling
KW - WATER sampling
KW - CALCIUM carbonate
KW - POLYMERASE chain reaction
KW - X-ray diffraction
KW - bio-soil
KW - bio-stimulation
KW - biomineralization
KW - calcite
KW - liquefaction
N1 - Accession Number: 60899985; Burbank, Malcolm B. 1 Weaver, Thomas J. 2; Email Address: thomas.weaver@nrc.gov Green, Tonia L. 1 Williams, Barbara C. 3 Crawford, Ronald L. 1,4; Affiliation: 1: Environmental Biotechnology Institute, University of Idaho, Moscow, Idaho, USA 2: U.S. Nuclear Regulatory Commission, Washington, District of Columbia, USA 3: Department of Biological and Agricultural Engineering, University of Idaho, Moscow, Idaho, USA 4: Department of Microbiology, Molecular Biology and Biochemistry, University of Idaho, Moscow, Idaho, USA; Source Info: 2011, Vol. 28 Issue 4, p301; Subject Term: CALCITE; Subject Term: BIOMINERALIZATION; Subject Term: SOIL sampling; Subject Term: WATER sampling; Subject Term: CALCIUM carbonate; Subject Term: POLYMERASE chain reaction; Subject Term: X-ray diffraction; Author-Supplied Keyword: bio-soil; Author-Supplied Keyword: bio-stimulation; Author-Supplied Keyword: biomineralization; Author-Supplied Keyword: calcite; Author-Supplied Keyword: liquefaction; NAICS/Industry Codes: 212399 All Other Nonmetallic Mineral Mining; NAICS/Industry Codes: 212398 All other non-metallic mineral mining and quarrying; Number of Pages: 12p; Illustrations: 1 Black and White Photograph, 4 Charts, 6 Graphs; Document Type: Article
L3 - 10.1080/01490451.2010.499929
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Shim, Do-Jun
AU - Wilkowski, Gery M.
AU - Rudland, David L.
T1 - Determination of the elastic-plastic fracture mechanics Z-factor for alloy 182 weld metal flaws
JO - International Journal of Pressure Vessels & Piping
JF - International Journal of Pressure Vessels & Piping
Y1 - 2011/05//
VL - 88
IS - 5-7
M3 - Article
SP - 231
EP - 238
SN - 03080161
AB - Abstract: One of the ways that the ASME Section XI code incorporates elastic-plastic fracture mechanics (EPFM) in the Section XI Appendix C flaw evaluation procedures for circumferential cracks is through a parameter called Z-factor. This parameter allows the simpler limit-load (or Net-Section-Collapse) solutions to be used with a multiplier from EPFM analyses. This paper shows how 3-D finite element (FE) analyses were employed to investigate the sensitivity of the crack-driving force as a function of crack location (i.e., crack in the center of weld, or closer to the stainless or low alloy steel sides) in an Alloy 182 dissimilar metal weld (DMW), and how an appropriate (or equivalent) stress-strain curve was determined for use in the J-estimation schemes. The J-estimation schemes are then used to cover a wider range of variables, i.e., pipe diameters, cracks lengths, and also incorporate crack growth by ductile tearing. The Z-factor equations as a function of pipe diameter were calculated using the LBB.ENG2 J-estimation scheme along with the most conservative equivalent stress-strain curve from the FE analyses. The proposed Z-factor approach was then validated against an Alloy 182 DMW full-scale pipe test that had a circumferential through-wall crack in the fusion line. The predicted EPFM maximum load showed excellent agreement with the experimental result. Furthermore, it was shown that the proposed Z-factor equation is not sensitive to the location of the crack. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Pressure Vessels & Piping is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - ELASTOPLASTICITY
KW - FRACTURE mechanics
KW - WELDING
KW - R-curves
KW - FINITE element method
KW - ALLOYS
KW - LOADS (Mechanics)
KW - STRESS-strain curves
KW - Alloy 182
KW - Circumferential through-wall crack
KW - Dissimilar metal weld
KW - EPFM
KW - J-resistance curve
KW - Pipe
KW - Z-Factor
N1 - Accession Number: 62557001; Shim, Do-Jun 1; Email Address: djshim@emc-sq.com Wilkowski, Gery M. 1 Rudland, David L. 2; Affiliation: 1: Engineering Mechanics Corporation of Columbus, 3518 Riverside Drive, Suite 202, Columbus, Ohio 43221, USA 2: U.S. Nuclear Regulatory Commission, Mail Stop: T10-M05, Washington DC 20555, USA; Source Info: May2011, Vol. 88 Issue 5-7, p231; Subject Term: ELASTOPLASTICITY; Subject Term: FRACTURE mechanics; Subject Term: WELDING; Subject Term: R-curves; Subject Term: FINITE element method; Subject Term: ALLOYS; Subject Term: LOADS (Mechanics); Subject Term: STRESS-strain curves; Author-Supplied Keyword: Alloy 182; Author-Supplied Keyword: Circumferential through-wall crack; Author-Supplied Keyword: Dissimilar metal weld; Author-Supplied Keyword: EPFM; Author-Supplied Keyword: J-resistance curve; Author-Supplied Keyword: Pipe; Author-Supplied Keyword: Z-Factor; NAICS/Industry Codes: 238190 Other Foundation, Structure, and Building Exterior Contractors; Number of Pages: 8p; Document Type: Article
L3 - 10.1016/j.ijpvp.2011.05.001
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=62557001&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Chopra, O.K.
AU - Rao, A.S.
T1 - A review of irradiation effects on LWR core internal materials – Neutron embrittlement
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2011/05//
VL - 412
IS - 1
M3 - Article
SP - 195
EP - 208
SN - 00223115
AB - Abstract: Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to neutron irradiation for extended periods not only changes the microstructure and microchemistry of these steels, but also degrades their fracture properties. The existing data on irradiated austenitic SSs are reviewed to determine the effects of key parameters such as material type and condition and irradiation temperature, dose, and dose rate on neutron embrittlement. Differences in the radiation-induced degradation of fracture properties between LWR and fast-reactor irradiations are also discussed. The results are used to (a) define a threshold fluence above which irradiation effects on fracture toughness of the material are significant, (b) evaluate the potential of neutron embrittlement under LWR operating conditions, and (c) assess the potential effects of voids on fracture toughness. [Copyright &y& Elsevier]
AB - Copyright of Journal of Nuclear Materials is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - LIGHT water reactors
KW - NUCLEAR reactors -- Cores
KW - NEUTRON irradiation
KW - EMBRITTLEMENT
KW - AUSTENITIC stainless steel
KW - PRESSURE vessels
KW - FRACTURE mechanics
N1 - Accession Number: 60162947; Chopra, O.K. 1; Email Address: okc@anl.gov Rao, A.S. 2; Affiliation: 1: Environmental Science Division, Argonne National Laboratory, Argonne, IL 60439, United States 2: Division of Engineering, US Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: May2011, Vol. 412 Issue 1, p195; Subject Term: LIGHT water reactors; Subject Term: NUCLEAR reactors -- Cores; Subject Term: NEUTRON irradiation; Subject Term: EMBRITTLEMENT; Subject Term: AUSTENITIC stainless steel; Subject Term: PRESSURE vessels; Subject Term: FRACTURE mechanics; Number of Pages: 14p; Document Type: Article
L3 - 10.1016/j.jnucmat.2011.02.059
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=60162947&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Bahn, Chi Bum
AU - Kasza, Ken E.
AU - Shack, William J.
AU - Natesan, Ken
AU - Klein, Paul
T1 - Evaluation of precipitates used in strainer head loss testing: Part III. Long-term aluminum hydroxide precipitation tests in borated water
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2011/05//
VL - 241
IS - 5
M3 - Article
SP - 1914
EP - 1925
SN - 00295493
AB - Abstract: Long-term aluminum (Al) hydroxide precipitation tests were conducted in slightly alkaline solutions containing 2500ppm boron. The solution temperature was cycled to obtain a temperature history more representative of emergency core cooling system temperatures after a loss-of-coolant accident. The observed Al precipitation boundary was close to predicted results for amorphous precipitates, which are higher than the solubility expected for crystalline forms. Bench-scale and loop head loss test results under various conditions were successfully combined into single map in a temperature – ‘pH+p[Al]T’ domain, which yielded two bounding lines for Al hydroxide solubility in borated alkaline water that depend on whether or not loop head loss tests with Al alloy coupons are included. Precipitates were observed to form either as fine, cloudy suspensions, which showed very little tendency to settle, or as flocculated precipitates. The flocculation tendency of the precipitates can be qualitatively explained by a colloid stability theory or a phase diagram for protein solutions. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - PRECIPITATION (Chemistry)
KW - STRAINS & stresses (Mechanics)
KW - ALUMINUM hydroxide
KW - WATER
KW - SOLUTION (Chemistry)
KW - BORON
KW - TEMPERATURE effect
KW - PREDICTION models
KW - AMORPHOUS substances
KW - SOLUBILITY
N1 - Accession Number: 60115146; Bahn, Chi Bum 1; Email Address: tochibum@gmail.com Kasza, Ken E. 1 Shack, William J. 1 Natesan, Ken 1 Klein, Paul 2; Affiliation: 1: Argonne National Laboratory, Lemont, IL 60439, USA 2: The United States Nuclear Regulatory Commission, Rockville, MD 20852, USA; Source Info: May2011, Vol. 241 Issue 5, p1914; Subject Term: PRECIPITATION (Chemistry); Subject Term: STRAINS & stresses (Mechanics); Subject Term: ALUMINUM hydroxide; Subject Term: WATER; Subject Term: SOLUTION (Chemistry); Subject Term: BORON; Subject Term: TEMPERATURE effect; Subject Term: PREDICTION models; Subject Term: AMORPHOUS substances; Subject Term: SOLUBILITY; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 12p; Document Type: Article
L3 - 10.1016/j.nucengdes.2010.10.013
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=60115146&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Bahn, Chi Bum
AU - Kasza, Ken E.
AU - Shack, William J.
AU - Natesan, Ken
AU - Klein, Paul
T1 - Evaluation of precipitates used in strainer head loss testing: Part II. Precipitates by in situ aluminum alloy corrosion
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2011/05//
VL - 241
IS - 5
M3 - Article
SP - 1926
EP - 1936
SN - 00295493
AB - Abstract: Vertical loop head loss tests were performed with 6061 and 1100 aluminum (Al) alloy plates immersed in borated solution at pH=9.3 at room temperature and 60°C. The results suggest that the potential for corrosion of an Al alloy to result in increased head loss across a glass fiber bed may depend on its microstructure, i.e., the size distribution and number density of intermetallic particles that are present in Al matrix and FeSiAl ternary compounds, as well as its Al release rate. Per unit mass of Al removed from solution, the WCAP-16530 aluminum hydroxide (Al(OH)3) surrogate was more effective in increasing head loss than the Al(OH)3 precipitates formed in situ by corrosion of Al alloy. However, in choosing a representative amount of surrogate for plant specific testing, consideration should be given to the potential for additional head losses due to intermetallic particles and the apparent reduction in the effective solubility of Al(OH)3 when intermetallic particles are present. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - PRECIPITATION (Chemistry)
KW - STRAINS & stresses (Mechanics)
KW - ALUMINUM alloys
KW - CORROSION & anti-corrosives
KW - TEMPERATURE effect
KW - INTERMETALLIC compounds
KW - ALUMINUM hydroxide
KW - SOLUBILITY
KW - PARTICLE size distribution
N1 - Accession Number: 60115165; Bahn, Chi Bum 1; Email Address: tochibum@gmail.com Kasza, Ken E. 1 Shack, William J. 1 Natesan, Ken 1 Klein, Paul 2; Affiliation: 1: Argonne National Laboratory, Lemont, IL 60439, USA 2: The United States Nuclear Regulatory Commission, Rockville, MD 20852, USA; Source Info: May2011, Vol. 241 Issue 5, p1926; Subject Term: PRECIPITATION (Chemistry); Subject Term: STRAINS & stresses (Mechanics); Subject Term: ALUMINUM alloys; Subject Term: CORROSION & anti-corrosives; Subject Term: TEMPERATURE effect; Subject Term: INTERMETALLIC compounds; Subject Term: ALUMINUM hydroxide; Subject Term: SOLUBILITY; Subject Term: PARTICLE size distribution; NAICS/Industry Codes: 331313 Alumina Refining and Primary Aluminum Production; NAICS/Industry Codes: 331314 Secondary Smelting and Alloying of Aluminum; NAICS/Industry Codes: 331317 Aluminum rolling, drawing, extruding and alloying; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.nucengdes.2011.01.004
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=60115165&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Thorp, John
T1 - Fukushima Sequence of Events & Seismic Attributes.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2011/05//May/Jun2011
VL - 29
IS - 3
M3 - Article
SP - 36
EP - 37
PB - Presidents & Prime Ministers
SN - 08922055
AB - The article presents an excerpt of the official transcript of proceedings of U.S. Nuclear Regulatory Commission's presentation before the Advisory Committee of Nuclear Safeguards on Fukushima Daiichi and other nuclear power plants in Japan. It describes the events that transpired during an earthquake in Japan which affected four nuclear power plants. It details the seismic attributes of the earthquake which was reportedly a magnitude nine of the Richter scale.
KW - Earthquakes
KW - Nuclear power plants
KW - Nuclear accidents
KW - Environmental disasters
KW - Trial transcripts
KW - Fukushima Nuclear Accident, Fukushima, Japan, 2011
KW - U.S. Nuclear Regulatory Commission
KW - Fukushima Daiichi Nuclear Power Plant (Japan)
N1 - Accession Number: 62807443; Thorp, John 1; Affiliations: 1: Chief of the Operating Experience Branch, Office of Nuclear Reactor Regulation, U.S. NRC.; Issue Info: May/Jun2011, Vol. 29 Issue 3, p36; Thesaurus Term: Earthquakes; Thesaurus Term: Nuclear power plants; Thesaurus Term: Nuclear accidents; Thesaurus Term: Environmental disasters; Subject Term: Trial transcripts; Subject Term: Fukushima Nuclear Accident, Fukushima, Japan, 2011 ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: Fukushima Daiichi Nuclear Power Plant (Japan); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Eyl, Nancy
AU - Grodin, Maryann Lawrence
AU - Keith, Alexandra
T1 - Growing Old Together: Inspector General and Ethics Counsel -- Changing Environments and Challenges. (Cover story)
JO - Federal Ethics Report
JF - Federal Ethics Report
Y1 - 2011/06//
VL - 18
IS - 6
M3 - Article
SP - 1
EP - 12
SN - 1080210X
AB - The article discusses the roles and the development of Inspector General (IG) Counsels and Designated Agency Ethics Officials (DAEO) in the U.S. It reports how provisions were enacted to allow IGs to function independently without interference from Counsels and management. Mentioned is the DAEO's growth to include new authority, notwithstanding its special relationship with the IG regarding ethics investigation and advice. Best case practices of the agencies' combined efforts are presented as important contributions to government integrity.
KW - ETHICS
KW - GOVERNMENTAL investigations
KW - BEST practices
KW - UNITED States
KW - UNITED States. War Dept. Inspector General's Office
N1 - Accession Number: 61253125; Eyl, Nancy 1 Grodin, Maryann Lawrence 2 Keith, Alexandra 3; Affiliation: 1: Senior Attorney, Office of General Counsel, Special Inspector General for Iraq Reconstruction (SIGIR) 2: General Counsel, Inspector General, U.S. Nuclear Regulatory Commission 3: Assistant Counsel to the Inspector General, Department of Homeland Security; Source Info: Jun2011, Vol. 18 Issue 6, p1; Subject Term: ETHICS; Subject Term: GOVERNMENTAL investigations; Subject Term: BEST practices; Subject Term: UNITED States; Company/Entity: UNITED States. War Dept. Inspector General's Office; Number of Pages: 12p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Tracy, G.
AU - Jackson, D.
T1 - Regulatory oversight of licensee use of contractors.
JO - NEA News (OECD Nuclear Energy Agency)
JF - NEA News (OECD Nuclear Energy Agency)
Y1 - 2011/06//
VL - 29
IS - 1
M3 - Article
SP - 13
EP - 15
SN - 16059581
AB - The article discusses the increased licensees' use of contracted services brought about by the changes in the nuclear industry sector. It cites that regulators must also find ways to provide assurance that licensees fulfill their responsibility for the facility's safety. It offers guidelines on the elements of the licensee's and regulator's programmes. It is concluded that increased international coordination among regulatory bodies will better regulatory efficiency in all countries.
KW - LICENSES
KW - NUCLEAR industry
KW - INDUSTRIAL safety
KW - ENERGY industries
KW - NUCLEAR energy
N1 - Accession Number: 74564438; Tracy, G. 1; Email Address: glenn.tracy@nrc.gov Jackson, D. 2; Email Address: diane.jackson@oecd.org; Affiliation: 1: US Nuclear Regulatory Commission 2: Nuclear Safety Division, NEA; Source Info: 2011, Vol. 29 Issue 1, p13; Subject Term: LICENSES; Subject Term: NUCLEAR industry; Subject Term: INDUSTRIAL safety; Subject Term: ENERGY industries; Subject Term: NUCLEAR energy; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 3p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Prokofiev, Iouri
AU - Cumblidge, Stephen E.
AU - Doctor, Steven R.
T1 - INSPECTION OF NICKEL ALLOY WELDS: RESULTS FROM FIVE-YEAR INTERNATIONAL PROGRAM.
JO - AIP Conference Proceedings
JF - AIP Conference Proceedings
Y1 - 2011/06/23/
VL - 1335
IS - 1
M3 - Article
SP - 1055
EP - 1062
PB - American Institute of Physics
SN - 0094243X
AB - The U.S. Nuclear Regulatory Commission established and coordinated the international Program for the Inspection of Nickel alloy Components (PINC). The goal of PINC was to evaluate the capabilities of various nondestructive examination (NDE) techniques to detect and characterize primary water stress corrosion cracking (PWSCC) in dissimilar metal welds. Round-robin results showed that a combination of conventional and phased-array ultrasound provide the highest performance for flaw detection and depth sizing in dissimilar metal piping welds. The effective detection of flaws in bottom-mounted instrumentation penetrations by eddy current and ultrasound shows that it may be possible to reliably inspect these components in the field. [ABSTRACT FROM AUTHOR]
AB - Copyright of AIP Conference Proceedings is the property of American Institute of Physics and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NICKEL alloys -- Welding
KW - NONDESTRUCTIVE testing
KW - WATER
KW - STRESS corrosion cracking
KW - ANTENNA arrays
KW - PENETRATION mechanics
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 61468611; Prokofiev, Iouri 1 Cumblidge, Stephen E. 1 Doctor, Steven R. 2; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, DC 2: Pacific Northwest National Laboratory, Richland, WA; Source Info: 6/23/2011, Vol. 1335 Issue 1, p1055; Subject Term: NICKEL alloys -- Welding; Subject Term: NONDESTRUCTIVE testing; Subject Term: WATER; Subject Term: STRESS corrosion cracking; Subject Term: ANTENNA arrays; Subject Term: PENETRATION mechanics; Subject Term: UNITED States; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 541380 Testing Laboratories; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 8p; Illustrations: 3 Charts, 3 Graphs; Document Type: Article
L3 - 10.1063/1.3592053
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - OSTENDORFF, WILLIAM C.
T1 - Small modular reactors.
JO - Issues in Science & Technology
JF - Issues in Science & Technology
Y1 - 2011///Fall2011
VL - 28
IS - 1
M3 - Letter
SP - 6
EP - 8
PB - University of Texas at Dallas
SN - 07485492
AB - A letter to the editor is presented in response to the article "The Little Reactor That Could," by Ross Carper and Sonja Schmid in the 2011 issue.
KW - LETTERS to the editor
KW - NUCLEAR reactors
N1 - Accession Number: 66736309; OSTENDORFF, WILLIAM C. 1; Affiliation: 1: Commissioner U.S. Nuclear Regulatory Commission Washington, DC; Source Info: Fall2011, Vol. 28 Issue 1, p6; Subject Term: LETTERS to the editor; Subject Term: NUCLEAR reactors; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 3p; Illustrations: 1 Color Photograph; Document Type: Letter
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Pelton, David L.
T1 - Draft License Renewal Interim Staff Guidance LR-ISG-2011-02; Aging Management Program for Steam Generators.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/09/30/
VL - 76
IS - 190
M3 - Article
SP - 60937
EP - 60938
SN - 00976326
AB - The article presents a notice for public comment on the Draft License Renewal Interim Staff Guidance for steam generator aging, issued by the U.S. Nuclear Regulatory Commission (NRC). It mentions that the draft calls for the evaluation on the suitability of using Revision 3 of NEI 97-06 to manage such aging. It notes that the draft also revises the management recommendations of the NRC. Information on the requirements for the submission of comments and information access is also offered.
KW - LICENSES
KW - ACCESS to information
KW - STEAM generators
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69931170; Pelton, David L. 1; Affiliations: 1: Acting Director, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 9/30/2011, Vol. 76 Issue 190, p60937; Thesaurus Term: LICENSES; Thesaurus Term: ACCESS to information; Subject Term: STEAM generators; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221330 Steam and Air-Conditioning Supply; NAICS/Industry Codes: 423720 Plumbing and Heating Equipment and Supplies (Hydronics) Merchant Wholesalers; NAICS/Industry Codes: 416120 Plumbing, heating and air-conditioning equipment and supplies merchant wholesalers; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Power Uprates; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/09/30/
VL - 76
IS - 190
M3 - Proceeding
SP - 60938
EP - 60938
SN - 00976326
AB - The article offers information on the meeting of the U.S. Nuclear Regulatory Commission for the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Power Uprates to be held on October 5, 2011.
KW - NUCLEAR power plants
KW - PUBLIC meetings of government agencies
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - CONGRESSES
N1 - Accession Number: 69931172; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 9/30/2011, Vol. 76 Issue 190, p60938; Thesaurus Term: NUCLEAR power plants; Subject Term: PUBLIC meetings of government agencies; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject Term: CONGRESSES; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Galloway, Melanie A.
T1 - Metal Fatigue Analysis Performed by Computer Software.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/09/30/
VL - 76
IS - 190
M3 - Article
SP - 60939
EP - 60941
SN - 00976326
AB - The article announces the proposal of the U.S. Nuclear Regulatory Commission (NRC) to issue a regulatory issue summary for nuclear reactor audits using a computer software. It mentions that the proposal is in compliance with the Rules for Construction of Nuclear Facility Components of the American Society of Mechanical Engineers (ASME). It notes the requirements for submission of comments regarding the proposal. Information on where to access documents related to the proposal is also offered.
KW - COMPUTER software
KW - NUCLEAR reactors -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - AMERICAN Society of Mechanical Engineers
N1 - Accession Number: 69931173; Galloway, Melanie A. 1; Affiliations: 1: Acting Director, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 9/30/2011, Vol. 76 Issue 190, p60939; Thesaurus Term: COMPUTER software; Subject Term: NUCLEAR reactors -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: AMERICAN Society of Mechanical Engineers; NAICS/Industry Codes: 417310 Computer, computer peripheral and pre-packaged software merchant wholesalers; NAICS/Industry Codes: 511211 Software publishers (except video game publishers); NAICS/Industry Codes: 443144 Computer and software stores; NAICS/Industry Codes: 423430 Computer and Computer Peripheral Equipment and Software Merchant Wholesalers; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Gallucci, Raymond H.V.
AU - Iqbal, Naeem
T1 - An integrated methodology to predict the likelihood of spurious actuation of AC circuits due to fires in commercial nuclear power plants
JO - Fire Safety Journal
JF - Fire Safety Journal
Y1 - 2011/10//
VL - 46
IS - 7
M3 - Article
SP - 388
EP - 396
SN - 03797112
AB - Abstract: Research efforts by the nuclear power industry and, most recently, its regulatory agency, the U.S. Nuclear Regulatory Commission (USNRC), have provided information useful for risk-informed analysis of the effects of spurious actuation (“hot shorting”) of alternating current (AC) electrical circuits at nuclear power plants. The results from these efforts have been integrated into a methodology to predict the likelihood of spurious actuation of AC circuits due to fires in commercial nuclear power plants. [Copyright &y& Elsevier]
AB - Copyright of Fire Safety Journal is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear power plants
KW - Fires
KW - Nuclear industry
KW - Alternating currents
KW - Electric circuits
KW - Probability theory
KW - Prediction theory
KW - United States
KW - AC circuits
KW - Cable fires
KW - Nuclear power
KW - Prediction
KW - Probabilities
KW - Spurious actuations
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 65045193; Gallucci, Raymond H.V.; Email Address: ray.gallucci@nrc.gov; Iqbal, Naeem 1; Affiliations: 1: Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Issue Info: Oct2011, Vol. 46 Issue 7, p388; Thesaurus Term: Nuclear power plants; Thesaurus Term: Fires; Thesaurus Term: Nuclear industry; Subject Term: Alternating currents; Subject Term: Electric circuits; Subject Term: Probability theory; Subject Term: Prediction theory; Subject: United States; Author-Supplied Keyword: AC circuits; Author-Supplied Keyword: Cable fires; Author-Supplied Keyword: Nuclear power; Author-Supplied Keyword: Prediction; Author-Supplied Keyword: Probabilities; Author-Supplied Keyword: Spurious actuations ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.firesaf.2011.06.005
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Guber, Andrey
AU - Gish, Timothy
AU - Pachepsky, Yakov
AU - McKee, Lynn
AU - Nicholson, Thomas
AU - Cady, Ralph
T1 - Event-based estimation of water budget components using a network of multi-sensor capacitance probes.
JO - Hydrological Sciences Journal/Journal des Sciences Hydrologiques
JF - Hydrological Sciences Journal/Journal des Sciences Hydrologiques
Y1 - 2011/10//
VL - 56
IS - 7
M3 - Article
SP - 1227
EP - 1241
SN - 02626667
AB - A new approach was developed for estimating vertical soil water fluxes using soil water content time series data. Instead of a traditional fixed time interval, this approach utilizes the time interval between two sequential minima of the soil water storage time series to identify groundwater recharge events and calculate components of the soil water budget. We calculated water budget components: surface-water excess (Sw), infiltration less evapotranspiration (I – ET) and groundwater recharge (R) from May 2001 to January 2003 at eight locations at the USDA Agricultural Research Center, Beltsville, Maryland, USA. High uncertainty was observed for all budget components. This uncertainty was attributed to spatial and temporal variation in Sw, I – ET and R, and was caused by nonuniform rainfall distributions during recharge events, variability in the profile water content, and spatial variability in soil hydraulic properties. The proposed event-based approach allows estimating water budget components when profile water content monitoring data are available. Citation Guber, A., Gish, T., Pachepsky, Y., McKee, L., Nicholson, T. & Cady, R. (2011) Event-based estimation of water budget components using a network of multi-sensor capacitance probes. Hydrol. Sci. J. 56(7), 1227–1241. [ABSTRACT FROM AUTHOR]
AB - Copyright of Hydrological Sciences Journal/Journal des Sciences Hydrologiques is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SENSOR networks
KW - SOIL moisture
KW - EVAPOTRANSPIRATION
KW - RAIN & rainfall
KW - ESTIMATION theory
KW - GROUNDWATER
KW - BELTSVILLE (Md.)
KW - MARYLAND
N1 - Accession Number: 66696374; Guber, Andrey 1; Email Address: andrey.guber@ars.usda.gov Gish, Timothy 2; Email Address: timothy.gish@ars.usda.gov Pachepsky, Yakov 1; Email Address: ypachepsky@anri.barc.usda.gov McKee, Lynn 2; Email Address: lynn.mckee@ars.usda.gov Nicholson, Thomas 3; Email Address: tjn@nrc.gov Cady, Ralph 3; Email Address: rec2@nrc.gov; Affiliation: 1: US Department of Agriculture, Agricultural Research Service (USDA-ARS), Environmental Microbial and Food Safety Laboratory, BARC-EAST, USA 2: USDA-ARS, Hydrology and Remote Sensing Laboratory, BARC-WEST, USA 3: US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, USA; Source Info: Oct2011, Vol. 56 Issue 7, p1227; Subject Term: SENSOR networks; Subject Term: SOIL moisture; Subject Term: EVAPOTRANSPIRATION; Subject Term: RAIN & rainfall; Subject Term: ESTIMATION theory; Subject Term: GROUNDWATER; Subject Term: BELTSVILLE (Md.); Subject Term: MARYLAND; Number of Pages: 15p; Illustrations: 3 Charts, 7 Graphs, 1 Map; Document Type: Article
L3 - 10.1080/02626667.2011.609485
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Bahn, Chi Bum
AU - Majumdar, Saurin
AU - Harris, Charles
T1 - Time-dependent leak behavior of flawed Alloy 600 tube specimens at constant pressure
JO - International Journal of Pressure Vessels & Piping
JF - International Journal of Pressure Vessels & Piping
Y1 - 2011/10//
VL - 88
IS - 10
M3 - Article
SP - 423
EP - 433
SN - 03080161
AB - Abstract: Leak rate testing has been performed using Alloy 600 tube specimens with throughwall flaws. Some specimens have shown time-dependent leak behavior at constant pressure conditions. Fractographic characterization was performed to identify the time-dependent crack growth mechanism. The fracture surface of the specimens showed the typical features of ductile fracture, as well as the distinct crystallographic facets, typical of fatigue crack growth at low ΔK level. Structural vibration appears to have been caused by the oscillation of pressure, induced by a high-pressure pump used in a test facility, and by the water jet/tube structure interaction. Analyses of the leak behaviors and crack growth indicated that both the high-pressure pump and the water jet could significantly contribute to fatigue crack growth. To determine whether the fatigue crack growth during the leak testing can occur solely by the water jet effect, leak rate tests at constant pressure without the high-pressure pump need to be performed. [Copyright &y& Elsevier]
AB - Copyright of International Journal of Pressure Vessels & Piping is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - MATERIALS -- Fatigue
KW - TUBES
KW - STEAM generators
KW - PRESSURE
KW - WATER jets
KW - VIBRATION (Mechanics)
KW - CHROMIUM-iron-nickel alloys
KW - FRACTURE mechanics
KW - Fatigue crack growth
KW - Leak rate
KW - Pump-induced oscillation
KW - Steam generator tube
KW - Water jet-induced vibration
N1 - Accession Number: 65345159; Bahn, Chi Bum 1; Email Address: bahn@anl.gov Majumdar, Saurin 1 Harris, Charles 2; Affiliation: 1: Argonne National Laboratory, Argonne, IL 60439, USA 2: The United States Nuclear Regulatory Commission, Rockville, MD 20852, USA; Source Info: Oct2011, Vol. 88 Issue 10, p423; Subject Term: MATERIALS -- Fatigue; Subject Term: TUBES; Subject Term: STEAM generators; Subject Term: PRESSURE; Subject Term: WATER jets; Subject Term: VIBRATION (Mechanics); Subject Term: CHROMIUM-iron-nickel alloys; Subject Term: FRACTURE mechanics; Author-Supplied Keyword: Fatigue crack growth; Author-Supplied Keyword: Leak rate; Author-Supplied Keyword: Pump-induced oscillation; Author-Supplied Keyword: Steam generator tube; Author-Supplied Keyword: Water jet-induced vibration; NAICS/Industry Codes: 221330 Steam and Air-Conditioning Supply; NAICS/Industry Codes: 416120 Plumbing, heating and air-conditioning equipment and supplies merchant wholesalers; NAICS/Industry Codes: 423720 Plumbing and Heating Equipment and Supplies (Hydronics) Merchant Wholesalers; NAICS/Industry Codes: 331210 Iron and Steel Pipe and Tube Manufacturing from Purchased Steel; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.ijpvp.2011.07.007
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Hoxie, Chris L.
AU - Mahaffy, John H.
AU - Bajorek, Stephen M.
AU - Staudenmeier, Joseph
AU - Murray, Christopher
AU - Downar, Thomas J.
T1 - Letter to the Editor on the paper by W. Wulff, “Critical review of conservation equations for two-phase flow in the U.S. NRC TRACE Code”
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2011/10//
VL - 241
IS - 10
M3 - Letter
SP - 4261
EP - 4268
SN - 00295493
N1 - Accession Number: 65951959; Hoxie, Chris L. 1 Mahaffy, John H. 1 Bajorek, Stephen M.; Email Address: SMB4@nrc.gov Staudenmeier, Joseph 1 Murray, Christopher 1 Downar, Thomas J. 1; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Oct2011, Vol. 241 Issue 10, p4261; Number of Pages: 8p; Document Type: Letter
L3 - 10.1016/j.nucengdes.2011.06.052
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DP - EBSCOhost
DB - aph
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor;Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/03/
VL - 76
IS - 191
M3 - Proceeding
SP - 61118
EP - 61118
SN - 00976326
AB - The article offers information on the U.S. Advisory Committee on Reactor Safeguards' (ACRS) Advanced Boiling Water Reactor (ABWR) meeting to be held on October 4, 2011 in Rockville, Maryland.
KW - CONFERENCES & conventions
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
N1 - Accession Number: 69931265; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 10/3/2011, Vol. 76 Issue 191, p61118; Thesaurus Term: CONFERENCES & conventions; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; NAICS/Industry Codes: 561920 Convention and Trade Show Organizers; Number of Pages: 1/2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Plant Operations and Fire Protection; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/03/
VL - 76
IS - 191
M3 - Proceeding
SP - 61118
EP - 61119
SN - 00976326
AB - The article offers information on the U.S. Advisory Committee on Reactor Safeguards' (ACRS) Plant Operations and Fire Protection meeting to be held on October 5, 2011 in Rockville, Maryland.
KW - CONFERENCES & conventions
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
N1 - Accession Number: 69931267; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Reactor Safety Branch , Advisory Committee on Reactor Safeguards; Issue Info: 10/3/2011, Vol. 76 Issue 191, p61118; Thesaurus Term: CONFERENCES & conventions; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; NAICS/Industry Codes: 561920 Convention and Trade Show Organizers; Number of Pages: 2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69931267&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Planning and Procedures; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/03/
VL - 76
IS - 191
M3 - Proceeding
SP - 61119
EP - 61119
SN - 00976326
AB - The article offers information on the U.S. Advisory Committee on Reactor Safeguards' (ACRS) Planning and Procedures meeting to be held on October 5, 2011 in Rockville, Maryland.
KW - CONFERENCES & conventions
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
N1 - Accession Number: 69931268; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Reactor Safety Branch , Advisory Committee on Reactor Safeguards.; Issue Info: 10/3/2011, Vol. 76 Issue 191, p61119; Thesaurus Term: CONFERENCES & conventions; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; NAICS/Industry Codes: 561920 Convention and Trade Show Organizers; Number of Pages: 1/2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/03/
VL - 76
IS - 191
M3 - Proceeding
SP - 61119
EP - 61120
SN - 00976326
AB - The article offers information on the U.S. Advisory Committee on Reactor Safeguards' (ACRS) Radiation Protection and Nuclear Materials meeting to be held on October 4, 2011 in Rockville, Maryland.
KW - CONFERENCES & conventions
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
N1 - Accession Number: 69931269; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 10/3/2011, Vol. 76 Issue 191, p61119; Thesaurus Term: CONFERENCES & conventions; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; NAICS/Industry Codes: 561920 Convention and Trade Show Organizers; Number of Pages: 2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Giitter, Joseph G.
T1 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/04/
VL - 76
IS - 192
M3 - Article
SP - 61391
EP - 61401
SN - 00976326
AB - The article offers information the biweekly notices of the U.S. Nuclear Regulatory Commission (NRC) to issue and grant facility operating licenses in pursuant to the Atomic Energy Act of 1954 on significant hazards consideration. It states that under the Title 10 of the Code of Federal Regulations, operation of a facility would not involve significant increase in the probability of an accident previously evaluated. Also, the Commission may issue the amendment until the 60-days expiration.
KW - BUSINESS licenses
KW - NUCLEAR energy -- Law & legislation -- United States
KW - CONSTITUTIONAL amendments
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69850500; Giitter, Joseph G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 10/4/2011, Vol. 76 Issue 192, p61391; Thesaurus Term: BUSINESS licenses; Subject Term: NUCLEAR energy -- Law & legislation -- United States; Subject Term: CONSTITUTIONAL amendments; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; Number of Pages: 11p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850500&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Colón, Araceli T. Billoch
T1 - Exelon Generation Company, LLC; Notice of Withdrawal of Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/06/
VL - 76
IS - 194
M3 - Article
SP - 62095
EP - 62095
SN - 00976326
AB - The article discusses the move of the U.S. Nuclear Regulatory Commission (NRC) to grant the request of Exelon Generation Co. LLC to withdraw its application for proposed amendment to Facility Operating License in LaSalle County, Illinois.
KW - TRADE regulation
KW - U.S. Nuclear Regulatory Commission
KW - EXELON Generation Co. LLC
N1 - Accession Number: 69715565; Colón, Araceli T. Billoch 1; Affiliations: 1: Project Manager, Plant Licensing Branch III-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 10/6/2011, Vol. 76 Issue 194, p62095; Thesaurus Term: TRADE regulation ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: EXELON Generation Co. LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2/5p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69715565&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Leeds, Eric J.
T1 - Tennessee Valley Authority (Bellefonte Nuclear Plant, Unit 1).
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/07/
VL - 76
IS - 195
M3 - Article
SP - 62457
EP - 62460
SN - 00976326
AB - The article discusses the Tennessee Valley Authority of Bellefonte Nuclear Plant, Unit 1. As stated, the Tennessee Valley Authority is the current holder of construction permit which were issued by the U.S. Nuclear Regulatory Commission (NRC). As reported, the NRC provides different websites for its information including www.nrc.gov/reading-rm/adams.html.
KW - LICENSES
KW - INFORMATION & communication technologies
KW - WEBSITES
KW - UNITED States
KW - TENNESSEE Valley Authority
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69824423; Leeds, Eric J. 1; Affiliations: 1: Director, Office of Nuclear Reactor Regulation.; Issue Info: 10/7/2011, Vol. 76 Issue 195, p62457; Thesaurus Term: LICENSES; Thesaurus Term: INFORMATION & communication technologies; Thesaurus Term: WEBSITES; Subject: UNITED States ; Company/Entity: TENNESSEE Valley Authority Ticker: TVC ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 519130 Internet Publishing and Broadcasting and Web Search Portals; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69824423&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Singal, Balwant K.
T1 - STP Nuclear Operating Company, South Texas Project, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/11/
VL - 76
IS - 196
M3 - Article
SP - 62861
EP - 62862
SN - 00976326
AB - The article reports on the issuance of environmental assessment and finding of no significant impact to South Texas Project (STP) Nuclear Operating Co. by the U.S. Nuclear Regulatory Commission (NRC). It reveals that the action of the agency would issue an exemption from the Code of Federal Regulations (CFR) regarding fuel cladding material and revision of the Technical Specifications document. In addition, the NRC concludes that the exemption does not present risk to public health and safety.
KW - ENVIRONMENTAL impact analysis
KW - ENVIRONMENTAL health -- United States
KW - UNITED States
KW - SOUTH Texas Project Nuclear Operating Co.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69850659; Singal, Balwant K. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 10/11/2011, Vol. 76 Issue 196, p62861; Thesaurus Term: ENVIRONMENTAL impact analysis; Subject Term: ENVIRONMENTAL health -- United States; Subject: UNITED States ; Company/Entity: SOUTH Texas Project Nuclear Operating Co. ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850659&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Economic Simplified Boiling Water Reactor; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/11/
VL - 76
IS - 196
M3 - Proceeding
SP - 62866
EP - 62867
SN - 00976326
AB - The article offers information on the U.S. Advisory Committee on Reactor Safeguards (ACRS) subcommittee meeting regarding Economic Simplified Boiling Water Reactor (ESBWR) which will be held in room T-2B1, 11545 Rockville Pike, Rockville, Maryland on October 21, 2011.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
KW - BOILING water reactors
N1 - Accession Number: 69850661; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 10/11/2011, Vol. 76 Issue 196, p62866; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; Subject Term: BOILING water reactors; Number of Pages: 2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850661&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on AP1000; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/11/
VL - 76
IS - 196
M3 - Proceeding
SP - 62867
EP - 62867
SN - 00976326
AB - The article offers information on the meeting of the U.S. Advisory Committee on Reactor Safeguards (ACRS) Subcommittee regarding the AP1000 Subsequent Combined License Application (SCOLA) which will be held at the room T-2B1, 11545 Rockville Pile, Rockville, Maryland on October 18-19, 2011.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
KW - MARYLAND Route 355 (Md.)
N1 - Accession Number: 69850662; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 10/11/2011, Vol. 76 Issue 196, p62867; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; Subject Term: MARYLAND Route 355 (Md.); Number of Pages: 1/2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850662&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on U.S. Advanced Pressurized Power Reactor; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/11/
VL - 76
IS - 196
M3 - Proceeding
SP - 62867
EP - 62868
SN - 00976326
AB - The article offers information on the U.S. Advisory Committee on Reactor Safeguards (ACRS) subcommittee meeting regarding the U.S. Advanced Pressurized Power Reactor (US-APWR) which will be held in room T-2B1, 11545 Rockville Pike, Rockville, Maryland on October 20, 2011.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
KW - NUCLEAR reactors -- Safety measures -- Congresses
N1 - Accession Number: 69850663; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 10/11/2011, Vol. 76 Issue 196, p62867; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; Subject Term: NUCLEAR reactors -- Safety measures -- Congresses; Number of Pages: 2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850663&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Silva, Patricia A.
T1 - Washington State University; Notice of Issuance of Renewed Facility Operating License No. R-76.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/11/
VL - 76
IS - 196
M3 - Article
SP - 62868
EP - 62869
SN - 00976326
AB - The article focuses on the U.S. Nuclear Regulatory Commission's (NRC) issuance of renewed Facility Operating License No. R-76 for continued operation of the Modified Training, Research, Isotope Production, General Atomics (TRIGA) Nuclear Reactor of the Washington State University (WSU) in Pullman, Whitman County, Washington. It notes the compliance of the renewed license to the Atomic Energy Act of 1954. Also outlined is the NRC staff's verification of the safety of the facility operation.
KW - LICENSES
KW - NUCLEAR reactors
KW - NUCLEAR energy -- Law & legislation
KW - PULLMAN (Wash.)
KW - WASHINGTON (State)
KW - U.S. Nuclear Regulatory Commission
KW - WASHINGTON State University
N1 - Accession Number: 69850665; Silva, Patricia A. 1; Affiliations: 1: Acting Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 10/11/2011, Vol. 76 Issue 196, p62868; Thesaurus Term: LICENSES; Subject Term: NUCLEAR reactors; Subject Term: NUCLEAR energy -- Law & legislation; Subject: PULLMAN (Wash.); Subject: WASHINGTON (State) ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: WASHINGTON State University; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850665&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Plant License Renewal; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/12/
VL - 76
IS - 197
M3 - Article
SP - 63329
EP - 63329
SN - 00976326
AB - The article offers information on a meeting to be hosted by the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Plant License Renewal on October 19, 2011 in Rockville, Maryland.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
KW - ROCKVILLE (Va.)
N1 - Accession Number: 69850836; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Reactor Safety Branch, Advisory Committee on Reactor Safeguards; Issue Info: 10/12/2011, Vol. 76 Issue 197, p63329; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; Subject: ROCKVILLE (Va.); Number of Pages: 1/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850836&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Kobetz, Timothy
T1 - Event Reporting Guidelines.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/13/
VL - 76
IS - 198
M3 - Article
SP - 63565
EP - 63566
SN - 00976326
AB - The article offers information on the "Event Reporting Guidelines" from the Nuclear Regulatory Commission (NRC) in the U.S. The mentioned government agency aims to make revision on its current guidelines to improve its operations as well as the staff's compliance in handling nuclear power reactors. Comments needed by the NRC for the improvement of its regulatory tasks are also mentioned.
KW - GOVERNMENT policy
KW - GUIDELINES
KW - NUCLEAR reactors -- Safety measures
KW - NUCLEAR energy
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69850899; Kobetz, Timothy 1; Affiliations: 1: Branch Chief, Reactor Inspection Branch, Division of Inspections and Regional Support, Office of Nuclear Reactor Regulation.; Issue Info: 10/13/2011, Vol. 76 Issue 198, p63565; Thesaurus Term: GOVERNMENT policy; Subject Term: GUIDELINES; Subject Term: NUCLEAR reactors -- Safety measures; Subject Term: NUCLEAR energy; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 911910 Other federal government public administration; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850899&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Omaha Public Power District; Fort Calhoun Station, Unit 1; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/13/
VL - 76
IS - 198
M3 - Article
SP - 63668
EP - 63670
SN - 00976326
AB - The article discusses the request of Omaha Public Power District (OPPD) for an exemption from the requirements of Title 10 of the Code of Federal Regulations (CFR) part 50, Appendix E. It notes that the district was authorized by the U.S. Nuclear Regulatory Commission to conduct biennial full participation emergency preparedness (EP) exercise required for 2011. The authorization was granted due to the findings that the exemptions will not present an undue risk to the public health and safety.
KW - FEDERAL regulation
KW - EMERGENCY management
KW - EXEMPTION (Law)
KW - UNITED States
KW - OMAHA Public Power District (Company)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69850984; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/13/2011, Vol. 76 Issue 198, p63668; Thesaurus Term: FEDERAL regulation; Thesaurus Term: EMERGENCY management; Subject Term: EXEMPTION (Law); Subject: UNITED States ; Company/Entity: OMAHA Public Power District (Company) DUNS Number: 006970453 ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850984&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Silva, Patricia A.
T1 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/13/
VL - 76
IS - 198
M3 - Article
SP - 63668
EP - 63668
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission (NRC) on its call for public comments on chapters 1-6 of Draft Interim Staff Guidance for preparing and reviewing licensing applications for the production of radioisotopes. Deadline for submission of comments is on November 14, 2011. Criteria for comments to be submitted are enumerated.
KW - GOVERNMENT policy
KW - RADIOISOTOPES
KW - GOVERNMENT information -- United States
KW - GOVERNMENT publications -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69850983; Silva, Patricia A. 1; Affiliations: 1: Chief, Research and Test Reactors Projects Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 10/13/2011, Vol. 76 Issue 198, p63668; Thesaurus Term: GOVERNMENT policy; Subject Term: RADIOISOTOPES; Subject Term: GOVERNMENT information -- United States; Subject Term: GOVERNMENT publications -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; Number of Pages: 2/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850983&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/13/
VL - 76
IS - 198
M3 - Article
SP - 63671
EP - 63672
SN - 00976326
AB - The article looks at the evaluation conducted by the U.S. Nuclear Regulatory Commission (NCR) on the request of the Omaha Public Power District (OPPD) for an extension of the compliance date regarding the requirement of Title 10 of the Code of Federal Regulations (CFR) Part 73. The NCR concluded that the OPPD has provided adequate justification for its request. It notes that the compliance date has been extended until November 5, 2013.
KW - NUCLEAR power plants
KW - FEDERAL regulation
KW - SAFETY measures
KW - UNITED States
KW - OMAHA Public Power District (Company)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69850985; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/13/2011, Vol. 76 Issue 198, p63671; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: FEDERAL regulation; Subject Term: SAFETY measures; Subject: UNITED States ; Company/Entity: OMAHA Public Power District (Company) DUNS Number: 006970453 ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850985&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Bahadur, Sher
T1 - Final Division of Safety Systems Interim Staff Guidance DSS-ISG-2010- 01: Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/13/
VL - 76
IS - 198
M3 - Article
SP - 63676
EP - 63677
SN - 00976326
AB - The article reports on the issuance of U.S. Nuclear Regulatory Commission (NRC) of the final Division of Safety Systems Interim Staff Guidance, which provides updated guidance to address complexity of spent fuel pool license application analyses and operations.
KW - GOVERNMENT policy
KW - NUCLEAR power plants
KW - SPENT reactor fuels
KW - UNITED States
KW - SAFETY measures
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69850987; Bahadur, Sher 1; Affiliations: 1: Acting Director, Division of Safety Systems, Office of Nuclear Reactor Regulation; Issue Info: 10/13/2011, Vol. 76 Issue 198, p63676; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: NUCLEAR power plants; Subject Term: SPENT reactor fuels; Subject Term: UNITED States; Subject Term: SAFETY measures ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69850987&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant Designs; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/17/
VL - 76
IS - 200
M3 - Proceeding
SP - 64123
EP - 64123
SN - 00976326
AB - The article offers information on the meeting of Advisory Committee on Reactor Safeguards (ACRS) of the U.S. Nuclear Regulatory Commission (NRC) to discuss future plant designs on November 2, 2011 in Rockville, Maryland.
KW - ADVISORY boards
KW - CONGRESSES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69911313; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Reactor Safety Branch, Advisory Committee on Reactor Safeguards.; Issue Info: 10/17/2011, Vol. 76 Issue 200, p64123; Thesaurus Term: ADVISORY boards; Subject Term: CONGRESSES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 541611 Administrative Management and General Management Consulting Services; Number of Pages: 2/3p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69911313&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele
T1 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses; Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/18/
VL - 76
IS - 201
M3 - Article
SP - 64388
EP - 64399
SN - 00976326
AB - The article reports on the publication of the biweekly notice of U.S. Nuclear Regulatory Commission (NRC) pursuant to Atomic Energy Act of 1954 in the U.S. It states that the biweekly notice included applications and amendments for facility operating licenses and offers information on the methods used to access available documents related to the biweekly notice. It provides an overview of the proposed determination for the amendment requests involving no significant hazards consideration
KW - LEGAL advertising
KW - BUSINESS licenses
KW - NUCLEAR energy -- Law & legislation
KW - LEGISLATIVE amendments
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69911451; Evans, Michele 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/18/2011, Vol. 76 Issue 201, p64388; Thesaurus Term: LEGAL advertising; Thesaurus Term: BUSINESS licenses; Subject Term: NUCLEAR energy -- Law & legislation; Subject Term: LEGISLATIVE amendments; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; Number of Pages: 12p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69911451&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Saba, Farideh E.
T1 - Florida Power Corporation; Notice of Withdrawal of Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/26/
VL - 76
IS - 207
M3 - Article
SP - 66332
EP - 66332
SN - 00976326
AB - The article presents the notice of withdrawal of Florida Power Corp.'s March 24, 2011 application for amendment to its facility operating license of the Crystal River Unit 3 nuclear generating plant in Citrus County, Florida from the U.S. Nuclear Regulatory Commission.
KW - FLORIDA
KW - FLORIDA Power Corp.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69756379; Saba, Farideh E. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch II-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/26/2011, Vol. 76 Issue 207, p66332; Subject: FLORIDA ; Company/Entity: FLORIDA Power Corp. DUNS Number: 006923700 ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/5p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=69756379&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Saba, Farideh E.
T1 - Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental Assessment and Finding of No Significant Impact.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/26/
VL - 76
IS - 207
M3 - Article
SP - 66333
EP - 66334
SN - 00976326
AB - The article reports on the proposed action of the U.S. Nuclear Regulatory Commission (NRC) to issue an exemption pursuant to Title 10 of the Code of Federal Regulations. The NRC will allow the use of M5 alloy fuel rod cladding for the facilities of Carolina Power & Light Co. and for operation of H.B. Robinson Steam Electric Plant in South Carolina. The NRC staff has concluded that the proposed action will have no significant environmental impact.
KW - POWER plants
KW - ENVIRONMENTAL impact analysis
KW - LAW & legislation
KW - SOUTH Carolina
KW - U.S. Nuclear Regulatory Commission
KW - CAROLINA Power & Light Co.
N1 - Accession Number: 69756381; Saba, Farideh E. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch II-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/26/2011, Vol. 76 Issue 207, p66333; Thesaurus Term: POWER plants; Thesaurus Term: ENVIRONMENTAL impact analysis; Subject Term: LAW & legislation; Subject: SOUTH Carolina ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: CAROLINA Power & Light Co. DUNS Number: 006997217 Ticker: CPL; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Jolicoeur, John R.
T1 - Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-510, Revision 2, ''Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection''.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/27/
VL - 76
IS - 208
M3 - Article
SP - 66763
EP - 66764
SN - 00976326
AB - The article reports that the U.S. Nuclear Regulatory Commission (NRC) is providing safety evaluation of the models for plant-specific adoption of Technical Specifications Task Force Traveler, Revision 2. As stated, the revision "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection" is available in the Agencywide Documents Access and Management System. As further stated, the revision is required to address implementation of administrative changes.
KW - NUCLEAR power plants
KW - ADMINISTRATIVE procedure
KW - SAFETY measures
KW - STEAM-boiler inspection
KW - NUCLEAR facilities
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69824559; Jolicoeur, John R. 1; Affiliations: 1: Chief, Licensing Processes Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 10/27/2011, Vol. 76 Issue 208, p66763; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: ADMINISTRATIVE procedure; Subject Term: SAFETY measures; Subject Term: STEAM-boiler inspection; Subject Term: NUCLEAR facilities; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221330 Steam and Air-Conditioning Supply; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Flanders, Scott
T1 - Detroit Edison Company; Notice of Availability of Draft Environmental Impact Statement for a Combined License for Unit 3 at the Enrico Fermi Atomic Power Plant Site.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/28/
VL - 76
IS - 209
M3 - Article
SP - 66998
EP - 67000
SN - 00976326
AB - The article presents a notice on the availability of draft Environmental Impact Statement (EIS) for a Combined License (COL) for unit three at the Enrico Fermi Atomic Power Plant Site, Monroe County, Michigan. As stated, the notice is submitted by the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Army Corps of Engineers, Detroit, Michigan. As further stated, the comments are invited from the interested parties on the draft EIS by NRC till January 11, 2012.
KW - NUCLEAR power plants
KW - ENVIRONMENTAL impact statements
KW - MONROE County (Mich.)
KW - DETROIT (Mich.)
KW - MICHIGAN
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - UNITED States. Army. Corps of Engineers
N1 - Accession Number: 69824711; Flanders, Scott 1; Affiliations: 1: Director, Division of Site and Environmental Reviews, Office of New Reactors; Issue Info: 10/28/2011, Vol. 76 Issue 209, p66998; Thesaurus Term: NUCLEAR power plants; Subject Term: ENVIRONMENTAL impact statements; Subject: MONROE County (Mich.); Subject: DETROIT (Mich.); Subject: MICHIGAN; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: UNITED States. Army. Corps of Engineers; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Diaz-Sanabria, Yoira
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/10/31/
VL - 76
IS - 210
M3 - Article
SP - 67232
EP - 67233
SN - 00976326
AB - The article offers information on the meeting of the Advisory Committee on Reactor Safeguards' (ACRS) Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) to be held on November 14-15, 2011 in Rockville, Maryland.
KW - PUBLIC meetings of government agencies
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
N1 - Accession Number: 69851204; Diaz-Sanabria, Yoira 1; Affiliations: 1: Technical Assistant, Reactor Safety Branch, Advisory Committee on Reactor Safeguards.; Issue Info: 10/31/2011, Vol. 76 Issue 210, p67232; Subject Term: PUBLIC meetings of government agencies; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Grobe, Jack
T1 - U.S. Nuclear Regulatory Commission Kept Safety Focus after Fukushima.
JO - Power Engineering
JF - Power Engineering
Y1 - 2011/11//
VL - 115
IS - 11
M3 - Article
SP - 4
EP - 4
PB - PennWell Corporation
SN - 00325961
AB - In this article the author discusses the inspections made on nuclear power plants throughout the U.S. by the Nuclear Regulatory Commission (NRC) after the Fukushima Dai-chi plant meltdown in Japan. He states that besides sending staff to Japan and monitoring events there, inspectors visited local sites assessing them with Extensive Damage Mitigation Guidelines (EDMG). While they passed, he reports that they made 12 recommendations to improve performance and safety for the long run.
KW - BUILDING inspection
KW - NUCLEAR power plants
KW - FUKUSHIMA Nuclear Accident, Fukushima, Japan, 2011
KW - UNITED States
KW - JAPAN
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 67723444; Grobe, Jack 1; Affiliation: 1: Deputy Director for Engineering, NRC's Office of Nuclear Reactor Regulation; Source Info: Nov2011, Vol. 115 Issue 11, Special section p4; Subject Term: BUILDING inspection; Subject Term: NUCLEAR power plants; Subject Term: FUKUSHIMA Nuclear Accident, Fukushima, Japan, 2011; Subject Term: UNITED States; Subject Term: JAPAN; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 541350 Building Inspection Services; NAICS/Industry Codes: 926150 Regulation, Licensing, and Inspection of Miscellaneous Commercial Sectors; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 1p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - STP Nuclear Operating Company; South Texas Project, Units 1 and 2; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/11/04/
VL - 76
IS - 214
M3 - Article
SP - 68511
EP - 68512
SN - 00976326
AB - The article announces the notice issued by the U.S. Nuclear Regulatory Commission on the exemption of STP Nuclear Operating Co.'s (STPNOC) South Texas Projects Units 1 and 2.
KW - EXEMPTION (Law)
KW - STP Nuclear Operating Co.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69931412; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 11/4/2011, Vol. 76 Issue 214, p68511; Subject Term: EXEMPTION (Law) ; Company/Entity: STP Nuclear Operating Co. ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit 2; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2011/11/04/
VL - 76
IS - 214
M3 - Article
SP - 68512
EP - 68514
SN - 00976326
AB - The article announces the notice issued by the U.S. Nuclear Regulatory Commission on the exemption of Carolina Power & Light Co.'s exemptiom of its H. B. Robinson Steam Electric Plant (HBRSEP), Unit 2 in New Hill, North Carolina.
KW - EXEMPTION (Law)
KW - CAROLINA Power & Light Co.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 69931413; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 11/4/2011, Vol. 76 Issue 214, p68512; Subject Term: EXEMPTION (Law) ; Company/Entity: CAROLINA Power & Light Co. DUNS Number: 006997217 Ticker: CPL ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Illustrations: 1 Chart; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Joyce, James A.
AU - Tregoning, Robert
T1 - Evaluation of a method to characterize material inhomogeneity in ferritic steels within the ductile-to-brittle transition regime
JO - Engineering Fracture Mechanics
JF - Engineering Fracture Mechanics
Y1 - 2011/12//
VL - 78
IS - 17
M3 - Article
SP - 2870
EP - 2884
SN - 00137944
AB - Abstract: The ASTM “Standard Test Method for Determination of Reference Temperature, T o, for Ferritic Steels in the Transition Range,” (ASTM E1921) has been developed to characterize the onset of cleavage cracking in the ductile-to-brittle transition regime for ferritic structural steels. This standard determines T o, the reference temperature at which the median fracture toughness of a 25mm thick specimen is 100MPa . Material inhomogeneity has been shown to have a strong effect on T o, and suggestions on how to characterize and quantify the effects of inhomogeneity have been developed within a proposed annex for E1921. This study demonstrates that for small data sets neither the current E1921 outlier procedure nor the method in the proposed annex can effectively distinguish between homogeneous and inhomogeneous materials. This study also shows that the bimodal inhomogeneity analysis in the proposed annex only accurately characterizes materials if (1) at least 30 specimens are tested, and (2) the difference between the T o values that describe each unique homogeneous population within the inhomogeneous material is greater than 20°C, and (3) the percentage of the smallest homogeneous material population is greater than 20%. [Copyright &y& Elsevier]
AB - Copyright of Engineering Fracture Mechanics is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - FERRITIC steel
KW - MATERIALS -- Analysis
KW - INHOMOGENEOUS materials
KW - METALS -- Ductility
KW - METALS -- Brittleness
KW - TEST methods
KW - Cleavage fracture
KW - Ductile-to-brittle
KW - Elastic–plastic fracture
KW - Ferritic steels
KW - Material inhomogeneity
KW - Monte-Carlo analysis
KW - Transition
KW - Weibull distribution
N1 - Accession Number: 66854401; Joyce, James A. 1; Email Address: jajoyce418@gmail.com Tregoning, Robert 2; Email Address: Robert.Tregoning@nrc.gov; Affiliation: 1: US Naval Academy, Mechanical Engineering, 590 Holloway Road, Annapolis, MD 21402, United States 2: US Nuclear Regulatory Commission, M/S CS 5 A24, Washington, DC 20555, United States; Source Info: Dec2011, Vol. 78 Issue 17, p2870; Subject Term: FERRITIC steel; Subject Term: MATERIALS -- Analysis; Subject Term: INHOMOGENEOUS materials; Subject Term: METALS -- Ductility; Subject Term: METALS -- Brittleness; Subject Term: TEST methods; Author-Supplied Keyword: Cleavage fracture; Author-Supplied Keyword: Ductile-to-brittle; Author-Supplied Keyword: Elastic–plastic fracture; Author-Supplied Keyword: Ferritic steels; Author-Supplied Keyword: Material inhomogeneity; Author-Supplied Keyword: Monte-Carlo analysis; Author-Supplied Keyword: Transition; Author-Supplied Keyword: Weibull distribution; Number of Pages: 15p; Document Type: Article
L3 - 10.1016/j.engfracmech.2011.08.001
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Easton, E
AU - Bajwa, C
AU - Li, Z
AU - Gordon, M
T1 - Thinking outside the box: options for transport of high burnup spent fuel.
JO - Packaging, Transport, Storage & Security of Radioactive Materials
JF - Packaging, Transport, Storage & Security of Radioactive Materials
Y1 - 2011/12//
VL - 22
IS - 4
M3 - Article
SP - 192
EP - 194
PB - Taylor & Francis Ltd
SN - 17465095
AB - The current uncertainty surrounding the licensing and eventual opening of a long term geologic repository for the nation's civilian and defense spent nuclear fuel and high level radioactive waste has shifted the window for the length of time spent fuel could be stored to periods of time significantly longer than the current licensing period of 40 years for dry storage. An alternative approach may be needed to the licensing of high burnup fuel for storage and transportation based on the assumption that spent fuel cladding may not always remain intact. The approach would permit spent fuel to be retrieved on a canister basis and could lessen the need for repackaging of spent fuel. This approach is being presented as a possible engineering solution to address the uncertainties and lack of data availability for cladding properties for high burnup fuel and extended storage time frames. The proposed approach does not involve relaxing current safety standards for criticality safety, containment, or permissible external dose rates. [ABSTRACT FROM AUTHOR]
AB - Copyright of Packaging, Transport, Storage & Security of Radioactive Materials is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radioactive wastes -- Transportation
KW - Industrial safety
KW - Spent reactor fuels -- Storage
KW - Cladding (Optics)
KW - Microencapsulation
KW - Uncertainty
KW - Cladding
KW - Encapsulation
KW - High burnup fuel
KW - Radioactive transport
N1 - Accession Number: 79680583; Easton, E 1; Bajwa, C 1; Li, Z 1; Gordon, M 1; Affiliations: 1: US Nuclear Regulatory Commission, Washington, DC 20005, USA; Issue Info: 2011, Vol. 22 Issue 4, p192; Thesaurus Term: Radioactive wastes -- Transportation; Thesaurus Term: Industrial safety; Subject Term: Spent reactor fuels -- Storage; Subject Term: Cladding (Optics); Subject Term: Microencapsulation; Subject Term: Uncertainty; Author-Supplied Keyword: Cladding; Author-Supplied Keyword: Encapsulation; Author-Supplied Keyword: High burnup fuel; Author-Supplied Keyword: Radioactive transport; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 484230 Specialized Freight (except Used Goods) Trucking, Long-Distance; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; Number of Pages: 3p; Illustrations: 2 Color Photographs, 2 Charts; Document Type: Article
L3 - 10.1179/1746510912Y.0000000005
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Wellock, Thomas R.
T1 - Fuel Cycle to Nowhere: U.S. Law and Policy on Nuclear Waste.
JO - Environmental History
JF - Environmental History
Y1 - 2012/01//
VL - 17
IS - 1
M3 - Book Review
SP - 189
EP - 191
SN - 10845453
AB - A review of the book "Fuel Cycle to Nowhere: U.S. Law and Policy on Nuclear Waste," by Richard B. Stewart, and Jane Bloom Stewart is presented.
KW - Radioactive wastes -- Government policy
KW - Nonfiction
KW - Stewart, Richard B.
KW - Stewart, Jane Bloom
KW - Fuel Cycle to Nowhere: US Law & Policy on Nuclear Waste (Book)
N1 - Accession Number: 77963609; Wellock, Thomas R. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: Jan2012, Vol. 17 Issue 1, p189; Subject Term: Radioactive wastes -- Government policy; Subject Term: Nonfiction; Reviews & Products: Fuel Cycle to Nowhere: US Law & Policy on Nuclear Waste (Book); NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; People: Stewart, Richard B.; People: Stewart, Jane Bloom; Number of Pages: 3p; Document Type: Book Review
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Raynaud, Patrick A.
AU - Koss, Donald A.
AU - Motta, Arthur T.
T1 - Crack growth in the through-thickness direction of hydrided thin-wall Zircaloy sheet
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2012/01//
VL - 420
IS - 1-3
M3 - Article
SP - 69
EP - 82
SN - 00223115
AB - Abstract: In a reactivity-initiated accident, cladding failure may occur by crack initiation within a defect such as a hydride rim or blister and subsequent crack propagation through the thickness of the thin-wall cladding. In such a circumstance, determining the cladding resistance to crack propagation in the through-thickness direction is crucial to predicting cladding failure. To address this issue, through-thickness crack propagation in hydrided Zircaloy-4 sheet was analyzed at 25°C, 300°C, and 375°C. At 25°C, the fracture toughness decreased with increasing hydrogen content and with an increasing fraction of radial hydrides. Hydride particles fractured ahead of the crack tip, creating a path for crack growth. At both 300°C and 375°C, the resistance to crack-growth initiation was sufficiently high that crack extension was often caused by crack-tip blunting. There was no evidence of hydride particles fracturing near the crack tip, and no significant effect of hydrogen content on fracture toughness was observed at these elevated temperatures. [Copyright &y& Elsevier]
AB - Copyright of Journal of Nuclear Materials is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - ZIRCONIUM alloys
KW - NUCLEAR fuel claddings
KW - ZIRCONIUM alloys -- Hydrogen content
KW - NUCLEAR power plants
KW - HYDRIDES
KW - HYDROGEN
KW - CRACK propagation (Fracture mechanics)
N1 - Accession Number: 70158793; Raynaud, Patrick A. 1; Email Address: patrick.raynaud@nrc.gov Koss, Donald A. 2 Motta, Arthur T. 3; Affiliation: 1: US Nuclear Regulatory Commission, Washington, DC 20555, USA 2: Department of Materials Science and Engineering, Penn State University, University Park, PA 16802, USA 3: Department of Mechanical and Nuclear Engineering, Penn State University, University Park, PA 16802, USA; Source Info: Jan2012, Vol. 420 Issue 1-3, p69; Subject Term: ZIRCONIUM alloys; Subject Term: NUCLEAR fuel claddings; Subject Term: ZIRCONIUM alloys -- Hydrogen content; Subject Term: NUCLEAR power plants; Subject Term: HYDRIDES; Subject Term: HYDROGEN; Subject Term: CRACK propagation (Fracture mechanics); NAICS/Industry Codes: 325120 Industrial Gas Manufacturing; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 331490 Non-ferrous metal (except copper and aluminum) rolling, drawing, extruding and alloying; Number of Pages: 14p; Document Type: Article
L3 - 10.1016/j.jnucmat.2011.09.005
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/01/10/
VL - 77
IS - 6
M3 - Article
SP - 1514
EP - 1521
SN - 00976326
AB - The article offers information on a biweekly notice issued by the U.S. Nuclear Regulatory Commission (NRC) inviting public comments on the amendment to granting operating license that involves no significant hazards considerations. It informs that comments must be sent 30 days after publishing this notice. It further informs that the comments could be submitted through the web site of NRC, public document room of NRC, and through agencywide documents access and management system of NRC.
KW - PUBLIC opinion
KW - GOVERNMENT agencies
KW - WEBSITES
KW - LICENSE agreements
KW - HAZARDOUS substances
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73068485; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 1/10/2012, Vol. 77 Issue 6, p1514; Thesaurus Term: PUBLIC opinion; Thesaurus Term: GOVERNMENT agencies; Thesaurus Term: WEBSITES; Thesaurus Term: LICENSE agreements; Thesaurus Term: HAZARDOUS substances; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 562112 Hazardous Waste Collection; NAICS/Industry Codes: 533110 Lessors of Nonfinancial Intangible Assets (except Copyrighted Works); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 519130 Internet Publishing and Broadcasting and Web Search Portals; Number of Pages: 8p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Preliminary Amendment Request Review Process.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/01/11/
VL - 77
IS - 7
M3 - Article
SP - 1749
EP - 1750
SN - 00976326
AB - The article reports on a notice issued by the U.S. Nuclear RegulatoryCommission (NRC) inviting public comments on draft Interim Staff Guidance (ISG). It informs that ISG provides guidance to the staff of NRC on the Preliminary Amendment Request (PAR) review process that is available to the holders of initial combined license (COL) so that it could be used as an elective precursor to the license amendment process. It further mentions that the comments should be submitted by March 26, 2012.
KW - PUBLIC opinion
KW - GOVERNMENT agencies
KW - LICENSES
KW - EMPLOYEES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73171523; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors.; Issue Info: 1/11/2012, Vol. 77 Issue 7, p1749; Thesaurus Term: PUBLIC opinion; Thesaurus Term: GOVERNMENT agencies; Thesaurus Term: LICENSES; Thesaurus Term: EMPLOYEES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 911910 Other federal government public administration; NAICS/Industry Codes: 912910 Other provincial and territorial public administration; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; NAICS/Industry Codes: 921190 Other General Government Support; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73171523&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Entergy Nuclear Indian Point 2, LLC; Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating Unit No. 2; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/10/
VL - 77
IS - 28
M3 - Article
SP - 7184
EP - 7211
SN - 00976326
AB - The article reports that Entergy Nuclear Operations Inc. which authorizes the operation of Indian Point Nuclear Generating Unit No. 2 (IP2), is requesting for the exemptions for the regulations of the U.S. Nuclear Regulatory Commission. It is stated that thermoplastic and thermoset low-voltage power, control, and instrument cables have been installed at the IP2. It is also stated that the danger of cable fires has been minimized through electrical protection devices.
KW - LICENSES
KW - THERMOPLASTICS
KW - THERMOSETTING plastics
KW - UNITED States
KW - ENTERGY Nuclear Operations Inc.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 71954140; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 2/10/2012, Vol. 77 Issue 28, p7184; Thesaurus Term: LICENSES; Subject Term: THERMOPLASTICS; Subject Term: THERMOSETTING plastics; Subject: UNITED States ; Company/Entity: ENTERGY Nuclear Operations Inc. ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 28p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=71954140&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Quichocho, Jessie F.
T1 - Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Renewal for University of California, Irvine Nuclear Reactor Facility.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/13/
VL - 77
IS - 29
M3 - Article
SP - 7610
EP - 7613
SN - 00976326
AB - The article reports that the U.S. Nuclear Regulatory Commission (NRC) has renewed a license for operating the University of California's Irvine Nuclear Reactor Facility (UCINRF) for a period of 20 years from the date of issuance. It states that the new license would not change the environmental impact of the facility's operation. It further states that the license would not influence human health and environment on minority residing in the vicinity of the UCINRF.
KW - GOVERNMENT policy
KW - NUCLEAR power plants
KW - ENVIRONMENTAL impact analysis
KW - LICENSES
KW - NUCLEAR energy
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 71931891; Quichocho, Jessie F. 1; Affiliations: 1: Branch Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 02/13/2012, Vol. 77 Issue 29, p7610; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: ENVIRONMENTAL impact analysis; Thesaurus Term: LICENSES; Subject Term: NUCLEAR energy; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=71931891&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Regulatory Policies and Practices; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/13/
VL - 77
IS - 29
M3 - Proceeding
SP - 7618
EP - 7618
SN - 00976326
AB - The article offers information on a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on March 6, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - NUCLEAR reactors -- Safety measures -- Congresses
N1 - Accession Number: 71931893; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 02/13/2012, Vol. 77 Issue 29, p7618; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject Term: NUCLEAR reactors -- Safety measures -- Congresses; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=71931893&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Reliability and PRA; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/13/
VL - 77
IS - 29
M3 - Proceeding
SP - 7618
EP - 7618
SN - 00976326
AB - The article offers information on a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Reliability and Probabilistic Risk Assessment of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on March 7, 2012.
KW - MEETINGS
KW - RISK assessment
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - CONGRESSES
N1 - Accession Number: 71931894; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 02/13/2012, Vol. 77 Issue 29, p7618; Thesaurus Term: MEETINGS; Thesaurus Term: RISK assessment; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject Term: CONGRESSES; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards; Meeting of the ACRS Subcommittee on Planning and Procedures; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/13/
VL - 77
IS - 29
M3 - Proceeding
SP - 7618
EP - 7619
SN - 00976326
AB - The article offers information on a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Planning and Procedures of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on March 7, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - ROCKVILLE (Md.)
N1 - Accession Number: 71931895; Santos, Cayetano 1; Affiliations: 1: Chief, Reactor Safety Branch, Advisory Committee on Reactor Safeguards.; Issue Info: 02/13/2012, Vol. 77 Issue 29, p7618; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject: ROCKVILLE (Md.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Billoch Colón,, Araceli T.
T1 - Environmental Assessment and Finding of No Significant Impact; Carolina Power and Light Company Shearon Harris Nuclear Power Plant, Unit 1.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/15/
VL - 77
IS - 31
M3 - Article
SP - 8903
EP - 8904
SN - 00976326
AB - The article provides information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) to Carolina Power and Light Co. regarding the exemption of emergency core cooling systems for light water nuclear power reactors. It states that NRC officials declared that the proposed action do not have impact on the environment.
KW - NUCLEAR reactors -- Cooling
KW - LIGHT water reactors
KW - NUCLEAR reactors -- Environmental aspects
KW - PUBLIC officers
KW - UNITED States
KW - CAROLINA Power & Light Co.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 71954310; Billoch Colón,, Araceli T. 1; Affiliations: 1: Project Manager, Plant Licensing Branch 2-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 02/15/2012, Vol. 77 Issue 31, p8903; Subject Term: NUCLEAR reactors -- Cooling; Subject Term: LIGHT water reactors; Subject Term: NUCLEAR reactors -- Environmental aspects; Subject Term: PUBLIC officers; Subject: UNITED States ; Company/Entity: CAROLINA Power & Light Co. DUNS Number: 006997217 Ticker: CPL ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=71954310&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Entergy Nuclear Indian Point 3, LLC.; Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit 3; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/15/
VL - 77
IS - 31
M3 - Article
SP - 8904
EP - 8926
SN - 00976326
AB - The article reports on a request submitted by Entergy Nuclear Operations Inc. to the U.S. Nuclear Regulatory Commission regarding exemption for running its Indian Point Nuclear Generating Unit 3. It states that Entergy Nuclear Operations Inc. has requested to use the Operator Manual Actions (OMAs) in lieu of meeting certain technical requirements. A table containing information on OMAs is presented. As stated the company met standards required during emergency shutdown in case of fire.
KW - NUCLEAR power plants -- Accidents
KW - NUCLEAR reactors -- Shutdown
KW - UNITED States
KW - ENTERGY Nuclear Operations Inc.
KW - INDIAN Point Nuclear Power Plant (N.Y.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 71954311; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 02/15/2012, Vol. 77 Issue 31, p8904; Thesaurus Term: NUCLEAR power plants -- Accidents; Subject Term: NUCLEAR reactors -- Shutdown; Subject: UNITED States ; Company/Entity: ENTERGY Nuclear Operations Inc. ; Company/Entity: INDIAN Point Nuclear Power Plant (N.Y.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 23p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=71954311&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio F.
T1 - Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on Power Uprates; Revision to February 23, 2012, ACRS Meeting Federal Register Notice.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/17/
VL - 77
IS - 33
M3 - Proceeding
SP - 9707
EP - 9707
SN - 00976326
AB - The article reports that the meeting of the U.S. Advisory Committee on Reactor Safeguards is rescheduled to be held on February 24, 2012.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
N1 - Accession Number: 71954452; Dias, Antonio F. 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 02/17/2012, Vol. 77 Issue 33, p9707; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; Number of Pages: 1/3p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=71954452&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio F.
T1 - Advisory Committee on Reactor Safeguards Meeting of the ACRS Subcommittee on Thermal-Hydraulics Phenomena; Revision to February 22, 2012, ACRS Meeting Federal Register Notice.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/17/
VL - 77
IS - 33
M3 - Proceeding
SP - 9707
EP - 9707
SN - 00976326
AB - The article reports that the meeting of the U.S. Advisory Committee on Reactor Safeguards Meeting related to thermal-hydraulics phenomena, which was scheduled to be held on February 22, 2012, has been cancelled.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards -- Congresses
KW - HYDRAULICS
N1 - Accession Number: 71954453; Dias, Antonio F. 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 02/17/2012, Vol. 77 Issue 33, p9707; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards -- Congresses; Subject Term: HYDRAULICS; Number of Pages: 1/6p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Reliability and PRA; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/21/
VL - 77
IS - 34
M3 - Proceeding
SP - 10003
EP - 10003
SN - 00976326
AB - The article offers information on a meeting of the Advisory Committee on Reactor Safeguards of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on March 7, 2012.
KW - MEETINGS
KW - NUCLEAR reactors -- Congresses
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 72324899; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 2/21/2012, Vol. 77 Issue 34, p10003; Thesaurus Term: MEETINGS; Subject Term: NUCLEAR reactors -- Congresses ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2/5p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Pickett, Douglas V.
T1 - Calvert Cliffs Nuclear Power Plant, LLC; Notice of Withdrawal of Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/23/
VL - 77
IS - 36
M3 - Article
SP - 10784
EP - 10784
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission to declare that the Calvert Cliffs Nuclear Power Plant, Maryland can withdraw its application regarding a proposed amendment in the Renewed Facility Operating License.
KW - LICENSES
KW - U.S. Nuclear Regulatory Commission
KW - CALVERT Cliffs Nuclear Power Plant (Md.)
N1 - Accession Number: 72336554; Pickett, Douglas V. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch I-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 2/23/2012, Vol. 77 Issue 36, p10784; Thesaurus Term: LICENSES ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: CALVERT Cliffs Nuclear Power Plant (Md.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2/5p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
AU - Haney, Catherine
T1 - Order Approving Application Regarding Proposed Corporate Merger and Indirect Transfer of Licenses.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/24/
VL - 77
IS - 37
M3 - Article
SP - 11165
EP - 11167
SN - 00976326
AB - The article offers information on an order passed by the U.S. Nuclear Regulatory Commission (NRC) that approves the application regarding proposed corporate merger and indirect transfer of licenses. It discusses the application for merger and indirect transfer of licenses of received by several corporations including Calvert Cliffs Nuclear Power Plant LLC, Exelon Generation Company LLC, and EDF Inc.
KW - CONSOLIDATION & merger of corporations
KW - LICENSES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - EDF Inc.
KW - CALVERT Cliffs Nuclear Power Plant LLC
KW - EXELON Generation Co. LLC
N1 - Accession Number: 72422527; Evans, Michele G. 1; Haney, Catherine 2; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; 2: Director, Office of Nuclear Material Safety and Safeguards; Issue Info: 2/24/2012, Vol. 77 Issue 37, p11165; Thesaurus Term: CONSOLIDATION & merger of corporations; Thesaurus Term: LICENSES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: EDF Inc. ; Company/Entity: CALVERT Cliffs Nuclear Power Plant LLC ; Company/Entity: EXELON Generation Co. LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=72422527&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - In the Matter of Exelon Corporation; Constellation Energy Group, Inc.; Nine Mile Nuclear Station, LLC; Nine Mile Point Nuclear Station, Units 1 and 2; Order Approving Application Regarding Proposed Corporate Merger and Indirect Transfer of Licenses.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/24/
VL - 77
IS - 37
M3 - Article
SP - 11168
EP - 11169
SN - 00976326
AB - The article offers information on an order passed by the U.S. Nuclear Regulatory Commission (NRC) that approves the application regarding proposed corporate merger and indirect transfer of licenses. It discusses the application for merger and indirect transfer of licenses of received by several corporations including Exelon Corp., Constellation Energy Group Inc., and Mile Nuclear Station LLC.
KW - CONSOLIDATION & merger of corporations
KW - LICENSES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - EXELON Corp.
KW - CONSTELLATION Energy Group Inc.
N1 - Accession Number: 72422528; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 2/24/2012, Vol. 77 Issue 37, p11168; Thesaurus Term: CONSOLIDATION & merger of corporations; Thesaurus Term: LICENSES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: EXELON Corp. Ticker: EXC ; Company/Entity: CONSTELLATION Energy Group Inc. Ticker: CEG; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=72422528&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - In the Matter of Exelon Corporation; Constellation Energy Group, Inc.; R.E. Ginna Nuclear Power Plant, LLC; R.E. Ginna Nuclear Power Plant; R.E. Ginna Independent Spent Fuel Storage Installation; Order Approving Application Regarding Proposed Corporate Merger and Indirect Transfer of License
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/24/
VL - 77
IS - 37
M3 - Article
SP - 11169
EP - 11171
SN - 00976326
AB - The article offers information on an order passed by the U.S. Nuclear Regulatory Commission (NRC) that approves the application regarding proposed corporate merger and indirect transfer of licenses. It discusses the application for merger and indirect transfer of licenses of received by several corporations including Exelon Corp., Constellation Energy Group Inc., R.E. Ginna Nuclear Power Plant LLC, and R.E. Ginna Nuclear Power Plan.
KW - CONSOLIDATION & merger of corporations
KW - LICENSES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - R.E. Ginna Nuclear Power Plant (N.Y.)
KW - EXELON Corp.
KW - CONSTELLATION Energy Group Inc.
N1 - Accession Number: 72422529; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 2/24/2012, Vol. 77 Issue 37, p11169; Thesaurus Term: CONSOLIDATION & merger of corporations; Thesaurus Term: LICENSES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: R.E. Ginna Nuclear Power Plant (N.Y.) ; Company/Entity: EXELON Corp. Ticker: EXC ; Company/Entity: CONSTELLATION Energy Group Inc. Ticker: CEG; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=72422529&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Wrona, David J.
T1 - License Renewal Application for Callaway Plant, Unit 1, Union Electric Company.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/24/
VL - 77
IS - 37
M3 - Proceeding
SP - 11171
EP - 11173
SN - 00976326
AB - The article offers information on the U.S. Nuclear Regulatory Commission's conference to be held on March 14, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
N1 - Accession Number: 72422530; Wrona, David J. 1; Affiliations: 1: Chief, Projects Branch 2, Division of License Renewal, Office of Nuclear Reactor Regulation; Issue Info: 2/24/2012, Vol. 77 Issue 37, p11171; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Delligatti, Mark S.
T1 - Renewal of Facility Operating License No. NPF-30, Union Electric Company, Callaway Plant, Unit 1.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/24/
VL - 77
IS - 37
M3 - Article
SP - 11173
EP - 11175
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) requesting an application for petitions for leave to intervene in matters related to the renewal of facility operating license number NPF-30. It states that NRC is considering an application for the renewal of an operating license that authorizes Union Electric Co. to operate its Callaway nuclear plant. It further states that requests for a hearing must be submitted within 60 days of publishing this notice.
KW - LICENSES
KW - NUCLEAR power plants
KW - PETITIONS
KW - NUCLEAR facilities
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - UNION Electric Co.
N1 - Accession Number: 72422531; Delligatti, Mark S. 1; Affiliations: 1: Acting Deputy Director, Division of License Renewal, Office of Nuclear Reactor Regulation; Issue Info: 2/24/2012, Vol. 77 Issue 37, p11173; Thesaurus Term: LICENSES; Thesaurus Term: NUCLEAR power plants; Subject Term: PETITIONS; Subject Term: NUCLEAR facilities; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: UNION Electric Co. DUNS Number: 004842845; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=72422531&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Sanders, Carleen J.
T1 - Central Vermont Public Service Corporation, Millstone Power Station, Unit 3; Notice of Consideration of Approval of Application Regarding Proposed Acquisition and Opportunity for a Hearing.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/27/
VL - 77
IS - 38
M3 - Article
SP - 11596
EP - 11598
SN - 00976326
AB - The article reports that Central Vermont Public Service Corp. has filed an application with the U.S. Nuclear Regulatory Commission (NRC) requesting to transfer the company's license for Dominion Nuclear Inc. to Gas Métro Ltd. It states that the transfer of license has been demanded in accordance with the U.S. Code of Federal Regulations. It further mentions that the public comments have been invited regarding the application by the NRC till March 28, 2012.
KW - LICENSES
KW - FEDERAL regulation
KW - PUBLIC opinion
KW - UNITED States
KW - CENTRAL Vermont Public Service Corp.
KW - U.S. Nuclear Regulatory Commission
KW - DOMINION Nuclear Inc.
N1 - Accession Number: 73068901; Sanders, Carleen J. 1; Affiliations: 1: Project Manager, Plant Licensing Branch I- 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 2/27/2012, Vol. 77 Issue 38, p11596; Thesaurus Term: LICENSES; Thesaurus Term: FEDERAL regulation; Thesaurus Term: PUBLIC opinion; Subject: UNITED States ; Company/Entity: CENTRAL Vermont Public Service Corp. DUNS Number: 007939614 Ticker: CV ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DOMINION Nuclear Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73068901&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Final Staff Guidance, Revision 4 to Standard Review Plan; Section 8.1 on Electric Power--Introduction.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/28/
VL - 77
IS - 39
M3 - Article
SP - 12086
EP - 12087
SN - 00976326
AB - The article provides information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding revision of reports related to nuclear power plants. The reports has been issued to facilitate timely implementation of staff guidance and to review licenses related to operating reactors. The interested individuals are required to contact Amy E. Cubbage, chief of policy branch of the NRC or electronic mail can be sent at amy.cubbage@nrc.gov for detail information.
KW - NUCLEAR power plants
KW - LICENSES
KW - EMAIL
KW - NUCLEAR reactors
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - CUBBAGE, Amy E.
N1 - Accession Number: 73171676; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors.; Issue Info: 2/28/2012, Vol. 77 Issue 39, p12086; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: EMAIL; Subject Term: NUCLEAR reactors; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; People: CUBBAGE, Amy E.; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73171676&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Morgan-Butler, Kimyata
T1 - Proposed Generic Communication; Regulatory Issue Summary 2012-XX: Developing Inservice Testing and Inservice Inspection Programs.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/28/
VL - 77
IS - 39
M3 - Article
SP - 12089
EP - 12092
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission (NRC) is soliciting public comments on a draft regulatory issue related to licenses, certifications and approval for nuclear power plants. This step has been taken by NRC for in-service inspection and in-service testing programs during 120 months interval following nuclear power plant startup. The NRC is seeking comments on this draft by April 13, 2012 via electronic mail, fax or through hand delivery.
KW - PUBLIC opinion
KW - NUCLEAR power plants
KW - LICENSES
KW - EMAIL
KW - COMMISSIONING
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73171680; Morgan-Butler, Kimyata 1; Affiliations: 1: Acting Chief, Generic Communications Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 2/28/2012, Vol. 77 Issue 39, p12089; Thesaurus Term: PUBLIC opinion; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: EMAIL; Subject Term: COMMISSIONING; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73171680&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Tonacci, Mark
T1 - Vogtle Electric Generating Plant, Units 3 and 4; Issuance of Combined Licenses and Limited Work Authorizations and Record of Decision.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/29/
VL - 77
IS - 40
M3 - Article
SP - 12332
EP - 12332
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding issuance of combined licenses to Southern Nuclear Operating Co., Oglethorpe Power Corp., Municipal Electric Authority of Georgia and the City of Dalton, Georgia for construction and operation of nuclear power plants. The notice has been issued in accordance with the Atomic Energy Act of 1954.
KW - NUCLEAR power plants
KW - LICENSES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - SOUTHERN Nuclear Operating Co.
KW - OGLETHORPE Power Corp.
KW - MUNICIPAL Electric Authority of Georgia
N1 - Accession Number: 73069131; Tonacci, Mark 1; Affiliations: 1: Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors.; Issue Info: 2/29/2012, Vol. 77 Issue 40, p12332; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: SOUTHERN Nuclear Operating Co. DUNS Number: 790778997 ; Company/Entity: OGLETHORPE Power Corp. DUNS Number: 073460305 ; Company/Entity: MUNICIPAL Electric Authority of Georgia; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73069131&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Smith, Brian W.
T1 - Special Nuclear Material License Amendment From Louisiana Energy Services, LLC, for the National Enrichment Facility, Hobbs, NM.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/02/29/
VL - 77
IS - 40
M3 - Article
SP - 12333
EP - 12335
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission (NRC) has decided to amend special nuclear material license given to Louisiana Energy Services for operating a uranium enrichment facility in Eunice Mexico. The proposed license will be extended from June 22, 2036, to June 9, 2040. Information on an environmental assessment prepared by NRC for Louisiana Energy Services is presented.
KW - NUCLEAR power plants
KW - LICENSES
KW - ENVIRONMENTAL impact analysis
KW - URANIUM enrichment
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - LOUISIANA Energy Services (Company)
N1 - Accession Number: 73069132; Smith, Brian W. 1; Affiliations: 1: Chief, Uranium Enrichment Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission.; Issue Info: 2/29/2012, Vol. 77 Issue 40, p12333; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: ENVIRONMENTAL impact analysis; Subject Term: URANIUM enrichment; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: LOUISIANA Energy Services (Company); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73069132&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - SMITH, TYSON
AU - CAMPBELL, TISON
T1 - The outlook for nuclear power across the United States and globally.
JO - Trends (15339556)
JF - Trends (15339556)
Y1 - 2012/03//Mar/Apr2012
VL - 43
IS - 4
M3 - Article
SP - 10
EP - 11
SN - 15339556
AB - The article focuses on nuclear power in the U.S. and globally. It states that increase in electricity demand and concerns regarding carbon dioxide emissions have revived interest of the U.S. in its nuclear power industry. It mentions that outlook for this industry is influenced by natural gas prices and there is interest in new plants due to incentives in the Energy Policy Act of 2005 in form of tax credits. It highlights that there is interest in nuclear energy globally.
KW - NUCLEAR energy
KW - ELECTRICITY
KW - CARBON dioxide mitigation
KW - TAX credits
KW - NATURAL gas -- Sales & prices
KW - UNITED States
N1 - Accession Number: 76114339; SMITH, TYSON 1; Email Address: trsmith@winston.com CAMPBELL, TISON 2; Email Address: tison.campbell@nrc.gov; Affiliation: 1: Partner in the Nuclear Energy Practice Group of Winston & Strawn LLP 2: Attorney at the U.S. Nuclear Regulatory Commission; Source Info: Mar/Apr2012, Vol. 43 Issue 4, p10; Subject Term: NUCLEAR energy; Subject Term: ELECTRICITY; Subject Term: CARBON dioxide mitigation; Subject Term: TAX credits; Subject Term: NATURAL gas -- Sales & prices; Subject Term: UNITED States; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 486210 Pipeline Transportation of Natural Gas; NAICS/Industry Codes: 221210 Natural Gas Distribution; Number of Pages: 2p; Document Type: Article; Full Text Word Count: 1769
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=76114339&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Leeds, Eric J.
T1 - Virgina Electric and Power Company; Receipt of Request for Action.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/02/
VL - 77
IS - 42
M3 - Article
SP - 12887
EP - 12888
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding a petition submitted by the petitioner Thomas Saporito to take action against Virginia Electric and Power Co.'s North Anna power station. The petitioner requested the NRC to take escalated enforcement action against the company's licensee and suspend, or revoke the operating licenses and also impose a penalty of one million U.S. dollars on the company.
KW - LICENSES
KW - FINES (Penalties)
KW - PETITIONS
KW - ENFORCEMENT
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - VIRGINIA Electric & Power Co.
KW - SAPORITO, Thomas
N1 - Accession Number: 73171998; Leeds, Eric J. 1; Affiliations: 1: Director, Office of Nuclear Reactor Regulation; Issue Info: 3/2/2012, Vol. 77 Issue 42, p12887; Thesaurus Term: LICENSES; Thesaurus Term: FINES (Penalties); Subject Term: PETITIONS; Subject Term: ENFORCEMENT; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: VIRGINIA Electric & Power Co. DUNS Number: 007941446 Ticker: VEA; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; People: SAPORITO, Thomas; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73171998&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Bradford, Peter
T1 - Energy policy: The nuclear landscape.
JO - Nature
JF - Nature
Y1 - 2012/03/08/
VL - 483
IS - 7388
M3 - Opinion
SP - 151
EP - 152
PB - Nature Publishing Group
SN - 00280836
AB - The author reflects on how many nations are convince by the accident at Fukushima nuclear plant in Japan to eliminate the use of nuclear power globally. The author highlights the dramatic impact of the disaster in Fukushima on the nuclear energy policies in other countries. He also mentions the other factors challenging the use of nuclear power including the long-term gas prices, prices forecasts and electricity demand.
KW - FUKUSHIMA Nuclear Accident, Fukushima, Japan, 2011
KW - NUCLEAR energy -- Government policy
KW - ENERGY policy
KW - PETROLEUM products -- Sales & prices
KW - FUKUSHIMA-ken (Japan)
KW - JAPAN
N1 - Accession Number: 72680238; Bradford, Peter 1; Affiliation: 1: Vermont Law School, South Royalton, Vermont 05068, USA. He served on the US Nuclear Regulatory Commission in 1977-82.; Source Info: 3/8/2012, Vol. 483 Issue 7388, p151; Subject Term: FUKUSHIMA Nuclear Accident, Fukushima, Japan, 2011; Subject Term: NUCLEAR energy -- Government policy; Subject Term: ENERGY policy; Subject Term: PETROLEUM products -- Sales & prices; Subject Term: FUKUSHIMA-ken (Japan); Subject Term: JAPAN; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 911910 Other federal government public administration; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Illustrations: 1 Color Photograph, 1 Graph; Document Type: Opinion
L3 - 10.1038/483151a
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=72680238&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Martin, Robert E.
T1 - Facility Operating License Amendment From Southern Nuclear Operating, Inc., Joseph M. Farley Nuclear Plant, Units 1 and 2.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/09/
VL - 77
IS - 47
M3 - Article
SP - 14441
EP - 14444
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) in order to declare the amendment of the Facility Operating License issued to Southern Nuclear Operating Co. regarding its nuclear plant located in Houston County, Alabama. The amendments will be declared in accordance with the U.S. Code of Federal Regulations. The public comments have been invited regarding the amendments till March 23, 2012 by the NRC.
KW - LICENSES
KW - NUCLEAR power plants
KW - FEDERAL regulation
KW - PUBLIC opinion
KW - LEGISLATIVE amendments
KW - ALABAMA
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - SOUTHERN Nuclear Operating Co.
N1 - Accession Number: 73770299; Martin, Robert E. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch II-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 3/9/2012, Vol. 77 Issue 47, p14441; Thesaurus Term: LICENSES; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: FEDERAL regulation; Thesaurus Term: PUBLIC opinion; Subject Term: LEGISLATIVE amendments; Subject Term: ALABAMA; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: SOUTHERN Nuclear Operating Co. DUNS Number: 790778997; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73770299&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Galloway, Melanie A.
T1 - Changes to the Generic Aging Lessons Learned (GALL) Report Revision 2 AMP XI.M41, ''Buried and Underground Piping and Tanks''.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/09/
VL - 77
IS - 47
M3 - Article
SP - 14446
EP - 14447
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) to invite public comments on the Draft License Renewal Interim Staff Guidance for the underground piping and tanks aging management programs. The license has been requested in accordance with the U.S. Code of Federal Regulations. The public comments have been invited regarding the revisions till April 9, 2012 by the NRC.
KW - PUBLIC opinion
KW - LICENSES
KW - FEDERAL regulation
KW - PIPING
KW - TANKS
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73770302; Galloway, Melanie A. 1; Affiliations: 1: Acting Director, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 3/9/2012, Vol. 77 Issue 47, p14446; Thesaurus Term: PUBLIC opinion; Thesaurus Term: LICENSES; Thesaurus Term: FEDERAL regulation; Subject Term: PIPING; Subject Term: TANKS; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237110 Water and Sewer Line and Related Structures Construction; NAICS/Industry Codes: 238220 Plumbing, Heating, and Air-Conditioning Contractors; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73770302&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Jolicoeur, John R.
T1 - Model Safety Evaluation for Plant- Specific Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 1, ''Provide Risk- Informed Extended Completion Times--RITSTF Initiative 4B''.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/15/
VL - 77
IS - 51
M3 - Article
SP - 15399
EP - 15399
SN - 00976326
AB - The article provides information on a notice issued by the U.S. Nuclear Regulatory Commission regarding the availability of the model safety evaluation for nuclear power plants technical specifications. It states that the notice has been issued to provide information on risks during completion times. Information on the Risk-Informed Completion Time Program is presented.
KW - NUCLEAR power plants
KW - RISK assessment
KW - SPECIFICATIONS
KW - SAFETY measures
KW - ENGINEERING models
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73897001; Jolicoeur, John R. 1; Affiliations: 1: Chief, Licensing Processes Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 3/15/2012, Vol. 77 Issue 51, p15399; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: RISK assessment; Thesaurus Term: SPECIFICATIONS; Subject Term: SAFETY measures; Subject Term: ENGINEERING models; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73897001&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Vaidya, Bhalchandra
T1 - PPL Susquehanna, LLC; Application and Amendment to Facility Operating License Involving: Proposed No Significant Hazards Consideration Determination.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/16/
VL - 77
IS - 52
M3 - Article
SP - 15814
EP - 15818
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission is soliciting public comments on amendment of a license related to operation of the Susquehanna Steam Electric Station in Luzerne County, Pennsylvania. This step has been taken to de-energize the electric power station and for maintenance activities. The NRC is soliciting public comments by April 16, 2012 via electronic mail or in writings.
KW - PUBLIC opinion
KW - STEAM power plants
KW - EMAIL
KW - MAINTENANCE & repair
KW - LUZERNE County (Pa.)
KW - PENNSYLVANIA
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73897161; Vaidya, Bhalchandra 1; Affiliations: 1: Project Manager, Plant Licensing Branch I- 1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 3/16/2012, Vol. 77 Issue 52, p15814; Thesaurus Term: PUBLIC opinion; Thesaurus Term: STEAM power plants; Thesaurus Term: EMAIL; Subject Term: MAINTENANCE & repair; Subject: LUZERNE County (Pa.); Subject: PENNSYLVANIA; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221330 Steam and Air-Conditioning Supply; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 5p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73897161&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Galloway, Melanie A.
T1 - License Renewal Interim Staff Guidance LR-ISG-2011-05: Ongoing Review of Operating Experience.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/16/
VL - 77
IS - 52
M3 - Article
SP - 15818
EP - 15819
SN - 00976326
AB - The article presents information on an interim staff guidance issued by the U.S. Nuclear Regulatory Commission regarding issuance of a license for reviewing operating experience at the nuclear power plants. Information on a public meeting organized by NRC on October 12, 2011 on this issue is presented. The NRC received a comment from Exelon Generation Co. LLC for this guidance.
KW - STANDARD operating procedure
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC meetings
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - EXELON Generation Co. LLC
N1 - Accession Number: 73897162; Galloway, Melanie A. 1; Affiliations: 1: Acting Director, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 3/16/2012, Vol. 77 Issue 52, p15818; Thesaurus Term: STANDARD operating procedure; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: PUBLIC meetings; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: EXELON Generation Co. LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73897162&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Leeds, Eric J.
AU - Johnson, Michael R.
T1 - In the Matter of All Power Reactor Licensees and Holders of Construction Permits in Active Or Deferred Status: Order Modifying Licenses With Regard To Reliable Spent Fuel Pool Instrumentation (Effective Immediately).
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/19/
VL - 77
IS - 53
M3 - Article
SP - 16082
EP - 16090
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding the identification of licensees and construction permitholders for constructing and operating nuclear power plants in the country. The identification will be made in accordance with the U.S. Atomic Energy Act of 1954 and the Code of Federal Regulations. The public comments have been invited till April 8, 2012 by the NRC regarding the identification.
KW - NUCLEAR power plants
KW - LICENSES
KW - FEDERAL regulation
KW - PUBLIC opinion
KW - NUCLEAR energy -- Law & legislation -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73934781; Leeds, Eric J. 1; Johnson, Michael R. 2; Affiliations: 1: Director, Office of Nuclear Reactor Regulation.; 2: Director, Office of New Reactors.; Issue Info: 3/19/2012, Vol. 77 Issue 53, p16082; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: FEDERAL regulation; Thesaurus Term: PUBLIC opinion; Subject Term: NUCLEAR energy -- Law & legislation -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 9p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=73934781&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Leeds, Eric J.
AU - Johnson, Michael R.
T1 - Order Modifying Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Effective Immediately).
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/19/
VL - 77
IS - 53
M3 - Article
SP - 16091
EP - 16098
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding identification of licensees and construction permitholders for constructing and operating nuclear power plants. The identification will be made in accordance with the U.S. Atomic Energy Act of 1954 and the Code of Federal Regulations. The public comments have been invited till April 8, 2012 by the NRC regarding the identification.
KW - NUCLEAR power plants
KW - LICENSES
KW - FEDERAL regulation
KW - PUBLIC opinion
KW - NUCLEAR energy -- Law & legislation -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73934782; Leeds, Eric J. 1; Johnson, Michael R.; Affiliations: 1: Director, Office of Nuclear Reactor Regulation.; Issue Info: 3/19/2012, Vol. 77 Issue 53, p16091; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: FEDERAL regulation; Thesaurus Term: PUBLIC opinion; Subject Term: NUCLEAR energy -- Law & legislation -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 8p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Leeds, Eric J.
T1 - In the Matter of All Operating Boiling Water Reactor Licensees With Mark I and Mark II Containments; Order Modifying Licenses With Regard To Reliable Hardened Containment Vents (Effective Immediately).
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/19/
VL - 77
IS - 53
M3 - Article
SP - 16098
EP - 16105
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding identification of licensees and construction permitholders for constructing and operating nuclear power plants. The identification will be made in accordance with the U.S. Atomic Energy Act of 1954 and the Code of Federal Regulations. The public comments have been invited till April 8, 2012 by the NRC regarding the identification.
KW - NUCLEAR power plants
KW - LICENSES
KW - FEDERAL regulation
KW - PUBLIC opinion
KW - NUCLEAR energy -- Law & legislation -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73934783; Leeds, Eric J. 1; Affiliations: 1: Director, Office of Nuclear Reactor Regulation.; Issue Info: 3/19/2012, Vol. 77 Issue 53, p16098; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: FEDERAL regulation; Thesaurus Term: PUBLIC opinion; Subject Term: NUCLEAR energy -- Law & legislation -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 8p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Galloway, Melanie A.
T1 - Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/20/
VL - 77
IS - 54
M3 - Article
SP - 16270
EP - 16271
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) with an intention to invite public comments on draft license renewal interim staff guidance regarding aging management of stainless steel structures and components exposed to treated borated water. The invitation will be made in accordance with the U.S. Code of Federal Regulations. The public comments have been invited till May 21, 2012 by the NRC regarding the draft license.
KW - PUBLIC opinion
KW - LICENSES
KW - FEDERAL regulation
KW - STAINLESS steel
KW - PRESSURIZED water reactors
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 73934910; Galloway, Melanie A. 1; Affiliations: 1: Acting Director, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 3/20/2012, Vol. 77 Issue 54, p16270; Thesaurus Term: PUBLIC opinion; Thesaurus Term: LICENSES; Thesaurus Term: FEDERAL regulation; Subject Term: STAINLESS steel; Subject Term: PRESSURIZED water reactors ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 331110 Iron and Steel Mills and Ferroalloy Manufacturing; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Wrona, David J.
T1 - License Renewal Application for Indian Point Nuclear Generating Units 2 and 3; Entergy Nuclear Operations, Inc.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/20/
VL - 77
IS - 54
M3 - Article
SP - 16278
EP - 16278
SN - 00976326
AB - The article focuses on an application submitted by Entergy Nuclear Operations Inc. with the U.S. Federal Energy Regulatory Commission (FERC) of the U.S. Department of Energy with an intention to request renewal of facility operating licenses. The FERC will prepare an Environmental Impact Statement as per the U.S. National Environmental Policy Act of 1969 and Code of Federal Regulations. The public comments have been invited by the FERC regarding the request for renewal of licenses.
KW - LICENSES
KW - FEDERAL regulation
KW - PUBLIC opinion
KW - ENVIRONMENTAL impact statements
KW - ENTERGY Nuclear Operations Inc.
KW - UNITED States. Federal Energy Regulatory Commission
KW - UNITED States. Dept. of Energy
KW - UNITED States. National Environmental Policy Act of 1969
N1 - Accession Number: 73934912; Wrona, David J. 1; Affiliations: 1: Chief, Projects Branch 2, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 3/20/2012, Vol. 77 Issue 54, p16278; Thesaurus Term: LICENSES; Thesaurus Term: FEDERAL regulation; Thesaurus Term: PUBLIC opinion; Subject Term: ENVIRONMENTAL impact statements ; Company/Entity: ENTERGY Nuclear Operations Inc. ; Company/Entity: UNITED States. Federal Energy Regulatory Commission ; Company/Entity: UNITED States. Dept. of Energy ; Company/Entity: UNITED States. National Environmental Policy Act of 1969; NAICS/Industry Codes: 926110 Administration of General Economic Programs; Number of Pages: 2/3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Jolicoeur, John R.
T1 - Proposed Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-522, Revision 0, ''Revise Ventilation System Surveillance Requirements To Operate for 10 Hours per Month''.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/22/
VL - 77
IS - 56
M3 - Article
SP - 16869
EP - 16870
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) with an intention to invite public comments on the proposed model safety evaluation (SE) for plant-specific adoption of Technical Specifications Task Force. The proposed SE has been intended to revise the Improved Standard Technical Specification. The public comments have been invited by the NRC till April 23, 2012 regarding the SE.
KW - PUBLIC opinion
KW - TASK forces
KW - SPECIFICATIONS
KW - SAFETY
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 74019087; Jolicoeur, John R. 1; Affiliations: 1: Chief, Licensing Processes Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 3/22/2012, Vol. 77 Issue 56, p16869; Thesaurus Term: PUBLIC opinion; Thesaurus Term: TASK forces; Thesaurus Term: SPECIFICATIONS; Subject Term: SAFETY; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Regulatory Policies & Practices; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/28/
VL - 77
IS - 60
M3 - Proceeding
SP - 18873
EP - 18873
SN - 00976326
AB - The article offers information on a meeting of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on April 25, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - ROCKVILLE (Md.)
N1 - Accession Number: 74076566; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 3/28/2012, Vol. 77 Issue 60, p18873; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject: ROCKVILLE (Md.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Quichocho, Jessie F.
T1 - Environmental Assessment and Finding of No Significant Impact for License Renewal for the Reed College/ Reed College Research Reactor.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/03/30/
VL - 77
IS - 62
M3 - Article
SP - 19362
EP - 19366
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) to declare the issuance of a license for the Reed Research Reactor (RRR), Portland, Oregon. The issuance will be declared in accordance with the U.S. National Environmental Policy of 1969 and the U.S. Code of Federal Regulations. The NRC has conducted an environmental impact analysis and drafted an Environmental Impact Statement for the RRR.
KW - LICENSES
KW - FEDERAL regulation
KW - ENVIRONMENTAL impact analysis
KW - RESEARCH reactors
KW - ENVIRONMENTAL impact statements
KW - PORTLAND (Or.)
KW - OREGON
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - UNITED States. National Environmental Policy Act of 1969
N1 - Accession Number: 74124328; Quichocho, Jessie F. 1; Affiliations: 1: Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 3/30/2012, Vol. 77 Issue 62, p19362; Thesaurus Term: LICENSES; Thesaurus Term: FEDERAL regulation; Thesaurus Term: ENVIRONMENTAL impact analysis; Subject Term: RESEARCH reactors; Subject Term: ENVIRONMENTAL impact statements; Subject: PORTLAND (Or.); Subject: OREGON; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: UNITED States. National Environmental Policy Act of 1969; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 5p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Devlin, S.
AU - Isacks, B. L.
AU - Pritchard, M. E.
AU - Barnhart, W. D.
AU - Lohman, R. B.
T1 - Depths and focal mechanisms of crustal earthquakes in the central Andes determined from teleseismic waveform analysis and InSAR.
JO - Tectonics
JF - Tectonics
Y1 - 2012/04//
VL - 31
IS - 2
M3 - Article
SP - n/a
EP - n/a
SN - 02787407
AB - We investigate the depths of crustal earthquakes (<80 km depth) of the central Andes (5°S to 35°S) to constrain the relationship between earthquake locations and inferred faults. We assemble parameters from 138 moderate-sized (7.0 > Mw ≳ 5.5) earthquakes from the Global CMT catalog and previous work spanning 1944-2007. For 38 well-recorded events, we use teleseismic P and SH waveforms to model the strike, dip, rake, focal depth, and source time function. We use InSAR observations of surface deformation from 9 earthquakes to compare inferred fault parameters with the waveform inversions and global catalogs to assess their accuracies. While the depths from the InSAR and waveform analyses generally agree within error, horizontal and depth errors in global catalogs are 10 to 50 km, as found elsewhere. As noted in previous work, the majority of crustal earthquakes occur in the Eastern Cordillera and foreland regions of the central Andes, although a few normal and strike-slip earthquakes occur beneath the Altiplano plateau and in the forearc in southern Peru and northernmost Chile. We propose a new interpretation of one of the basement thrusts (Shira Mountain, Peru) as a pop up block on the basis of our new earthquake depths. We confirm that earthquakes in the flat slab areas of Peru and Argentina are within the sometimes aseismic lower crust. Lower crustal earthquakes are globally found in all types of tectonic settings only when the thermal lithosphere is more than 80 km thick and the amount of recent shortening/extension is <30%. [ABSTRACT FROM AUTHOR]
AB - Copyright of Tectonics is the property of Wiley-Blackwell and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Andes
KW - earthquake
KW - InSAR
KW - teleseismic waveform modeling
N1 - Accession Number: 87203447; Devlin, S. 1; Isacks, B. L. 2; Pritchard, M. E. 2; Barnhart, W. D. 2; Lohman, R. B. 2; Affiliations: 1: Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, D. C., USA; 2: Department of Earth and Atmospheric Sciences, Cornell University, Ithaca, New York, USA; Issue Info: 2012, Vol. 31 Issue 2, pn/a; Author-Supplied Keyword: Andes; Author-Supplied Keyword: earthquake; Author-Supplied Keyword: InSAR; Author-Supplied Keyword: teleseismic waveform modeling; Number of Pages: 33p; Document Type: Article
L3 - 10.1029/2011TC002914
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - DiFrancesco, Nicholas J.
T1 - Exelon Generation Company, LLC; Notice of Withdrawal of Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/03/
VL - 77
IS - 64
M3 - Article
SP - 20059
EP - 20059
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission to report that Exelon Generation Co. LLC has withdrawn its application seeking amendments in regulations for issuance of permit to conduct operations at the nuclear power plant station in LaSalle County, Illinois.
KW - NUCLEAR power plants
KW - LICENSES
KW - U.S. Nuclear Regulatory Commission
KW - EXELON Generation Co. LLC
N1 - Accession Number: 74166445; DiFrancesco, Nicholas J. 1; Affiliations: 1: Project Manager, Plant Licensing Branch 3- 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 4/3/2012, Vol. 77 Issue 64, p20059; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: EXELON Generation Co. LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Paige, Jason C.
T1 - License Amendment To Increase the Maximum Reactor Power Level, Florida Power & Light Company, Turkey Point, Units 3 and 4.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/03/
VL - 77
IS - 64
M3 - Article
SP - 20059
EP - 20070
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission to inform about an application filed by Florida Power and Light Co. seeking amendments in regulations for issuance of permit to conduct operations and to increase the maximum reactor power level at the Turkey Point nuclear power plant station in Florida. The draft of environmental assessment (EA) report on the influence of station prepared by the National Park Service is available for inspection.
KW - NUCLEAR power plants
KW - LICENSES
KW - ENVIRONMENTAL impact analysis
KW - NUCLEAR reactors -- Power distribution
KW - LEGISLATIVE amendments
KW - INSPECTION & review
KW - FLORIDA
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - FLORIDA Power & Light Co.
N1 - Accession Number: 74166446; Paige, Jason C. 1; Affiliations: 1: Project Manager, Plant Licensing Branch 2- 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 4/3/2012, Vol. 77 Issue 64, p20059; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: ENVIRONMENTAL impact analysis; Subject Term: NUCLEAR reactors -- Power distribution; Subject Term: LEGISLATIVE amendments; Subject Term: INSPECTION & review; Subject: FLORIDA; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: FLORIDA Power & Light Co.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 12p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Biweekly Notice of Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/03/
VL - 77
IS - 64
M3 - Article
SP - 20070
EP - 20077
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission to inform about the approved applications seeking amendments in regulations for issuance of permit to conduct operations at the nuclear power plant stations. The applicants include Entergy Nuclear Vermont Yankee and Entergy Nuclear Operations Inc. The amendments are in accordance with the U.S. Atomic Energy Act of 1954. The public comments have been invited within 60 days of the notice publication.
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - LEGISLATIVE amendments
KW - NUCLEAR energy
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - ENTERGY Nuclear Vermont Yankee LLC
KW - ENTERGY Nuclear Operations Inc.
N1 - Accession Number: 74166447; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 4/3/2012, Vol. 77 Issue 64, p20070; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Subject Term: LEGISLATIVE amendments; Subject Term: NUCLEAR energy; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: ENTERGY Nuclear Vermont Yankee LLC ; Company/Entity: ENTERGY Nuclear Operations Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 8p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Quichocho, Jessie F.
T1 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/10/
VL - 77
IS - 69
M3 - Article
SP - 21592
EP - 21593
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission is soliciting comments on guidelines regarding preparation and review of licensing applications related to non-power reactors. The guidelines issued by NRC are related to production of radioisotopes. The NRC is seeking public comments on these guidelines by May 10, 2012 via electronic mail or in writings.
KW - PUBLIC opinion
KW - LICENSES
KW - STANDARD operating procedure
KW - EMAIL
KW - NUCLEAR reactors
KW - RADIOISOTOPES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 74284848; Quichocho, Jessie F. 1; Affiliations: 1: Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 4/10/2012, Vol. 77 Issue 69, p21592; Thesaurus Term: PUBLIC opinion; Thesaurus Term: LICENSES; Thesaurus Term: STANDARD operating procedure; Thesaurus Term: EMAIL; Subject Term: NUCLEAR reactors; Subject Term: RADIOISOTOPES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Tonacci, Mark
T1 - V. C. Summer Nuclear Station, Units 2 and 3 Combined Licenses and Record of Decision.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/10/
VL - 77
IS - 69
M3 - Article
SP - 21593
EP - 21594
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding issuance of combined construction and operating license to South Carolina Electric and Gas Co. and Santee Cooper, South Carolina Public Service Authority for two new nuclear power plants at V. C. Summer Station in Jenkinsville, South Carolina. Information on a safety evaluation report and an environmental impact statement prepared by NRC is presented.
KW - NUCLEAR power plants
KW - LICENSES
KW - DESIGN & construction
KW - ENVIRONMENTAL impact statements
KW - SOUTH Carolina
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - SOUTH Carolina Electric & Gas Co.
KW - SOUTH Carolina Public Service Authority
N1 - Accession Number: 74284849; Tonacci, Mark 1; Affiliations: 1: Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors.; Issue Info: 4/10/2012, Vol. 77 Issue 69, p21593; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: DESIGN & construction; Subject Term: ENVIRONMENTAL impact statements; Subject: SOUTH Carolina; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: SOUTH Carolina Electric & Gas Co. ; Company/Entity: SOUTH Carolina Public Service Authority; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Stang, John
T1 - Duke Energy Carolinas, LLC; Environmental Assessment and Finding of No Significant Impact, Oconee Nuclear Station, Units 1, 2, and 3.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/10/
VL - 77
IS - 69
M3 - Article
SP - 21594
EP - 21595
SN - 00976326
AB - The article provides information on an application filed by Duke Energy Carolinas LLC to the U.S. Nuclear Regulatory Commission (NRC) for acquiring exemption for operating of the Oconee Nuclear Station in Oconee County in South Carolina. It states that the NRC has completed environmental assessment and also prepared environmental impact statement in this regard. The NRC has declared that operation of this plant will have no impact on the environment.
KW - ENVIRONMENTAL impact analysis
KW - NUCLEAR power plants -- Environmental aspects
KW - EXEMPTION (Law)
KW - ENVIRONMENTAL impact statements
KW - SOUTH Carolina
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - DUKE Energy Carolinas LLC
N1 - Accession Number: 74284850; Stang, John 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch II-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 4/10/2012, Vol. 77 Issue 69, p21594; Thesaurus Term: ENVIRONMENTAL impact analysis; Thesaurus Term: NUCLEAR power plants -- Environmental aspects; Subject Term: EXEMPTION (Law); Subject Term: ENVIRONMENTAL impact statements; Subject: SOUTH Carolina; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DUKE Energy Carolinas LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=74284850&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Morey, Dennis
T1 - Energy Northwest, Columbia Generating Station; Final Supplement 47 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/13/
VL - 77
IS - 72
M3 - Article
SP - 22361
EP - 22362
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding publication of a final plant specific supplement related to environmental impact statement for permit renewal of nuclear power plants. The notice has been issued to Columbia Generating Station, a nuclear power station Richland, Washington, for operating its nuclear power plants for additional 20 years.
KW - NUCLEAR power plants
KW - LICENSES
KW - ENVIRONMENTAL impact statements
KW - LAW & legislation
KW - SUPPLEMENTAL jurisdiction
KW - RICHLAND (Wash.)
KW - WASHINGTON (State)
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 74581787; Morey, Dennis 1; Affiliations: 1: Chief, Reactor Projects Branch 1, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 4/13/2012, Vol. 77 Issue 72, p22361; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: ENVIRONMENTAL impact statements; Subject Term: LAW & legislation; Subject Term: SUPPLEMENTAL jurisdiction; Subject: RICHLAND (Wash.); Subject: WASHINGTON (State); Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=74581787&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Howe, Allen G.
T1 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/17/
VL - 77
IS - 74
M3 - Article
SP - 22808
EP - 22823
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding issuance of a nuclear power plants facility operating license and any amendment made to these licenses. The NRC is soliciting public comments on this notice via electronic mail or in writings. This notice is applicable to the companies including Carolina Power and Light Co., Entergy Gulf States Louisiana LLC and Entergy Operations Inc.
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - EMAIL
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - CAROLINA Power & Light Co.
KW - ENTERGY Gulf States Louisiana LLC
KW - ENTERGY Operations Inc.
N1 - Accession Number: 74619624; Howe, Allen G. 1; Affiliations: 1: Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 4/17/2012, Vol. 77 Issue 74, p22808; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: CAROLINA Power & Light Co. DUNS Number: 006997217 Ticker: CPL ; Company/Entity: ENTERGY Gulf States Louisiana LLC ; Company/Entity: ENTERGY Operations Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 16p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=74619624&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Delligatti, Mark S.
T1 - Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/19/
VL - 77
IS - 76
M3 - Correction notice
SP - 23513
EP - 23513
SN - 00976326
AB - A correction to a notice issued by the U.S. Nuclear Regulatory Commission that was published in the March 20, 2012 issued of the journal is presented.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 74581899; Delligatti, Mark S. 1; Affiliations: 1: Deputy Director, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 4/19/2012, Vol. 77 Issue 76, p23513 ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Correction notice
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Stang, John
T1 - Duke Energy Carolinas, LLC; Notice of Withdrawal of Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/20/
VL - 77
IS - 77
M3 - Article
SP - 23766
EP - 23767
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission that granted the request of Duke Energy Carolina LLC to withdraw its application for proposed amendment to renewed licenses for facility operation.
KW - LICENSES
KW - U.S. Nuclear Regulatory Commission
KW - DUKE Energy Carolinas LLC
N1 - Accession Number: 74644739; Stang, John 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch II-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 4/20/2012, Vol. 77 Issue 77, p23766; Thesaurus Term: LICENSES ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DUKE Energy Carolinas LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=74644739&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Planning and Procedures; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/25/
VL - 77
IS - 80
M3 - Proceeding
SP - 24744
EP - 24744
SN - 00976326
AB - The article offers information on a meeting of the Advisory Committee on Reactor Safeguards Subcommittee on Planning and Procedures to be held in Maryland on May 9, 2012.
KW - MEETINGS
KW - ADVISORY boards
KW - NUCLEAR reactors -- Safety measures -- Congresses
KW - CONGRESSES
N1 - Accession Number: 74645113; Santos, Cayetano 1; Affiliations: 1: Chief, Reactor Safety Branch, Advisory Committee on Reactor Safeguards; Issue Info: 4/25/2012, Vol. 77 Issue 80, p24744; Thesaurus Term: MEETINGS; Thesaurus Term: ADVISORY boards; Subject Term: NUCLEAR reactors -- Safety measures -- Congresses; Subject Term: CONGRESSES; NAICS/Industry Codes: 541611 Administrative Management and General Management Consulting Services; Number of Pages: 1/2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=74645113&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Thermal Hydraulic Phenomena; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/04/25/
VL - 77
IS - 80
M3 - Proceeding
SP - 24745
EP - 24745
SN - 00976326
AB - The article offers information on a meeting of the Advisory Committee on Reactor Safeguards Subcommittee on Planning and Procedures to be held in Maryland from May 8-9, 2012.
KW - MEETINGS
KW - ADVISORY boards
KW - NUCLEAR reactors -- Safety measures -- Congresses
KW - CONGRESSES
N1 - Accession Number: 74645114; Santos, Cayetano 1; Affiliations: 1: Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 4/25/2012, Vol. 77 Issue 80, p24745; Thesaurus Term: MEETINGS; Thesaurus Term: ADVISORY boards; Subject Term: NUCLEAR reactors -- Safety measures -- Congresses; Subject Term: CONGRESSES; NAICS/Industry Codes: 541611 Administrative Management and General Management Consulting Services; Number of Pages: 1/2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=74645114&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Burbank, Malcolm B.
AU - Weaver, Thomas J.
AU - Williams, Barbara C.
AU - Crawford, Ronald L.
T1 - Urease Activity of Ureolytic Bacteria Isolated from Six Soils in which Calcite was Precipitated by Indigenous Bacteria.
JO - Geomicrobiology Journal
JF - Geomicrobiology Journal
Y1 - 2012/05//
VL - 29
IS - 4
M3 - Article
SP - 389
EP - 395
PB - Taylor & Francis Ltd
SN - 01490451
AB - Ten distinct and phylogenetically diverse bacterial strains able to produce urease constitutively, even in the presence of high levels of ammonia, were isolated. Each isolate was characterized with respect to morphology, growth conditions, 16S rRNA sequence identity and the urease specific activity each isolate was measured. At least one bacteria that was able to hydrolyze urea in the presence of high concentration of ammonia was isolated from each soil tested. These results indicate that constitutive production of urease is a common trait in soil bacteria. This makes the general application of biomineralization process based on stimulation of urea hydrolysis possible and potentially useful for a variety of soil bioengineering and environmental bioremediation applications. [ABSTRACT FROM AUTHOR]
AB - Copyright of Geomicrobiology Journal is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - UREASE
KW - SOIL microbiology
KW - CALCITE
KW - AMMONIA
KW - NUCLEOTIDE sequence
KW - BIOMINERALIZATION
KW - BIOREMEDIATION
KW - biocement
KW - calcite
KW - indigenous bacteria
KW - microbial induced calcite precipitation
KW - urease activity
N1 - Accession Number: 71347591; Burbank, Malcolm B. 1,2; Email Address: barbwill@uidaho.edu Weaver, Thomas J. 3 Williams, Barbara C. 4 Crawford, Ronald L. 5; Affiliation: 1: Environmental Biotechnology Institute, University of Idaho, USA 2: Department of Microbiology, Molecular Biology and Biochemistry, University of Idaho, USA 3: Geotechnical Engineer, U.S. Nuclear Regulatory Commission, USA 4: Department of Biological and Agricultural Engineering, University of Idaho, USA 5: Professor Emeritus, University of Idaho, USA; Source Info: 2012, Vol. 29 Issue 4, p389; Subject Term: UREASE; Subject Term: SOIL microbiology; Subject Term: CALCITE; Subject Term: AMMONIA; Subject Term: NUCLEOTIDE sequence; Subject Term: BIOMINERALIZATION; Subject Term: BIOREMEDIATION; Author-Supplied Keyword: biocement; Author-Supplied Keyword: calcite; Author-Supplied Keyword: indigenous bacteria; Author-Supplied Keyword: microbial induced calcite precipitation; Author-Supplied Keyword: urease activity; NAICS/Industry Codes: 325311 Nitrogenous Fertilizer Manufacturing; NAICS/Industry Codes: 325313 Chemical fertilizer (except potash) manufacturing; NAICS/Industry Codes: 424690 Other Chemical and Allied Products Merchant Wholesalers; NAICS/Industry Codes: 418410 Chemical (except agricultural) and allied product merchant wholesalers; NAICS/Industry Codes: 325612 Polish and Other Sanitation Good Manufacturing; NAICS/Industry Codes: 325610 Soap and cleaning compound manufacturing; NAICS/Industry Codes: 562910 Remediation Services; NAICS/Industry Codes: 212399 All Other Nonmetallic Mineral Mining; NAICS/Industry Codes: 212398 All other non-metallic mineral mining and quarrying; Number of Pages: 7p; Illustrations: 1 Diagram, 2 Charts; Document Type: Article
L3 - 10.1080/01490451.2011.575913
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=71347591&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Sieracki, Diane
T1 - A Spotlight on Safety Culture.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2012/05//May/Jun2012
VL - 30
IS - 3
M3 - Interview
SP - 32
EP - 33
PB - Presidents & Prime Ministers
SN - 08922055
AB - This article presents an interview with Diane Sieracki, Senior Safety Culture Program Manager in the Office of Enforcement (OE) at the U.S. Nuclear Regulatory Commission (NRC). When asked about how does the NRC train its staff for safety culture, she says that NRC provides formal training along with on-the-job training that involves participation in safety culture assessments. Sieracki says that NRC has sponsored a meeting with other government agencies to share experience in safety culture.
KW - Nuclear industry -- Safety measures
KW - Training
KW - Meetings
KW - United States
KW - U.S. Nuclear Regulatory Commission
KW - Sieracki, Diane -- Interviews
N1 - Accession Number: 77619093; Sieracki, Diane 1; Email Address: diane.sieracki@nrc.gov; Affiliations: 1: Senior Safety Culture Program Manager, Office of Enforcement (OE), U.S. Nuclear Regulatory Commission (NRC); Issue Info: May/Jun2012, Vol. 30 Issue 3, p32; Subject Term: Nuclear industry -- Safety measures; Subject Term: Training; Subject Term: Meetings; Subject: United States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; People: Sieracki, Diane -- Interviews; Number of Pages: 2p; Document Type: Interview
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Matthews, David B.
T1 - Progress Energy Florida; Final Environmental Impact Statement for Combined Licenses for Levy Nuclear Plant Units 1 and 2.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/03/
VL - 77
IS - 86
M3 - Article
SP - 26316
EP - 26317
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission and the U.S. Army Corps of Engineers to declare the availability of the proposed final environmental impact statement for public inspection related to the Levy Nuclear Plant in Levy County, Florida.
KW - NUCLEAR power plants
KW - ENVIRONMENTAL impact statements
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 75056242; Matthews, David B. 1; Affiliations: 1: Director, Division of New Reactor Licensing, Office of New Reactors; Issue Info: 5/3/2012, Vol. 77 Issue 86, p26316; Thesaurus Term: NUCLEAR power plants; Subject Term: ENVIRONMENTAL impact statements; Subject Term: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=75056242&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Duke Energy Carolinas, LLC., Oconee Nuclear Station, Units 1, 2, and 3 Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/03/
VL - 77
IS - 86
M3 - Article
SP - 26318
EP - 26321
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission to inform about an application filed by Duke Energy Carolinas LLC requesting amendments in the regulations for renewal of license to operate the Oconee Nuclear Power stations in South Carolina. The amendments are in accordance with the U.S. Atomic Energy Act of 1954. The exemption has been approved after the review of no significance impact on the public health and safety.
KW - NUCLEAR power plants
KW - LICENSES
KW - NUCLEAR facilities -- Law & legislation
KW - PUBLIC health
KW - SOUTH Carolina
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - DUKE Energy Carolinas LLC
N1 - Accession Number: 75056244; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 5/3/2012, Vol. 77 Issue 86, p26318; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: NUCLEAR facilities -- Law & legislation; Subject Term: PUBLIC health; Subject: SOUTH Carolina; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DUKE Energy Carolinas LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 525120 Health and Welfare Funds; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=75056244&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Boger, Bruce A.
T1 - Virginia Electric and Power Company.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/03/
VL - 77
IS - 86
M3 - Article
SP - 26321
EP - 26323
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding the issuance of decision by the Director of the Office of Nuclear Reactor Regulation (NRR) with respect to a petition filed on September 8, 2011 by petitioner Thomas Saporito. The petition requested the NRC to take enforcement action against the licensee and revoke or suspend the operating licenses for Virginia Electric and Power Co's North Anna Power Station in Louisa County, Virginia.
KW - LICENSES
KW - PETITIONS
KW - LAW enforcement
KW - NUCLEAR reactors
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - VIRGINIA Electric & Power Co.
KW - SAPORITO, Thomas
N1 - Accession Number: 75056246; Boger, Bruce A. 1; Affiliations: 1: Deputy Director, Reactor Safety Programs, Office of Nuclear Reactor Regulation; Issue Info: 5/3/2012, Vol. 77 Issue 86, p26321; Thesaurus Term: LICENSES; Subject Term: PETITIONS; Subject Term: LAW enforcement; Subject Term: NUCLEAR reactors; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: VIRGINIA Electric & Power Co. DUNS Number: 007941446 Ticker: VEA; NAICS/Industry Codes: 922190 Other Justice, Public Order, and Safety Activities; NAICS/Industry Codes: 922120 Police Protection; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; People: SAPORITO, Thomas; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=75056246&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Quichocho, Jessie F.
T1 - Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/03/
VL - 77
IS - 86
M3 - Article
SP - 26321
EP - 26321
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission regarding the renewal of facility operating license for Reed Research Nuclear Reactor, a research nuclear reactor located on campus at Reed College in Portland, Oregon. The renewed facility operating license is issued in accordance with the standards and requirements of the U.S. Atomic Energy Act of 1954.
KW - LICENSES
KW - NUCLEAR reactors
KW - NUCLEAR energy -- Law & legislation -- United States
KW - PORTLAND (Or.)
KW - OREGON
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - REED College (Portland, Or.)
N1 - Accession Number: 75056245; Quichocho, Jessie F. 1; Affiliations: 1: Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 5/3/2012, Vol. 77 Issue 86, p26321; Thesaurus Term: LICENSES; Subject Term: NUCLEAR reactors; Subject Term: NUCLEAR energy -- Law & legislation -- United States; Subject: PORTLAND (Or.); Subject: OREGON; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: REED College (Portland, Or.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=75056245&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Florida Power and Light Company, St. Lucie Plant, Unit No. 2, Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/07/
VL - 77
IS - 88
M3 - Article
SP - 26793
EP - 26795
SN - 00976326
AB - The article presents information on an application filed by Florida Power & Light Co. to the U.S. Nuclear Regulatory Commission (NRC) for exemption related to facility operating unit No. 2. The request for exemption has been submitted for revision of the pressure temperature operating limits. The NRC after review authorizes this exemption request and also declares that this authorization will have no risk to the public health and safety.
KW - NUCLEAR power plants
KW - EXEMPTION (Law)
KW - PUBLIC health -- United States
KW - PUBLIC safety
KW - UNITED States
KW - FLORIDA Power & Light Co.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 75329979; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 5/7/2012, Vol. 77 Issue 88, p26793; Thesaurus Term: NUCLEAR power plants; Subject Term: EXEMPTION (Law); Subject Term: PUBLIC health -- United States; Subject Term: PUBLIC safety; Subject: UNITED States ; Company/Entity: FLORIDA Power & Light Co. ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=75329979&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Elliott, Robert
T1 - Plant-Specific Adoption, Revision 4 of the Improved Standard Technical Specifications.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/10/
VL - 77
IS - 91
M3 - Article
SP - 27490
EP - 27491
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding availability of a the improved standard technical specifications for the nuclear power plants, Westinghouse plants, combustion engineering plants and general electric plants. These technical specifications are available at the commission website.
KW - SPECIFICATIONS
KW - NUCLEAR power plants
KW - ELECTRIC power plants
KW - WEBSITES
KW - COMBUSTION engineering
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 75291581; Elliott, Robert 1; Affiliations: 1: Chief, Technical Specifications Branch, Division of Safety Systems, Office of Nuclear Reactor Regulation.; Issue Info: 5/10/2012, Vol. 77 Issue 91, p27490; Thesaurus Term: SPECIFICATIONS; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: ELECTRIC power plants; Thesaurus Term: WEBSITES; Subject Term: COMBUSTION engineering; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 541330 Engineering Services; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 519130 Internet Publishing and Broadcasting and Web Search Portals; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=75291581&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Boyle, Patrick G.
T1 - Southern Nuclear Operating Company, Inc., Notice of Withdrawal of Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/11/
VL - 77
IS - 92
M3 - Article
SP - 27804
EP - 27804
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission has granted license to Southern Nuclear Operating Company Inc. for withdrawing its facility operating license in Appling County, Georgia.
KW - NUCLEAR power plants
KW - LICENSES
KW - U.S. Nuclear Regulatory Commission
KW - SOUTHERN Nuclear Operating Co. Inc.
N1 - Accession Number: 75291788; Boyle, Patrick G. 1; Affiliations: 1: Project Manager, Plant Licensing Branch II- 1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 5/11/2012, Vol. 77 Issue 92, p27804; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: SOUTHERN Nuclear Operating Co. Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Wang, Alan B.
T1 - Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/11/
VL - 77
IS - 92
M3 - Article
SP - 27804
EP - 27814
SN - 00976326
AB - The article reports on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding amendment of a license which has been granted to Entergy Operations Inc. for operation of its nuclear power station in Claiborne County in Mississippi. The NRC has prepared a draft environmental assessment and found that the nuclear plant operation will have no significant impact on the environment. The NRC is soliciting comments on this notice by May 21, 2012 via electronic mail or in writings.
KW - NUCLEAR power plants
KW - LICENSES
KW - ENVIRONMENTAL impact analysis
KW - PUBLIC opinion
KW - EMAIL
KW - DRAFT (Military service) -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - ENTERGY Operations Inc.
N1 - Accession Number: 75291789; Wang, Alan B. 1; Affiliations: 1: Project Manager, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 5/11/2012, Vol. 77 Issue 92, p27804; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: ENVIRONMENTAL impact analysis; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject Term: DRAFT (Military service) -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: ENTERGY Operations Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 11p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Jolicoeur, John R.
T1 - Model Safety Evaluation for Plant- Specific Adoption of Technical Specifications Task Force Traveler TSTF-432, Revision 1, ''Change in Technical Specifications End States (WCAP-16294)'' Using the Consolidated Line Item Improvement Process.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/11/
VL - 77
IS - 92
M3 - Article
SP - 27814
EP - 27815
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding availability of a model safety evaluation for plants technical specifications. These specifications are applicable to Westinghouse-designed pressurized water reactor plants. This notice will revise the permit for some nuclear systems and will allow for a hot shutdown end state rather than a cold shutdown.
KW - NUCLEAR power plants
KW - LICENSES
KW - SPECIFICATIONS
KW - PRESSURIZED water reactors -- Safety measures
KW - NUCLEAR reactors -- Shutdown
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 75291790; Jolicoeur, John R. 1; Affiliations: 1: Chief, Licensing Processes Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 5/11/2012, Vol. 77 Issue 92, p27814; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: SPECIFICATIONS; Subject Term: PRESSURIZED water reactors -- Safety measures; Subject Term: NUCLEAR reactors -- Shutdown ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Galloway, Melanie A.
T1 - Aging Management of Stainless Steel Structures and Components in Treated Borated Water.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/11/
VL - 77
IS - 92
M3 - Article
SP - 27815
EP - 27816
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding issuance of staff guidance titled "Aging Management of Stainless Steel Structures and Components in Treated Borated Water" This guidance will help the NRC staff for managing the stainless steel structures and components which are treated with borated water.
KW - NUCLEAR power plants
KW - PUBLIC officers
KW - GUIDELINES
KW - STAINLESS steel -- Corrosion
KW - MAINTENANCE & repair
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 75291791; Galloway, Melanie A. 1; Affiliations: 1: Acting Director, Division of License Renewal, Office of Nuclear Reactor Regulation; Issue Info: 5/11/2012, Vol. 77 Issue 92, p27815; Thesaurus Term: NUCLEAR power plants; Subject Term: PUBLIC officers; Subject Term: GUIDELINES; Subject Term: STAINLESS steel -- Corrosion; Subject Term: MAINTENANCE & repair ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Biweekly Notice, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/15/
VL - 77
IS - 94
M3 - Article
SP - 28626
EP - 28637
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding publication of amendments or rules related to nuclear power plants operating licenses. The commission is soliciting public comments on this notice via electronic mail, fax or in writings. The commission publishes any changes to the regulations along with its related hazards. The last biweekly notice in this regard has been published on May 1, 2012 in the journal.
KW - GOVERNMENT regulation
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - EMAIL
KW - GOVERNMENT publications
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 76111877; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 5/15/2012, Vol. 77 Issue 94, p28626; Thesaurus Term: GOVERNMENT regulation; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject Term: GOVERNMENT publications ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 12p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=76111877&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio
T1 - Advisory Committee On Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Power Uprates; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/15/
VL - 77
IS - 94
M3 - Proceeding
SP - 28637
EP - 28638
SN - 00976326
AB - The article offers information on a meeting of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on May 24, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - ROCKVILLE (Md.)
N1 - Accession Number: 76111879; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 5/15/2012, Vol. 77 Issue 94, p28637; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject: ROCKVILLE (Md.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=76111879&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/15/
VL - 77
IS - 94
M3 - Proceeding
SP - 28637
EP - 28637
SN - 00976326
AB - The article offers information on a meeting of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland from May 23-24, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - ROCKVILLE (Md.)
N1 - Accession Number: 76111878; Santos, Cayetano 1; Affiliations: 1: Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 5/15/2012, Vol. 77 Issue 94, p28637; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject: ROCKVILLE (Md.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Impact of Construction (Under a Combined License) of New Nuclear Power Plant Units on Operating Units at Multi-Unit Sites.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/18/
VL - 77
IS - 97
M3 - Article
SP - 29701
EP - 29701
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding issuance of a guidance related to impact of construction of nuclear power plants. The guidance will help the NRC officials during nuclear power plants licensing activities. The notice will be effective by June 18, 2012.
KW - NUCLEAR power plants
KW - LICENSES
KW - GUIDELINES
KW - DESIGN & construction
KW - PUBLIC officers
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 76112127; Cubbage, Amy E. 1; Email Address: amy.cubbage@nrc.gov; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors.; Issue Info: 5/18/2012, Vol. 77 Issue 97, p29701; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: GUIDELINES; Subject Term: DESIGN & construction; Subject Term: PUBLIC officers ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2/3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Proposed Revision 3 to Standard Review Plan, Section 19.1 on Determining the Technical Adequacy of Probabilistic Risk Assessment for Risk-Informed License Amendment Requests After Initial Fuel Load.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/22/
VL - 77
IS - 99
M3 - Article
SP - 30335
EP - 30335
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission is soliciting public comments on regulatory guides titled "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition." The agency is soliciting public comments within 30 days of publication of this notice in the journal via electronic mail or in writings.
KW - PUBLIC opinion
KW - NUCLEAR power plants
KW - EMAIL
KW - GUIDELINES
KW - SAFETY measures
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 76381259; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors; Issue Info: 5/22/2012, Vol. 77 Issue 99, p30335; Thesaurus Term: PUBLIC opinion; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: EMAIL; Subject Term: GUIDELINES; Subject Term: SAFETY measures ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 1p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Morgan-Butler, Kimyata
T1 - Proposed Generic Communication; Generic Letter on Seismic Risk Evaluations for Operating Reactors.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/23/
VL - 77
IS - 100
M3 - Article
SP - 30560
EP - 30560
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission is withdrawing a draft titled "Seismic Risk Evaluations for Operating Reactors." This draft will be withdrawn by May 23, 2012. The agency solicited public comments on this draft proposal. Information on a correction notice issued by the agency for extending the dates for public comments is also presented.
KW - NUCLEAR power plants
KW - PUBLIC opinion
KW - DRAFT (Military service) -- United States
KW - EARTHQUAKE hazard analysis
KW - SAFETY measures
KW - ERRATA (Publishing)
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 76338701; Morgan-Butler, Kimyata 1; Affiliations: 1: Acting Chief, Generic Communications Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 5/23/2012, Vol. 77 Issue 100, p30560; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: PUBLIC opinion; Subject Term: DRAFT (Military service) -- United States; Subject Term: EARTHQUAKE hazard analysis; Subject Term: SAFETY measures; Subject Term: ERRATA (Publishing); Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 1/2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/24/
VL - 77
IS - 101
M3 - Proceeding
SP - 31044
EP - 31045
SN - 00976326
AB - The article presents information on a meeting of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on June 5, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - ROCKVILLE (Md.)
N1 - Accession Number: 76338841; Santos, Cayetano 1; Affiliations: 1: Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 5/24/2012, Vol. 77 Issue 101, p31044; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject: ROCKVILLE (Md.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Morey, Dennis
T1 - Energy Northwest, Columbia Generating Station; Record of Decision and Issuance of Renewed Facility Operating License for an Additional 20- Year Period.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/05/30/
VL - 77
IS - 104
M3 - Article
SP - 31895
EP - 31896
SN - 00976326
AB - The article presents information that the U.S. Nuclear RegulatoryCommission has issued a renewed facility operating license to the company Energy Northwest for its reactor core power levels. The commission has also prepared an environmental impact statement related to this issue. Information on several alternatives identified by the commission including natural gas-fired combined cycle, coal-fired power and energy conservation and energy efficiency is presented.
KW - NUCLEAR power plants
KW - LICENSES
KW - ENERGY conservation
KW - ENERGY consumption
KW - NUCLEAR reactors -- Cores
KW - U.S. Nuclear Regulatory Commission
KW - ENERGY Northwest (Company)
N1 - Accession Number: 76436042; Morey, Dennis 1; Affiliations: 1: Chief, Projects Branch 1, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 5/30/2012, Vol. 77 Issue 104, p31895; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: ENERGY conservation; Thesaurus Term: ENERGY consumption; Subject Term: NUCLEAR reactors -- Cores ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: ENERGY Northwest (Company) DUNS Number: 061666103; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - NEWS
AU - Was, Gary S.
AU - Byun, Thak Sang
AU - Hu, Shenyang
AU - Morgan, Dane
AU - Nagai, Yasuyoshi
AU - Kerr, Matthew
T1 - Preface
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2012/06//
VL - 425
IS - 1-3
M3 - Editorial
SP - 1
EP - 1
SN - 00223115
N1 - Accession Number: 74992428; Was, Gary S. 1; Email Address: gsw@umich.edu Byun, Thak Sang 2; Email Address: byunts@ornl.gov Hu, Shenyang 3; Email Address: shenyang.hu@pnnl.gov Morgan, Dane 4; Email Address: ddmorgan@wisc.edu Nagai, Yasuyoshi 5; Email Address: nagai@imr.tohoku.ac.jp Kerr, Matthew 6; Email Address: matthew.kerr@nrc.gov; Affiliation: 1: Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 48109-2104 Ann Arbor, MI, USA 2: Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA 3: Radiological & Nuclear Science & Technology Division, Pacific Northwest National Laboratory, Richland, WA 99352, USA 4: Department of Materials Science and Engineering, University of Wisconsin, Madison, WI 53706, USA 5: Tohoku University, Oarai, Ibaraki 311-1313, Japan 6: Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission, Washington, DC, USA; Source Info: Jun2012, Vol. 425 Issue 1-3, p1; Number of Pages: 1p; Document Type: Editorial
L3 - 10.1016/j.jnucmat.2012.03.025
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=74992428&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Tulk, E.
AU - Kerr, M.
AU - Daymond, M.R.
T1 - Study on the effects of matrix yield strength on hydride phase stability in Zircaloy-2 and Zr 2.5wt% Nb
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2012/06//
VL - 425
IS - 1-3
M3 - Article
SP - 93
EP - 104
SN - 00223115
AB - Abstract: A study on the effect of matrix yield strength on precipitation of hydride phases in zirconium alloys is presented. X-ray diffraction measurements from the National Synchrotron Light Source (NSLS) at Brookhaven National Laboratory were used to characterise the quantity of δ (fcc) and γ (fct) hydride phases in zirconium alloys as a function of yield stress and cooling rate. While experimental results indicate that yield stress has a pronounced effect on hydride phase stability in the zirconium–hydrogen system, other factors including defect structure and β-phase distribution also influence the hydride phase stability, for material of a given yield stress. These results offer a possible explanation for the wide range of hydride phase stability reported in the literature for the zirconium–hydrogen system. [Copyright &y& Elsevier]
AB - Copyright of Journal of Nuclear Materials is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - STRENGTH of materials
KW - HYDRIDES
KW - STABILITY (Mechanics)
KW - ZIRCALOY-2
KW - PRECIPITATION (Chemistry)
KW - X-ray diffraction
KW - STRAINS & stresses (Mechanics)
KW - PHYSICS experiments
KW - METALS -- Microstructure
N1 - Accession Number: 74992442; Tulk, E. 1 Kerr, M. 2 Daymond, M.R. 1; Email Address: daymond@me.queensu.ca; Affiliation: 1: Department of Mechanical and Materials Engineering, Queen’s University, Kingston, Ontario, Canada K7L 3N6 2: US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC 20555, United States; Source Info: Jun2012, Vol. 425 Issue 1-3, p93; Subject Term: STRENGTH of materials; Subject Term: HYDRIDES; Subject Term: STABILITY (Mechanics); Subject Term: ZIRCALOY-2; Subject Term: PRECIPITATION (Chemistry); Subject Term: X-ray diffraction; Subject Term: STRAINS & stresses (Mechanics); Subject Term: PHYSICS experiments; Subject Term: METALS -- Microstructure; Number of Pages: 12p; Document Type: Article
L3 - 10.1016/j.jnucmat.2011.10.051
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Thadani, A.
AU - Teschendorff, V.
AU - Gauvain, J.
T1 - International joint projects on nuclear safety: 30 years of benefits.
JO - NEA News (OECD Nuclear Energy Agency)
JF - NEA News (OECD Nuclear Energy Agency)
Y1 - 2012/06//
VL - 30
IS - 1
M3 - Article
SP - 15
EP - 18
SN - 16059581
AB - The article discusses the benefits of international joint projects on nuclear safety. It cites the role of the Nuclear Energy Agency (NEA) in assisting its member countries in maintaining and developing the scientific, technological, and legal bases required for a safe, environmentally friendly and economic use of nuclear energy. Over 30 projects devoted to nuclear safety research were conducted since 1958 when the first project at the Halden reactor in Norway was established.
KW - NUCLEAR energy -- Economic aspects
KW - NUCLEAR crisis control
KW - NUCLEAR reactors
KW - NUCLEAR accidents -- Prevention
KW - NORWAY
N1 - Accession Number: 83286811; Thadani, A. 1,2; Email Address: ashok.thadani@verizon.net Teschendorff, V. 3,4; Email Address: victor-teschendorff@t-online.de Gauvain, J. 5; Email Address: jean.gauvain@oecd.org; Affiliation: 1: Director, Office for Nuclear Regulatory Research, United States Nuclear Regulatory Commission (USNRC) 2: Chairman, CSNI 3: Head, Reactor Safety Research Division, GRS (Germany) 4: Chairman, CSNI Programme Review Group 5: Coordinator, joint projects, NEA Nuclear Safety Division; Source Info: 2012, Vol. 30 Issue 1, p15; Subject Term: NUCLEAR energy -- Economic aspects; Subject Term: NUCLEAR crisis control; Subject Term: NUCLEAR reactors; Subject Term: NUCLEAR accidents -- Prevention; Subject Term: NORWAY; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=83286811&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Mahoney, Michael
T1 - Exelon Generation Company, LLC; Clinton Power Station, Unit 1.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/04/
VL - 77
IS - 107
M3 - Article
SP - 33004
EP - 33005
SN - 00976326
AB - The article presents information on a request submitted by Exelon Generation Co. LLC to the U.S. Nuclear Regulatory Commission for releasing sites for its Clinton Power Station located in DeWitt County, Illinois. The agency is soliciting public comments on this request by June 13, 2012 via electronic mail or in writings.
KW - NUCLEAR power plants
KW - PUBLIC opinion
KW - EMAIL
KW - DE Witt County (Ill.)
KW - ILLINOIS
KW - EXELON Generation Co. LLC
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 76590418; Mahoney, Michael 1; Affiliations: 1: Project Manager, Plant Licensing Branch III- 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 6/4/2012, Vol. 77 Issue 107, p33004; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject: DE Witt County (Ill.); Subject: ILLINOIS ; Company/Entity: EXELON Generation Co. LLC ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=76590418&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Kim, James
T1 - Notice of Withdrawal of Application for Amendment to Facility Operating License; Dominion Nuclear Connecticut, Inc., Millstone Power Station, Unit 3.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/05/
VL - 77
IS - 108
M3 - Article
SP - 33252
EP - 33252
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission has granted the petition filed by Dominion Nuclear Connecticut Inc. for withdrawing its application for the facility operating license located in Connecticut.
KW - PETITIONS
KW - U.S. Nuclear Regulatory Commission
KW - DOMINION Nuclear Connecticut Inc.
N1 - Accession Number: 77061336; Kim, James 1; Affiliations: 1: Project Manager, Plant Licensing Branch I-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 6/5/2012, Vol. 77 Issue 108, p33252; Subject Term: PETITIONS ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DOMINION Nuclear Connecticut Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77061336&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Skeen, David L.
T1 - Interim Staff Guidance JLD-ISG-2012- 02; Compliance With Order EA-12-050, Order Modifying Licenses With Regard to Reliable Hardened Containment Vents.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/07/
VL - 77
IS - 110
M3 - Article
SP - 33777
EP - 33778
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding the issuance of a draft titled "Compliance with Order EA-12-050, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents.'' This draft helps the agency officials related to nuclear power plants applicants and licensees. The agency is soliciting public comments on this notice by July 7, 2012 via electronic mail or in writings.
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - EMAIL
KW - DRAFT (Military service) -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 76926777; Skeen, David L. 1; Affiliations: 1: Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation; Issue Info: 6/7/2012, Vol. 77 Issue 110, p33777; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject Term: DRAFT (Military service) -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=76926777&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Skeen, David L.
T1 - Interim Staff Guidance JLD-ISG-2012- 01; Compliance With Order EA-12-049, Order Modifying Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/07/
VL - 77
IS - 110
M3 - Article
SP - 33779
EP - 33780
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding the issuance of a draft titled "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.'' This draft helps the agency officials related to nuclear power plants applicants and licensees. The agency is soliciting public comments on this notice by July 7, 2012 via electronic mail or in writings.
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - EMAIL
KW - DRAFT (Military service) -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 76926778; Skeen, David L. 1; Affiliations: 1: Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation; Issue Info: 6/7/2012, Vol. 77 Issue 110, p33779; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject Term: DRAFT (Military service) -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=76926778&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Skeen, David L.
T1 - Interim Staff Guidance JLD-ISG-2012- 03; Compliance with Order EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/07/
VL - 77
IS - 110
M3 - Article
SP - 33780
EP - 33782
SN - 00976326
AB - The article presents information on a notice issued by the U.S. Nuclear Regulatory Commission regarding the issuance of a draft titled "Compliance With Order EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation.'' This draft helps the agency officials related to nuclear power plants applicants and licensees. The agency is soliciting public comments on this notice by July 7, 2012 via electronic mail or in writings.
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - EMAIL
KW - DRAFT (Military service) -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 76926779; Skeen, David L. 1; Affiliations: 1: Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation; Issue Info: 6/7/2012, Vol. 77 Issue 110, p33780; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject Term: DRAFT (Military service) -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=76926779&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Wrona, David J.
T1 - License Renewal Application for Seabrook Station, Unit 1 ; NextEra Energy Seabrook, LLC.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/12/
VL - 77
IS - 113
M3 - Article
SP - 35079
EP - 35080
SN - 00976326
AB - The article presents information on an application filed by NextEra Energy Seabrook LLC to the U.S. Nuclear Regulatory Commission for renewing its facility operating license for an additional 20 years. It informs that the commission will prepare a supplemental environmental impact statement on this license renewal application. This application has been filed in accordance with the U.S. National Environmental Policy Act of 1969.
KW - NUCLEAR power plants
KW - LICENSES
KW - ENVIRONMENTAL impact statements
KW - U.S. Nuclear Regulatory Commission
KW - NEXTERA Energy Seabrook LLC
KW - UNITED States. National Environmental Policy Act of 1969
N1 - Accession Number: 77245364; Wrona, David J. 1; Affiliations: 1: Chief, Projects Branch 2, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 6/12/2012, Vol. 77 Issue 113, p35079; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: ENVIRONMENTAL impact statements ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: NEXTERA Energy Seabrook LLC ; Company/Entity: UNITED States. National Environmental Policy Act of 1969; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77245364&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Morey, Dennis
T1 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Record of Decision and Issuance of Renewed Facility Operating License No. DPR-35 for an Additional 20-Year Period.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/12/
VL - 77
IS - 113
M3 - Article
SP - 35080
EP - 35081
SN - 00976326
AB - The article presents information on an application filed by Entergy Nuclear Operations Inc. to the U.S. Nuclear Regulatory Commission for renewing its facility operating license for an additional 20 years. It informs that the commission has approved this application after review as the application complies with the U.S. Atomic Energy Act of 1954. The agency has also prepared a supplemental environmental impact statement for this license renewal.
KW - NUCLEAR power plants
KW - LICENSES
KW - NUCLEAR power plants -- Environmental aspects
KW - ENVIRONMENTAL impact statements
KW - U.S. Nuclear Regulatory Commission
KW - ENTERGY Nuclear Operations Inc.
N1 - Accession Number: 77245365; Morey, Dennis 1; Affiliations: 1: Chief, Projects Branch 1, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 6/12/2012, Vol. 77 Issue 113, p35080; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: NUCLEAR power plants -- Environmental aspects; Subject Term: ENVIRONMENTAL impact statements ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: ENTERGY Nuclear Operations Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77245365&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Matthews, David B.
T1 - PPL Bell Bend, LLC; Bell Bend Nuclear Power Plant Combined License Application; Notice of Intent To Conduct a Supplemental Scoping Process on the Revised Site Layout.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/15/
VL - 77
IS - 116
M3 - Article
SP - 36012
EP - 36014
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission (NRC) is soliciting public comments in response to an application filed by PPL Bell Bend LLC for reviewing its license for the nuclear power plant. The NRC is soliciting public comments by July 16, 2012 via electronic mail or in writing. The NRC has decided to prepare the environmental impact statement on this application filed.
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - EMAIL
KW - ENVIRONMENTAL impact statements
KW - U.S. Nuclear Regulatory Commission
KW - PPL Bell Bend LLC
N1 - Accession Number: 77389504; Matthews, David B. 1; Affiliations: 1: Director, Division of New Reactor Licensing, Office of New Reactors.; Issue Info: 6/15/2012, Vol. 77 Issue 116, p36012; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject Term: ENVIRONMENTAL impact statements ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: PPL Bell Bend LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77389504&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C Cancellation of the June 19, 2012 ACRS Subcommittee Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/15/
VL - 77
IS - 116
M3 - Article
SP - 36017
EP - 36017
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission has cancelled a meeting that was scheduled to be held on June 19, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 77389507; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 6/15/2012, Vol. 77 Issue 116, p36017; Thesaurus Term: MEETINGS ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77389507&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Plant License Renewal; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/19/
VL - 77
IS - 118
M3 - Proceeding
SP - 36582
EP - 36583
SN - 00976326
AB - The article offers information on a meeting of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on July 10, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - ROCKVILLE (Md.)
N1 - Accession Number: 77411521; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 6/19/2012, Vol. 77 Issue 118, p36582; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject: ROCKVILLE (Md.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77411521&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Lund, Louise
T1 - Central Vermont Public Service Corporation, Gaz Me'tro Limited Partnership, Dominion Nuclear Connecticut, Inc. (Millstone Power Station, Unit 3); Order Approving Application Regarding Proposed Merger of Central Vermont Public Service Corporation and Gaz Me' tro Limited Partnership and Indirect Transfer of License
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/25/
VL - 77
IS - 122
M3 - Article
SP - 37936
EP - 37937
SN - 00976326
AB - The article presents information that Central Vermont Public Service Corp. (CVPSC), Danaus Vermont Corp. and Gaz Métro LP have submitted an application to the U.S. Nuclear Regulatory Commission for the indirect transfer of control of the facility operating license. It informs that Danaus Vermont Corp. will merge with CVPSC and CVPSC will continue as the surviving corporation and also an indirect wholly owned subsidiary of Gaz Métro.
KW - NUCLEAR power plants
KW - SUBSIDIARY corporations
KW - U.S. Nuclear Regulatory Commission
KW - CENTRAL Vermont Public Service Corp.
KW - DANAUS Vermont Corp.
KW - GAZ Metro (Company)
N1 - Accession Number: 77638498; Lund, Louise 1; Affiliations: 1: Acting Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 6/25/2012, Vol. 77 Issue 122, p37936; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: SUBSIDIARY corporations ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: CENTRAL Vermont Public Service Corp. DUNS Number: 007939614 Ticker: CV ; Company/Entity: DANAUS Vermont Corp. ; Company/Entity: GAZ Metro (Company); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 551114 Corporate, Subsidiary, and Regional Managing Offices; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77638498&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Lund, A. Louise
T1 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/26/
VL - 77
IS - 123
M3 - Article
SP - 38094
EP - 38099
SN - 00976326
AB - The article presents information that the U.S. Nuclear RegulatoryCommission in accordance with the U.S. Atomic Energy Act of 1954 is publishing this notice to inform public about the facility operating licenses which are filed to it. The agency is soliciting public comments via electronic mail or in writing. It informs that Northern States Power Co., Union Electric Co. and Carolina Power and Light Co. have applied to the agency for their facility operating license.
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - EMAIL
KW - U.S. Nuclear Regulatory Commission
KW - NORTHERN States Power Co.
KW - UNION Electric Co.
KW - CAROLINA Power & Light Co.
N1 - Accession Number: 77665960; Lund, A. Louise 1; Affiliations: 1: Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 6/26/2012, Vol. 77 Issue 123, p38094; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: NORTHERN States Power Co. Ticker: NSP ; Company/Entity: UNION Electric Co. DUNS Number: 004842845 ; Company/Entity: CAROLINA Power & Light Co. DUNS Number: 006997217 Ticker: CPL; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 6p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77665960&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S. Advanced Pressurized Power Reactor.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/26/
VL - 77
IS - 123
M3 - Proceeding
SP - 38099
EP - 38100
SN - 00976326
AB - The article offers information on a meeting of the U.S. Nuclear Regulatory Commission to be held on July 9, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
N1 - Accession Number: 77665962; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 6/26/2012, Vol. 77 Issue 123, p38099; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77665962&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Quichocho, Jessie F.
T1 - Non-Power Reactor License Renewal.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/06/29/
VL - 77
IS - 126
M3 - Article
SP - 38742
EP - 38743
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission (NRC) is soliciting comments from the public, licensees, certificate holders and stakeholders for modifying its regulations for the license renewal requirements of non-power reactors. It informs that these inputs will also be used for addressing technical issues for its existing non-power reactors. The NRC is soliciting public comments by July 31, 2012 via electronic mail or in writing.
KW - PUBLIC opinion
KW - NUCLEAR power plants
KW - LICENSES
KW - STAKEHOLDERS
KW - EMAIL
KW - NUCLEAR reactors -- Law & legislation
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 77690200; Quichocho, Jessie F. 1; Affiliations: 1: Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 6/29/2012, Vol. 77 Issue 126, p38742; Thesaurus Term: PUBLIC opinion; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: STAKEHOLDERS; Thesaurus Term: EMAIL; Subject Term: NUCLEAR reactors -- Law & legislation ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=77690200&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Marcus, Gail H.
T1 - Heeding the Lessons of History.
JO - Mechanical Engineering
JF - Mechanical Engineering
Y1 - 2012/07//
VL - 134
IS - 7
M3 - Article
SP - 28
EP - 33
PB - American Society of Mechanical Engineers
SN - 00256501
AB - The article focuses on nuclear power reactors used in firms around the world. It states that these reactors uses enriched uranium and are moderated by water. It further informs about the second generation of reactors which is known as Generation four reactors. It focuses on the two concepts of generators including the Very High Temperature Reactor and the Gas-cooled Fast Reactor. As mentioned, earlier reactors were known as piles, they were stacks of large graphite blocks with channels containing the uranium fuel.
KW - NUCLEAR reactors
KW - URANIUM
KW - PILING (Civil engineering)
KW - TEMPERATURE
KW - GRAPHITE
KW - ELECTRIC generators
KW - WATER
KW - ALGEBRAIC stacks
KW - BLOCKS (Building materials)
N1 - Accession Number: 77347655; Marcus, Gail H. 1; Affiliation: 1: Department of Energy, and the U.S. Nuclear Regulatory Commission, and has served as president of the American Nuclear Society; Source Info: Jul2012, Vol. 134 Issue 7, p28; Subject Term: NUCLEAR reactors; Subject Term: URANIUM; Subject Term: PILING (Civil engineering); Subject Term: TEMPERATURE; Subject Term: GRAPHITE; Subject Term: ELECTRIC generators; Subject Term: WATER; Subject Term: ALGEBRAIC stacks; Subject Term: BLOCKS (Building materials); NAICS/Industry Codes: 444190 Other Building Material Dealers; NAICS/Industry Codes: 335312 Motor and Generator Manufacturing; NAICS/Industry Codes: 423610 Electrical Apparatus and Equipment, Wiring Supplies, and Related Equipment Merchant Wholesalers; NAICS/Industry Codes: 238299 All other building equipment contractors; NAICS/Industry Codes: 238290 Other Building Equipment Contractors; NAICS/Industry Codes: 416110 Electrical wiring and construction supplies merchant wholesalers; NAICS/Industry Codes: 212398 All other non-metallic mineral mining and quarrying; NAICS/Industry Codes: 327992 Ground or Treated Mineral and Earth Manufacturing; NAICS/Industry Codes: 327990 All other non-metallic mineral product manufacturing; NAICS/Industry Codes: 212399 All Other Nonmetallic Mineral Mining; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; NAICS/Industry Codes: 237990 Other Heavy and Civil Engineering Construction; NAICS/Industry Codes: 238910 Site Preparation Contractors; NAICS/Industry Codes: 213119 Other support activities for mining; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; Number of Pages: 6p; Illustrations: 3 Color Photographs; Document Type: Article; Full Text Word Count: 3410
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=77347655&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Kim, James
T1 - Dominion Nuclear Connecticut, Inc. Millstone Power Station, Unit 2; Environmental Assessment and Finding of No Significant Impact.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/05/
VL - 77
IS - 129
M3 - Article
SP - 39746
EP - 39747
SN - 00976326
AB - The article presents the U.S. Nuclear Regulatory Commission's (NRC) proposal to grant exemptions to certain NRC requirements pertaining to fire regulations. The NRC is considering issuance of an exemption from the requirements of Title 10 of the Code of Federal Regulations "Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979," for Facility Operating License No. DPR-65 issued to Dominion Nuclear Connecticut Inc. for operation of the Millstone Power Station.
KW - GOVERNMENT policy
KW - FEDERAL regulation
KW - FIRE prevention
KW - EXCEPTIONS (Law)
KW - UNITED States
KW - DOMINION Nuclear Connecticut Inc.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 77739044; Kim, James 1; Affiliations: 1: Project Manager, Plant Licensing Branch I- 1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 7/5/2012, Vol. 77 Issue 129, p39746; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: FEDERAL regulation; Subject Term: FIRE prevention; Subject Term: EXCEPTIONS (Law); Subject: UNITED States ; Company/Entity: DOMINION Nuclear Connecticut Inc. ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Wrona, David J.
T1 - Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating, Units 2 and 3.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/06/
VL - 77
IS - 130
M3 - Article
SP - 40091
EP - 40092
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission on a draft supplement to Supplement 38 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants (GEIS). It indicates the request for public comments on a draft supplement to Supplement 38 involving the renewal of operating licenses of Indian Point Nuclear Generating Units 2 and 3 of Entergy Nuclear Operations Inc . It states that comments must be received by August 20, 2012.
KW - PUBLIC opinion
KW - BUSINESS licenses
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - ENTERGY Nuclear Operations Inc.
KW - INDIAN Point Nuclear Power Plant (N.Y.)
N1 - Accession Number: 77739171; Wrona, David J. 1; Affiliations: 1: Chief, Projects Branch 2, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 7/6/2012, Vol. 77 Issue 130, p40091; Thesaurus Term: PUBLIC opinion; Thesaurus Term: BUSINESS licenses; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: ENTERGY Nuclear Operations Inc. ; Company/Entity: INDIAN Point Nuclear Power Plant (N.Y.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Orf, Tracy J.
T1 - License Amendment To Increase the Maximum Reactor Power Level, Florida Power & Light Company, St. Lucie, Units 1 and 2.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/06/
VL - 77
IS - 130
M3 - Article
SP - 40092
EP - 40106
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission (NRC) on the issuance of an amendment for Renewed Facility Operating License to Florida Power & Light Co. (FPL). It indicates the agency's environmental assessment (EA) and findings of no significant impact (FONSI) to the operation of the St. Lucie Plant, Units 1 and 2 in Florida. Also noted is the agency's request for public comments and review on a draft EA and FONSI.
KW - BUSINESS licenses
KW - ENVIRONMENTAL impact analysis
KW - PUBLIC opinion
KW - UNITED States
KW - FLORIDA Power & Light Co.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 77739172; Orf, Tracy J. 1; Affiliations: 1: Project Manager, Plant Licensing Branch II-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 7/6/2012, Vol. 77 Issue 130, p40092; Thesaurus Term: BUSINESS licenses; Thesaurus Term: ENVIRONMENTAL impact analysis; Thesaurus Term: PUBLIC opinion; Subject: UNITED States ; Company/Entity: FLORIDA Power & Light Co. ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; Number of Pages: 15p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Lingam, Siva P.
T1 - Tennessee Valley Authority; Notice of Withdrawal of Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/09/
VL - 77
IS - 131
M3 - Article
SP - 40384
EP - 40385
SN - 00976326
AB - The article presents a notice indicating that the U.S. Nuclear Regulatory Commission (NRC) has granted the request of Tennessee Valley Authority to withdraw its application for amendment to Facility Operating License for the Sequoyah Nuclear Plant in Hamilton County, Tennessee.
KW - NUCLEAR facilities -- Tennessee
KW - U.S. Nuclear Regulatory Commission
KW - TENNESSEE Valley Authority
N1 - Accession Number: 78039631; Lingam, Siva P. 1; Affiliations: 1: Project Manager, Plant Licensing Branch II-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 7/9/2012, Vol. 77 Issue 131, p40384; Subject Term: NUCLEAR facilities -- Tennessee ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: TENNESSEE Valley Authority Ticker: TVC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Quichocho, Jessie F.
T1 - Guidelines for Preparing and Reviewing Licensing Applications for Instrumentation and Control Upgrades for Non-Power Reactors.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/12/
VL - 77
IS - 134
M3 - Article
SP - 41206
EP - 41207
SN - 00976326
AB - The article presents information that the U.S. Nuclear Regulatory Commission (NRC) is soliciting comments on two guidelines titled "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Format and Content" and "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Standard Review Plan and Acceptance Criteria." The NRC is soliciting public comments by August 13, 2012 via electronic mail or in writing.
KW - NUCLEAR power plants
KW - LICENSES
KW - PUBLIC opinion
KW - EMAIL
KW - GUIDELINES
KW - NUCLEAR reactors -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 78039980; Quichocho, Jessie F. 1; Affiliations: 1: Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 7/12/2012, Vol. 77 Issue 134, p41206; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EMAIL; Subject Term: GUIDELINES; Subject Term: NUCLEAR reactors -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=78039980&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Boska, John P.
T1 - Entergy Nuclear Indian Point Unit 2, LLC, Entergy Nuclear Indian Point Unit 3, LLC, Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Units 2 and 3; Environmental Assessment and Finding of No Significant Impact.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/13/
VL - 77
IS - 135
M3 - Article
SP - 41454
EP - 41457
SN - 00976326
AB - The article discusses the findings of the U.S. Nuclear Regulatory Commission (NRC) on its environmental assessment of Entergy Nuclear Operations Inc.'s Indian Point Nuclear Generating Units in Westchester County, New York. The NRC reportedly determined that Entergy's proposed amendment to the technical specifications for the facility operating license numbers DPR-26 and DPR-64 will have no significant impact on the quality of the environment. It also discusses how the evaluation was conducted.
KW - NUCLEAR power plants
KW - BUSINESS licenses
KW - ENVIRONMENTAL risk assessment
KW - WESTCHESTER County (N.Y.)
KW - NEW York (State)
KW - U.S. Nuclear Regulatory Commission
KW - ENTERGY Nuclear Operations Inc.
N1 - Accession Number: 78040099; Boska, John P. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch I-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 7/13/2012, Vol. 77 Issue 135, p41454; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: BUSINESS licenses; Subject Term: ENVIRONMENTAL risk assessment; Subject: WESTCHESTER County (N.Y.); Subject: NEW York (State) ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: ENTERGY Nuclear Operations Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Galloway, Melanie A.
T1 - Aging Management Associated With Wall Thinning Due to Erosion Mechanisms.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/13/
VL - 77
IS - 135
M3 - Article
SP - 41457
EP - 41458
SN - 00976326
AB - The article presents a request for public comments from the U.S. Nuclear Regulatory Commission (NRC) on Draft License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2012-01 which proposes to amend an aging management program. It offers information on the guidance which suggested changing the definition of wall thinning to include erosion mechanisms. It also provides instructions to submit comments and to access information related to the document.
KW - NUCLEAR power plants
KW - MANAGEMENT
KW - BUSINESS licenses
KW - WALLS
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 78040100; Galloway, Melanie A. 1; Affiliations: 1: Acting Director, Division of License Renewal, Office of Nuclear Reactor Regulation; Issue Info: 7/13/2012, Vol. 77 Issue 135, p41457; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: MANAGEMENT; Thesaurus Term: BUSINESS licenses; Subject Term: WALLS; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Markley, Michael T.
T1 - Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/16/
VL - 77
IS - 136
M3 - Article
SP - 41814
EP - 41824
SN - 00976326
AB - The article presents a notice of the U.S. Nuclear Regulatory Commission's (NRC) issuance of an amendment to Facility Operating License No. NPF-29, issued to Entergy Operations Inc. The ammendment is for the company's operation of the Grand Gulf Nuclear Station, Unit 1 located in Claiborne County, Mississippi. Thus, the NRC has prepared the final environmental assessment (EA) and finding of no significant impact (FONSI) for the proposed action.
KW - LICENSES
KW - NUCLEAR power plants
KW - ENVIRONMENTAL impact analysis
KW - CLAIBORNE County (Miss.)
KW - MISSISSIPPI
KW - U.S. Nuclear Regulatory Commission
KW - ENTERGY Operations Inc.
KW - GRAND Gulf Nuclear Powerplant (Miss.)
N1 - Accession Number: 78115472; Markley, Michael T. 1; Affiliations: 1: Chief, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 7/16/2012, Vol. 77 Issue 136, p41814; Thesaurus Term: LICENSES; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: ENVIRONMENTAL impact analysis; Subject: CLAIBORNE County (Miss.); Subject: MISSISSIPPI ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: ENTERGY Operations Inc. ; Company/Entity: GRAND Gulf Nuclear Powerplant (Miss.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 11p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Kim, James
T1 - Central Vermont Public Service Corporation, Millstone Power Station, Unit 3; Notice of Consideration of Approval of Transfer of Facility Operating License, Conforming Amendment and Opportunity for a Hearing.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/20/
VL - 77
IS - 140
M3 - Article
SP - 42768
EP - 42771
SN - 00976326
AB - The article offers information on a notice from the U.S. Nuclear Regulatory Commission requesting the approval of transfer of facility operating license of Central Vermont Public Service Corp. for the Millstone Power Station. It notes that under 10 Code of Federal Regulations (CFR) 50.80, no license or any right can be transferred through transfer of control of the license unless the Commission provides its consent in writing. Moreover, it calls for public comments regarding the application.
KW - NUCLEAR industry
KW - GOVERNMENT policy
KW - LICENSES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - CENTRAL Vermont Public Service Corp.
N1 - Accession Number: 78125406; Kim, James 1; Affiliations: 1: Project Manager, Plant Licensing Branch I- 1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 7/20/2012, Vol. 77 Issue 140, p42768; Thesaurus Term: NUCLEAR industry; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: LICENSES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: CENTRAL Vermont Public Service Corp. DUNS Number: 007939614 Ticker: CV; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Quichocho, Jessie F.
T1 - License Renewal for the Dow Chemical TRIGA Research Reactor.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/20/
VL - 77
IS - 140
M3 - Article
SP - 42771
EP - 42774
SN - 00976326
AB - The article focuses on the issuance of a renewed Facility Operating License No. R-108 to Dow Chemical Co. for its Training, Research, Isotope production, General Atomics (TRIGA) Research Reactor in Midland County, Michigan. It notes the efforts of the U.S. Nuclear Regulatory Commission (NRC) in assessing the environmental impact of the facility operation. Moreover, it cites the implication of the National Environmental Policy Act (NEPA) on the works of the NRC.
KW - ENVIRONMENTAL law
KW - LICENSES
KW - MIDLAND County (Mich.)
KW - MICHIGAN
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - DOW Chemical Co.
N1 - Accession Number: 78125407; Quichocho, Jessie F. 1; Affiliations: 1: Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 7/20/2012, Vol. 77 Issue 140, p42771; Thesaurus Term: ENVIRONMENTAL law; Thesaurus Term: LICENSES; Subject: MIDLAND County (Mich.); Subject: MICHIGAN; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DOW Chemical Co. DUNS Number: 001381581 Ticker: DOW; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Millstone Power Station, Unit 2; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/24/
VL - 77
IS - 142
M3 - Article
SP - 43382
EP - 43405
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission (NRC) regarding the exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix R, Section III.G, Fire Protection of Safe Shutdown Capability granted to Millstone Power Station Unit 2 (MPS2) of Dominion Nuclear Connecticut Inc. The Commission asserts that the exemption will not present an undue risk to the public health and safety. The issuance of the exemption took effect on July 12, 2012.
KW - FIRE prevention -- Law & legislation -- United States
KW - PUBLIC health -- United States
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - DOMINION Nuclear Connecticut Inc.
N1 - Accession Number: 78329762; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 7/24/2012, Vol. 77 Issue 142, p43382; Subject Term: FIRE prevention -- Law & legislation -- United States; Subject Term: PUBLIC health -- United States; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DOMINION Nuclear Connecticut Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 24p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Final Standard Review Plan, Branch Technical Position 7-19 on Guidance for Evaluation of Diversity and Defense-in-Depth in Digital Computer- Based Instrumentation and Control Systems.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/24/
VL - 77
IS - 142
M3 - Article
SP - 43405
EP - 43406
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission (NRC) regarding the issuance of Standard Review Plans (SRPs) and Branch Technical Positions (BTPs) to facilitate timely implementation of staff guidance and to facilitate activities associated with the review for design certifications. The BTP is considered as the acceptance criteria for standard reactor designs that were not certified prior to the date of BTP. Further, the effective date of SRP update is August 23, 2012.
KW - STANDARDS
KW - GOVERNMENT policy
KW - CIVIL service
KW - CERTIFICATION
KW - NUCLEAR reactors
KW - DESIGN & construction
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 78329763; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors.; Issue Info: 7/24/2012, Vol. 77 Issue 142, p43405; Thesaurus Term: STANDARDS; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: CIVIL service; Thesaurus Term: CERTIFICATION; Subject Term: NUCLEAR reactors; Subject Term: DESIGN & construction; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Pelton, David L.
T1 - NRC Position on the Relationship Between General Design Criteria and Technical Specification Operability.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/07/31/
VL - 77
IS - 147
M3 - Article
SP - 45282
EP - 45285
SN - 00976326
AB - The article reports on a public meeting and request for comment relating to a draft regulatory issue summary (RIS) proposed by the U.S. Nuclear Regulatory Commission (NRC). It announces that the NRC will hold the public meeting to discuss the RIS that clarifies the position of its staff on the relationship between the general design criteria (GDC) for nuclear power plants and technical specification operability. It states that comments must be submitted on September 14, 2012.
KW - PUBLIC opinion
KW - NUCLEAR power plants
KW - POWER plants
KW - STANDARDS
KW - PUBLIC meetings
KW - DESIGN & construction
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 78560519; Pelton, David L. 1; Affiliations: 1: Chief, Generic Communications Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 7/31/2012, Vol. 77 Issue 147, p45282; Thesaurus Term: PUBLIC opinion; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: POWER plants; Thesaurus Term: STANDARDS; Subject Term: PUBLIC meetings; Subject Term: DESIGN & construction; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 4p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee On Economic Simplified Boiling Water Reactors (ESBWR); Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08//8/1/2012
VL - 77
IS - 148
M3 - Article
SP - 45699
EP - 45700
SN - 00976326
AB - The article presents the notice of the Nuclear Regulatory Commission that announces the meeting of the Advisory On Reactor Safeguards (ACRS) Subcommittee to be held in Rockville, Maryland on August 16, 2012.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards
N1 - Accession Number: 78560734; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 8/1/2012, Vol. 77 Issue 148, p45699; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission. Advisory Committee on Reactor Safeguards; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=78560734&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Galloway, Melanie A.
T1 - Interim Staff Guidance on Changes to the Generic Aging Lessons Learned (GALL) Report Revision 2 AMP XI.M41, ''Buried and Underground Piping and Tanks''.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/02/
VL - 77
IS - 149
M3 - Article
SP - 46127
EP - 46128
SN - 00976326
AB - The article presents the issued License Renewal Interim Staff Guidance (LR-ISG) by the U.S. Nuclear Regulatory Commission (NRC) in 2012. It says that the LR-ISG offers changes to the suggestions in the Generic Aging Lessons Learned (GALL) Report on underground piping and tanks following evaluations of several license renewal applications. The purpose of the said move is to communicate insights and lessons and manage issues excluded in license renewal guidance documents.
KW - BUSINESS licenses
KW - PIPELINE contractors
KW - GUIDELINES
KW - UNDERGROUND pipelines
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 78560849; Galloway, Melanie A. 1; Affiliations: 1: Deputy Director, Division of License Renewal, Office of Nuclear Reactor Regulation.; Issue Info: 8/2/2012, Vol. 77 Issue 149, p46127; Thesaurus Term: BUSINESS licenses; Thesaurus Term: PIPELINE contractors; Subject Term: GUIDELINES; Subject Term: UNDERGROUND pipelines; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; NAICS/Industry Codes: 237120 Oil and Gas Pipeline and Related Structures Construction; NAICS/Industry Codes: 238290 Other Building Equipment Contractors; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Proposed Revision 0 to Standard Review Plan Section 19.5: Adequacy of Design Features and Functional Capabilities Identified and Described for Withstanding Aircraft Impacts.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/02/
VL - 77
IS - 149
M3 - Article
SP - 46128
EP - 46129
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission (NRC) which seeks for public comments on a proposed revision to its standard review plan (SRP) in 2012. It says that the SRP is all about the design features and functions determined for withstanding aircraft impacts. The deadline for the submission of comments is 30 days after the notice's publication.
KW - STANDARDS
KW - AIRPLANES
KW - REVISIONS
KW - DESIGN & construction
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 78560850; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors.; Issue Info: 8/2/2012, Vol. 77 Issue 149, p46128; Thesaurus Term: STANDARDS; Thesaurus Term: AIRPLANES; Subject Term: REVISIONS; Subject Term: DESIGN & construction; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 336411 Aircraft Manufacturing; NAICS/Industry Codes: 336410 Aerospace product and parts manufacturing; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/07/
VL - 77
IS - 152
M3 - Article
SP - 47121
EP - 47123
SN - 00976326
AB - The article reports on the request of exemption from the requirements of the Title 10 of the Code of Federal Regulations (10 CFR) to the U.S. Nuclear Regulatory Commission (NRC) by Calvert Cliffs Nuclear Power Plant LLC in 2012. It says that the exemption will allow the company to establish a 12-hour work schedule to ensure safety of operations during severe weather conditions. It notes that the NRC determined that the exemption involves no hazards considerations.
KW - WORKING hours
KW - INDUSTRIAL safety
KW - EXEMPTION (Law)
KW - UNITED States
KW - CALVERT Cliffs Nuclear Power Plant LLC
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 79285778; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 8/7/2012, Vol. 77 Issue 152, p47121; Thesaurus Term: WORKING hours; Thesaurus Term: INDUSTRIAL safety; Subject Term: EXEMPTION (Law); Subject: UNITED States ; Company/Entity: CALVERT Cliffs Nuclear Power Plant LLC ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Thompson, Jon H.
T1 - Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2, Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/09/
VL - 77
IS - 154
M3 - Article
SP - 47677
EP - 47680
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission (NRC) on the consideration of issuance of amendment to facility operating license to Duke Energy Carolinas LLC for operation of its McGuire Nuclear Station in North Carolina. The NRC has made proposed determination that such amendment request involves no significant hazards consideration. Meanwhile, interested parties are requested to submit their comments regarding the consideration of issuance by September 10, 2012.
KW - LICENSES
KW - OCCUPATIONAL hazards
KW - AMENDED & supplemental pleading
KW - NORTH Carolina
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - DUKE Energy Carolinas LLC
N1 - Accession Number: 79286042; Thompson, Jon H. 1; Affiliations: 1: Project Manager, Plant Licensing Branch II- 1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 8/9/2012, Vol. 77 Issue 154, p47677; Thesaurus Term: LICENSES; Thesaurus Term: OCCUPATIONAL hazards; Subject Term: AMENDED & supplemental pleading; Subject: NORTH Carolina; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DUKE Energy Carolinas LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 4p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=79286042&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Leeds, Eric J.
T1 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station Receipt of Request for Action.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/09/
VL - 77
IS - 154
M3 - Article
SP - 47680
EP - 47681
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission (NRC) regarding a request from someone named Ms. Mary Lampert with regard to the Pilgrim Nuclear Power Station in pursuant to Title 10 of the Code of Federal Regulations (10 CFR). One of the requests of the petitioner is for NRC to commit to a timely upgrade of the regulatory guidance for maintaining cable qualification. Other specific issues and concerns identified in the July 19, 2010 petition are also tackled.
KW - UNITED States. Advisory Committee on Reactor Safeguards
KW - MASSACHUSETTS
KW - UNITED States
KW - PILGRIM Nuclear Power Station (Mass.)
KW - LAMPERT, Mary
N1 - Accession Number: 79286044; Leeds, Eric J. 1; Affiliations: 1: Director, Office of Nuclear Reactor Regulation.; Issue Info: 8/9/2012, Vol. 77 Issue 154, p47680; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards; Subject: MASSACHUSETTS; Subject: UNITED States ; Company/Entity: PILGRIM Nuclear Power Station (Mass.); People: LAMPERT, Mary; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=79286044&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittees on Reliability and PRA and Fukushima; Revision to Notice of Meetings.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/09/
VL - 77
IS - 154
M3 - Article
SP - 47680
EP - 47680
SN - 00976326
AB - The article announces that the meeting of Advisory Committee on Reactor Safeguards (ACRS) on Fukushima of the U.S. Nuclear Regulatory Commission on August 14, 2012 has been moved to August 15 while ACRS Subcommittee on Reliability and Probabilistic Risk Assessment (PRA) meeting has been cancelled.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards
KW - UNITED States
N1 - Accession Number: 79286043; Santos, Cayetano 1; Affiliations: 1: Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards.; Issue Info: 8/9/2012, Vol. 77 Issue 154, p47680; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards; Subject: UNITED States; Number of Pages: 1/5p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=79286043&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Sebrosky, Joseph M.
T1 - Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3; Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards Consideration Determination.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/16/
VL - 77
IS - 159
M3 - Article
SP - 49463
EP - 49472
SN - 00976326
AB - The article focuses on a notice given by the U.S. Nuclear Regulatory Commission (NRC) regarding license amendment request. Applicants can access information regarding operation of the San Onofre Nuclear Generating Station (SONGS) in California from Federal rulemaking websites, NRC Agencywide Documents Access and Management System (ADAMS) or NRC Public Document Room (PDR) and file their comments by September 17, 2012 and request of hearing and petition by October 15, 2012.
KW - LICENSES
KW - PETITIONS
KW - CALIFORNIA
KW - U.S. Nuclear Regulatory Commission
KW - SAN Onofre Nuclear Generating Station (Calif.)
N1 - Accession Number: 79450053; Sebrosky, Joseph M. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 8/16/2012, Vol. 77 Issue 159, p49463; Thesaurus Term: LICENSES; Subject Term: PETITIONS; Subject: CALIFORNIA ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: SAN Onofre Nuclear Generating Station (Calif.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 10p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Kim, James
T1 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit 3.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/21/
VL - 77
IS - 162
M3 - Article
SP - 50533
EP - 50534
SN - 00976326
AB - The article reports a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding environmental assessment related to Millstone Power Station, Unit 3 (MPS3) located in the town of Waterford, Connecticut. It mentions that NRC conducted the environmental impact analysis of MPS3 in order to find the suitability of license issued to Dominion Nuclear Connecticut Inc. for the operation of MPS3.
KW - ENVIRONMENTAL impact analysis
KW - NUCLEAR power plants
KW - LICENSES
KW - WATERFORD (Conn.)
KW - CONNECTICUT
KW - U.S. Nuclear Regulatory Commission
KW - DOMINION Nuclear Connecticut Inc.
N1 - Accession Number: 79469929; Kim, James 1; Affiliations: 1: Project Manager, Plant Licensing Branch 1- 1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 8/21/2012, Vol. 77 Issue 162, p50533; Thesaurus Term: ENVIRONMENTAL impact analysis; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject: WATERFORD (Conn.); Subject: CONNECTICUT ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DOMINION Nuclear Connecticut Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Singal, Balwant K.
T1 - STP Nuclear Operating Company, South Texas Project, Units 1 and 2; Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/21/
VL - 77
IS - 162
M3 - Article
SP - 50541
EP - 50541
SN - 00976326
AB - The article reports a notice issued by the U.S. Nuclear Regulatory Commission (NRC), an independent agency to ensure the safe use of radioactive materials for beneficial civilian purposes while protecting people and the environment, regarding proposed amendment to facility operating licenses for the South Texas Project (STP) nuclear Operating Co. located in Matagorda County, Texas.
KW - LICENSES
KW - NUCLEAR power plants
KW - INDEPENDENT regulatory commissions
KW - GOVERNMENT policy
KW - NUCLEAR energy
KW - MATAGORDA County (Tex.)
KW - TEXAS
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
KW - STP Nuclear Operating Co.
N1 - Accession Number: 79469931; Singal, Balwant K. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 8/21/2012, Vol. 77 Issue 162, p50541; Thesaurus Term: LICENSES; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: INDEPENDENT regulatory commissions; Thesaurus Term: GOVERNMENT policy; Subject Term: NUCLEAR energy; Subject: MATAGORDA County (Tex.); Subject: TEXAS; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: STP Nuclear Operating Co.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Tam, Peter S.
T1 - Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 2, Environmental Assessment and Finding of No Significant Impact.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/23/
VL - 77
IS - 164
M3 - Article
SP - 51071
EP - 51072
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding environmental assessment of the exemption and amendment to Renewed Facility Operating License issued to Indiana Michigan Power Co. The license was issued for operation of Donald C. Cook Nuclear Plant, Unit 2 in Michigan. The amendment and exemption issued would not affect plant safety or change normal plant operating conditions.
KW - LICENSES
KW - NUCLEAR power plants -- Environmental aspects
KW - MICHIGAN
KW - U.S. Nuclear Regulatory Commission
KW - INDIANA Michigan Power Co.
N1 - Accession Number: 79470045; Tam, Peter S. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch III-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 8/23/2012, Vol. 77 Issue 164, p51071; Thesaurus Term: LICENSES; Thesaurus Term: NUCLEAR power plants -- Environmental aspects; Subject: MICHIGAN ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: INDIANA Michigan Power Co. DUNS Number: 006985584 Ticker: IMK; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Dominion Nuclear Connecticut, Inc. Millstone Power Station, Unit 3; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/08/30/
VL - 77
IS - 169
M3 - Article
SP - 52765
EP - 52766
SN - 00976326
AB - The article informs about a notice issued by the U.S. Nuclear Regulatory Commission (NRC). The notice informs that NRC grants Dominion Nuclear Connecticut Inc. an exemption for Renewed Facility Operating License authorizing operation of the Millstone Power Station, Unit 3 (MPS3) located in Waterford, Connecticut.
KW - NUCLEAR power plants
KW - UNITED States. National Regulatory Commission
KW - EXEMPTION (Law)
KW - WATERFORD (Conn.)
KW - CONNECTICUT
KW - DOMINION Nuclear Connecticut Inc.
N1 - Accession Number: 79837271; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 8/30/2012, Vol. 77 Issue 169, p52765; Thesaurus Term: NUCLEAR power plants; Subject Term: UNITED States. National Regulatory Commission; Subject Term: EXEMPTION (Law); Subject: WATERFORD (Conn.); Subject: CONNECTICUT ; Company/Entity: DOMINION Nuclear Connecticut Inc.; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
ID - 108077176
T1 - US NRC discussion of options to revise radiation protection recommendations.
AU - Cool, D A
Y1 - 2012/09//
N1 - Accession Number: 108077176. Language: English. Entry Date: 20130329. Revision Date: 20150712. Publication Type: Journal Article. Journal Subset: Biomedical. Special Interest: Diagnostic Imaging. NLM UID: 7708044.
KW - United States Nuclear Regulatory Commission
KW - Government Regulations -- United States
KW - United States
SP - 313
EP - 317
JO - Annals of the ICRP
JF - Annals of the ICRP
JA - ANN ICRP
VL - 41
IS - 3-4
CY - Thousand Oaks, California
PB - Sage Publications Inc.
SN - 0146-6453
AD - US Nuclear Regulatory Commission, Office of Federal and State Materials and Environmental Management Programs, Washington, DC 20555, USA. Electronic address: Donald.Cool@nrc.gov.
U2 - PMID: 23089031.
DO - 10.1016/j.icrp.2012.06.006
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DP - EBSCOhost
DB - rzh
ER -
TY - JOUR
ID - 2012-22614-002
AN - 2012-22614-002
AU - Gallucci, Raymond
T1 - 'What—Me worry?' 'Why so serious?': A personal view on the Fukushima nuclear reactor accidents.
JF - Risk Analysis
JO - Risk Analysis
JA - Risk Anal
Y1 - 2012/09//
VL - 32
IS - 9
SP - 1444
EP - 1450
CY - United Kingdom
PB - Wiley-Blackwell Publishing Ltd.
SN - 0272-4332
SN - 1539-6924
AD - Gallucci, Raymond, U.S. Nuclear Regulatory Commission, Mail Stop O-10C15, Washington, DC, US, 20555
N1 - Accession Number: 2012-22614-002. PMID: 22394214 Partial author list: First Author & Affiliation: Gallucci, Raymond; U.S. Nuclear Regulatory Commission, Washington, DC, US. Other Publishers: Blackwell Publishing. Release Date: 20121119. Publication Type: Journal (0100), Peer Reviewed Journal (0110). Format Covered: Electronic. Document Type: Journal Article. Language: English. Major Descriptor: Natural Disasters; Nuclear Technology; Safety. Classification: Environmental Issues & Attitudes (4070). Population: Human (10). Location: Japan. Tests & Measures: International Nuclear and Radiological Event Scale. References Available: Y. Page Count: 7. Issue Publication Date: Sep, 2012. Copyright Statement: Society for Risk Analysis. 2012.
AB - Infrequently, it seems that a significant accident precursor or, worse, an actual accident, involving a commercial nuclear power reactor occurs to remind us of the need to reexamine the safety of this important electrical power technology from a risk perspective. Twenty‐five years since the major core damage accident at Chernobyl in the Ukraine, the Fukushima reactor complex in Japan experienced multiple core damages as a result of an earthquake‐induced tsunami beyond either the earthquake or tsunami design basis for the site. Although the tsunami itself killed tens of thousands of people and left the area devastated and virtually uninhabitable, much concern still arose from the potential radioactive releases from the damaged reactors, even though there was little population left in the area to be affected. As a lifelong probabilistic safety analyst in nuclear engineering, even I must admit to a recurrence of the doubt regarding nuclear power safety after Fukushima that I had experienced after Three Mile Island and Chernobyl. This article is my attempt to 'recover' my personal perspective on acceptable risk by examining both the domestic and worldwide history of commercial nuclear power plant accidents and attempting to quantify the risk in terms of the frequency of core damage that one might glean from a review of operational history. (PsycINFO Database Record (c) 2016 APA, all rights reserved)
KW - nuclear power plants
KW - nuclear reactor accidents
KW - risk
KW - earthquake
KW - tsunami
KW - 2012
KW - Natural Disasters
KW - Nuclear Technology
KW - Safety
KW - 2012
DO - 10.1111/j.1539-6924.2011.01780.x
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=psyh&AN=2012-22614-002&site=ehost-live&scope=site
UR - Ray.Gallucci@nrc.gov
DP - EBSCOhost
DB - psyh
ER -
TY - JOUR
AU - Leeds, Eric J.
T1 - Exelon Generation Company, LLC., Receipt of Request for Action.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/05/
VL - 77
IS - 172
M3 - Article
SP - 54619
EP - 54619
SN - 00976326
AB - The article presents a notice issued by the U.S. Nuclear Regulatory Commission regarding the closure of Byron Station, Units 1 and 2, andBraidwood Station, Units 1 and 2, of Exelon Generation Co. LLC. It mentions that the combustion air can be diluted with steam so its sufficient supply to diesel generators (DG) is threatened. It states that NRC is treating it pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 2.206.
KW - NUCLEAR power plant shutdowns
KW - ELECTRIC power production
KW - FEDERAL regulation
KW - COMBUSTION
KW - STEAM
KW - U.S. Nuclear Regulatory Commission
KW - EXELON Generation Co. LLC
N1 - Accession Number: 79962659; Leeds, Eric J. 1; Affiliations: 1: Director, Office of Nuclear Reactor Regulation; Issue Info: 9/5/2012, Vol. 77 Issue 172, p54619; Thesaurus Term: NUCLEAR power plant shutdowns; Thesaurus Term: ELECTRIC power production; Thesaurus Term: FEDERAL regulation; Subject Term: COMBUSTION; Subject Term: STEAM ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: EXELON Generation Co. LLC; NAICS/Industry Codes: 221112 Fossil Fuel Electric Power Generation; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Pelton, David L.
T1 - Clarification of Submission of Requests for Relief or Alternatives From the Regulatory Requirements Pertaining to Codes and Standards.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/06/
VL - 77
IS - 173
M3 - Article
SP - 54839
EP - 54843
SN - 00976326
AB - The article informs that the U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS). It informs that the draft RIS provides information on requests for alternatives to and relief from the regulatory requirements pertaining to Codes and Standards. It mentions that the draft is publicly available and information on the procedure to send the comments is also provided.
KW - GOVERNMENT policy
KW - DELEGATED legislation
KW - GOVERNMENT regulation
KW - GOVERNMENT standards
KW - NUCLEAR energy
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 79962716; Pelton, David L. 1; Affiliations: 1: Chief, Generic Communications Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 9/6/2012, Vol. 77 Issue 173, p54839; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: DELEGATED legislation; Thesaurus Term: GOVERNMENT regulation; Thesaurus Term: GOVERNMENT standards; Subject Term: NUCLEAR energy; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 5p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=79962716&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Monninger, John D.
T1 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-01; Compliance With Order EA-12-049, Order Modifying Licenses With Regard to Requirements for Mitigation Strategies for Beyond- Design-Basis External Events.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/07/
VL - 77
IS - 174
M3 - Article
SP - 55230
EP - 55231
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding issuance of the Final Japan Lessons-Learned Project Directorate Interim Staff Guidance (JLD-ISG). JLD-ISG "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" provides guidance to assist nuclear reactor applicants and licensees with the measures needed to mitigate challenges to safety functions.
KW - GOVERNMENT agencies
KW - NUCLEAR reactors -- Safety measures
KW - COUNSELORS
KW - NUCLEAR energy
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 79962913; Monninger, John D. 1; Affiliations: 1: Associate Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation.; Issue Info: 9/7/2012, Vol. 77 Issue 174, p55230; Thesaurus Term: GOVERNMENT agencies; Subject Term: NUCLEAR reactors -- Safety measures; Subject Term: COUNSELORS; Subject Term: NUCLEAR energy ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 911910 Other federal government public administration; NAICS/Industry Codes: 912910 Other provincial and territorial public administration; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; NAICS/Industry Codes: 921190 Other General Government Support; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=79962913&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Monninger, John D.
T1 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-02; Compliance With Order EA-12-050, Order Modifying Licenses With Regard to Reliable Hardened Containment Vents.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/07/
VL - 77
IS - 174
M3 - Article
SP - 55231
EP - 55232
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding issuance of the Final Japan Lessons-Learned Project Directorate Interim Staff Guidance (JLD-ISG). JLD-ISG "Compliance with Order EA-12-050, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents" provides guidance to assist nuclear power reactor applicants and licensees with the measures needed to mitigate challenges to safety functions.
KW - LICENSES
KW - COUNSELORS
KW - GAS appliances -- Vents
KW - NUCLEAR energy
KW - NUCLEAR reactors -- Safety measures
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 79962914; Monninger, John D. 1; Affiliations: 1: Associate Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation.; Issue Info: 9/7/2012, Vol. 77 Issue 174, p55231; Thesaurus Term: LICENSES; Subject Term: COUNSELORS; Subject Term: GAS appliances -- Vents; Subject Term: NUCLEAR energy; Subject Term: NUCLEAR reactors -- Safety measures ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=79962914&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Monninger, John D.
T1 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-03; Compliance With Order EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/07/
VL - 77
IS - 174
M3 - Article
SP - 55232
EP - 55233
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding issuance of the Final Japan Lessons-Learned Project Directorate Interim Staff Guidance (JLD-ISG). JLD-ISG "Compliance with Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation" provides guidance to assist nuclear power reactor applicants and licensees with the measures needed to install enhanced spent fuel pool monitoring capability.
KW - LICENSES
KW - COUNSELORS
KW - SPENT reactor fuels
KW - NUCLEAR energy
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 79962915; Monninger, John D. 1; Affiliations: 1: Associate Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation.; Issue Info: 9/7/2012, Vol. 77 Issue 174, p55232; Thesaurus Term: LICENSES; Subject Term: COUNSELORS; Subject Term: SPENT reactor fuels; Subject Term: NUCLEAR energy ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=79962915&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Bahadur, Sher
T1 - Fitness-for-Duty Programs.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/10/
VL - 77
IS - 175
M3 - Article
SP - 55429
EP - 55430
SN - 00976326
AB - The article offers information on a notice regarding proposed rules related to the Fitness-for-Duty Program, employee record program issued by the U.S. Nuclear Regulatory Commission (NRC). The NRC will release several documents informing about the proposed rulemaking effort to amend its regulations regarding the program. It also mentions that availability of these documents publicly will bring awareness to interested stakeholders.
KW - ADMINISTRATIVE procedure
KW - GOVERNMENT programs
KW - STAKEHOLDERS
KW - GOVERNMENT regulation
KW - CIVIL service
KW - PUBLIC records
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 80162552; Bahadur, Sher 1; Affiliations: 1: Deputy Director, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 9/10/2012, Vol. 77 Issue 175, p55429; Thesaurus Term: ADMINISTRATIVE procedure; Thesaurus Term: GOVERNMENT programs; Thesaurus Term: STAKEHOLDERS; Thesaurus Term: GOVERNMENT regulation; Thesaurus Term: CIVIL service; Subject Term: PUBLIC records ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 921190 Other General Government Support; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80162552&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Snyder, Amy M.
T1 - Approval of Transfer of Early Site Permit (ESP) and Conforming Amendment, Virginia Electric and Power Company, North Anna ESP Site.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/10/
VL - 77
IS - 175
M3 - Article
SP - 55507
EP - 55509
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission. The notice is related to the transfer of early site permit, transfer of licenses and application for amendment of license, construction permit, or early site permit. The notice seeks public comments until October 10, 2012 and mentions that any request for a hearing must be filed by October 1, 2012.
KW - LICENSES
KW - BUILDING permits
KW - NUCLEAR power plants
KW - PUBLIC opinion
KW - EARLY site permits
KW - LEGISLATIVE amendments
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 80162624; Snyder, Amy M. 1; Affiliations: 1: Acting Chief, Projects Licensing Branch 2, Division of New Reactor Licensing, Office of New Reactors; Issue Info: 9/10/2012, Vol. 77 Issue 175, p55507; Thesaurus Term: LICENSES; Thesaurus Term: BUILDING permits; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: PUBLIC opinion; Subject Term: EARLY site permits; Subject Term: LEGISLATIVE amendments ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80162624&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele
T1 - Indiana Michigan Power Company; Donald C. Cook Nuclear Plant, Unit 2; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/10/
VL - 77
IS - 175
M3 - Article
SP - 55509
EP - 55510
SN - 00976326
AB - The article informs that the Indian Michigan Power Co. is the holder of Renewed Facility Operating License No. DPR-74, which authorizes operation of the Donald C. Cook Nuclear Plant. It informs that the license provides that the facility is subject to all rules, regulations, and orders of the U.S Nuclear Regulatory Commission. It mentions about the exemption of the licensee from the requirements of 10 CFR 50.46 and Appendix K for the use of zircaloy fuel rod cladding.
KW - NUCLEAR power plants
KW - LICENSES
KW - DELEGATED legislation
KW - EXEMPTION (Law)
KW - ZIRCALOY-2
KW - NUCLEAR fuel claddings
KW - INDIAN Michigan Power Co.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 80162625; Evans, Michele 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 9/10/2012, Vol. 77 Issue 175, p55509; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Thesaurus Term: DELEGATED legislation; Subject Term: EXEMPTION (Law); Subject Term: ZIRCALOY-2; Subject Term: NUCLEAR fuel claddings ; Company/Entity: INDIAN Michigan Power Co. ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80162625&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Skeen, David L.
T1 - Guidance on Performing a Seismic Margin Assessment.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/10/
VL - 77
IS - 175
M3 - Article
SP - 55510
EP - 55512
SN - 00976326
AB - The article informs that the U.S. Nuclear Regulatory Commission (NRC) is issuing the draft Japan Lessons-Learned Project Directorate Interim Staff Guidance ''Guidance on Performing a Seismic Margin Assessment in response to the March 2012 Request for Information Letter". The draft provides guidance on an acceptable method for licensees to carry out a Seismic Margins Analysis (SMA) method. NRC seeks public comments related to the draft before October 10, 2012.
KW - PUBLIC opinion
KW - GOVERNMENT policy
KW - LICENSES
KW - GOVERNMENT agencies
KW - NUCLEAR reactors
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 80162626; Skeen, David L. 1; Affiliations: 1: Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation; Issue Info: 9/10/2012, Vol. 77 Issue 175, p55510; Thesaurus Term: PUBLIC opinion; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: LICENSES; Thesaurus Term: GOVERNMENT agencies; Subject Term: NUCLEAR reactors; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80162626&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Leeds, Eric J.
T1 - Florida Power & Light Company; Receipt of Request for Action.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/11/
VL - 77
IS - 176
M3 - Article
SP - 55878
EP - 55879
SN - 00976326
AB - The article offers information on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) related to the request of a petitioner Thomas King for taking action with regard to Saint Lucie Nuclear Plant, Units 1 and 2, and Turkey Point Nuclear Generating, Units 3 and 4.
KW - U.S. Nuclear Regulatory Commission
KW - SAINT Lucie Nuclear Plant (Fla.)
KW - KING, Thomas
N1 - Accession Number: 80146743; Leeds, Eric J. 1; Affiliations: 1: Director, Office of Nuclear Reactor Regulation.; Issue Info: 9/11/2012, Vol. 77 Issue 176, p55878 ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: SAINT Lucie Nuclear Plant (Fla.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; People: KING, Thomas; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80146743&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Benney, Brian J.
T1 - Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station; Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/12/
VL - 77
IS - 177
M3 - Article
SP - 56238
EP - 56239
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding withdrawal of the license amendment application. The proposed amendment filed by Wolf Creek Nuclear Operating Corp. of WOLF Creek Nuclear Generating Station of Kansas replaces the large break loss-of-coolant accident (LOCA) analysis methodology.
KW - LICENSE agreements
KW - KANSAS
KW - U.S. Nuclear Regulatory Commission
KW - WOLF Creek Nuclear Generating Station (Kan.)
KW - WOLF Creek Nuclear Operating Corp.
N1 - Accession Number: 80146849; Benney, Brian J. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 9/12/2012, Vol. 77 Issue 177, p56238; Thesaurus Term: LICENSE agreements; Subject: KANSAS ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: WOLF Creek Nuclear Generating Station (Kan.) ; Company/Entity: WOLF Creek Nuclear Operating Corp. DUNS Number: 173479478; NAICS/Industry Codes: 533110 Lessors of Nonfinancial Intangible Assets (except Copyrighted Works); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80146849&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/12/
VL - 77
IS - 177
M3 - Proceeding
SP - 56240
EP - 56240
SN - 00976326
AB - The article offers information on a meeting of the Advisory Committee on Reactor Safeguards (ACRS) subcommittee on Radiation Protection and Nuclear Materials to be held on September 18, 2012 at Rockville Pike, Maryland organized by the U.S. Nuclear Regulatory Commission (NRC).
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - RADIATION -- Safety measures
N1 - Accession Number: 80146853; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 9/12/2012, Vol. 77 Issue 177, p56240; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject Term: RADIATION -- Safety measures; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Proceeding
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80146853&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Matthews, David B.
T1 - Notice of Withdrawal of Final Design Approval; Westinghouse Electric Company; Advanced Passive 1000.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/12/
VL - 77
IS - 177
M3 - Article
SP - 56241
EP - 56241
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding withdrawal of the final design approval (FDA) for the Advanced Passive 1000 (AP1000) requested by Westinghouse Electric Co. AP1000 design (FDA) superseded the previous NCR approved versions of design certification (DCR) for AP1000 design control document (DCD) and was preferred not to update the AP1000 FDA of the DCD.
KW - CERTIFICATION
KW - PRESSURIZED water reactors
KW - NUCLEAR reactors -- Design & construction
KW - U.S. Nuclear Regulatory Commission
KW - WESTINGHOUSE Electric Co.
N1 - Accession Number: 80146855; Matthews, David B. 1; Affiliations: 1: Director, Division of New Reactor Licensing, Office of New Reactors.; Issue Info: 9/12/2012, Vol. 77 Issue 177, p56241; Thesaurus Term: CERTIFICATION; Subject Term: PRESSURIZED water reactors; Subject Term: NUCLEAR reactors -- Design & construction ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: WESTINGHOUSE Electric Co.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80146855&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Tran, Linh N.
T1 - Guidelines for Preparing and Reviewing Licensing Applications for Instrumentation and Control Upgrades for Non-Power Reactors.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/20/
VL - 77
IS - 183
M3 - Article
SP - 58419
EP - 58420
SN - 00976326
AB - The article reports a notice issued by the U.S. Nuclear Regulatory Commission (NRC) seeking comments regarding guidelines related to reviewing licensing applications for instrumentation and control (I&C) systems for non power reactors. It mentions that the same revises the guidelines for preparing and reviewing applications related to facility operating license for I&C upgrades. It further states that the comments regarding the same must reach NRC on or before December 4, 2012.
KW - LICENSES
KW - GOVERNMENT agencies
KW - FACILITY management
KW - GOVERNMENT policy
KW - PUBLIC opinion
KW - GUIDELINES
KW - RULES & practice
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 80734239; Tran, Linh N. 1; Affiliations: 1: Acting Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 9/20/2012, Vol. 77 Issue 183, p58419; Thesaurus Term: LICENSES; Thesaurus Term: GOVERNMENT agencies; Thesaurus Term: FACILITY management; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: PUBLIC opinion; Subject Term: GUIDELINES; Subject Term: RULES & practice; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 531120 Lessors of Nonresidential Buildings (except Miniwarehouses); Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80734239&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Stuchell, Sheldon D.
T1 - Model Safety Evaluation for Plant- Specific Adoption of Technical Specifications Task Force Traveler TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements To Operate for 10 Hours per Month," Using the Consolidated Line Item Improvement Process
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/20/
VL - 77
IS - 183
M3 - Article
SP - 58421
EP - 58421
SN - 00976326
AB - The article reports a notice of availability issued by the U.S. Nuclear Regulatory Commission (NRC) regarding technical specifications task force traveller revision entitled "Revise Ventilation System (VS) Surveillance Requirements (SR) to Operate for 10 Hours per Month". It mentions that the revision shall be applicable to SR which operate VS for at least 10 hours with the heaters. It further states that details regarding same shall be accessible to public via web based information portal.
KW - HEATING & ventilation industry
KW - GOVERNMENT policy
KW - ACCESS control
KW - GOVERNMENT information
KW - REVISIONS
KW - WEB-based user interfaces
KW - VENTILATION
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 80734241; Stuchell, Sheldon D. 1; Affiliations: 1: Acting Chief, Licensing Processes Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 9/20/2012, Vol. 77 Issue 183, p58421; Thesaurus Term: HEATING & ventilation industry; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: ACCESS control; Subject Term: GOVERNMENT information; Subject Term: REVISIONS; Subject Term: WEB-based user interfaces; Subject Term: VENTILATION; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 238220 Plumbing, Heating, and Air-Conditioning Contractors; NAICS/Industry Codes: 221330 Steam and Air-Conditioning Supply; Number of Pages: 2/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=80734241&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Determining Technical Adequacy of Probabilistic Risk Assessment for Risk-Informed License Amendment Requests After Initial Fuel Load.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/21/
VL - 77
IS - 184
M3 - Article
SP - 58590
EP - 58591
SN - 00976326
AB - The article informs about a notice issued by the U.S. Nuclear Regulatory Commission (NRC). The notice informs that NRC issues its final revision to Standard Review Plan (SRP) Section 19.1 entitled ''Determining the Technical Adequacy of Probabilistic Risk Assessment for Risk-Informed License Amendment Requests after Initial Fuel Load''. The proposed revision facilitates timely implementation of the current staff guidance and reviews to licenses for operating reactors.
KW - RISK assessment
KW - LICENSES
KW - NUCLEAR reactors
KW - NUCLEAR fuels
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 81283239; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors; Issue Info: 9/21/2012, Vol. 77 Issue 184, p58590; Thesaurus Term: RISK assessment; Thesaurus Term: LICENSES; Subject Term: NUCLEAR reactors; Subject Term: NUCLEAR fuels ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=81283239&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Turtil, Richard H.
T1 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/21/
VL - 77
IS - 184
M3 - Article
SP - 58591
EP - 58592
SN - 00976326
AB - The article informs about a notice issued by the U.S. Nuclear Regulatory Commission (NRC). The notice informs that NPC issues a document entitled ''Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities''. The notice invites public comments on the documents which are to be submitted to NRC in Washington D.C.
KW - WASTE management
KW - PUBLIC opinion
KW - COSTS
KW - INCINERATION
KW - WASHINGTON (D.C.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 81283241; Turtil, Richard H. 1; Affiliations: 1: Acting Chief, Financial Analysis and International Projects Branch, Division of Inspection and Regional Support, Office of Nuclear Reactor Regulation; Issue Info: 9/21/2012, Vol. 77 Issue 184, p58591; Thesaurus Term: WASTE management; Thesaurus Term: PUBLIC opinion; Subject Term: COSTS; Subject Term: INCINERATION; Subject: WASHINGTON (D.C.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 562213 Solid Waste Combustors and Incinerators; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=81283241&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Skeen, David L.
T1 - Compliance With Information Request, Flooding Hazard Reevaluation.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/28/
VL - 77
IS - 189
M3 - Article
SP - 59675
EP - 59676
SN - 00976326
AB - The article informs about a notice issued by the U.S. Nuclear Regulatory Commission (NRC). The notice informs that the draft Japan Lessons-Learned Project Directorate Interim Staff Guidance (JLD-ISG) is issued by the NRC entitled as ''Performance of an Integrated Assessment'' which provides guidance to assist nuclear power reactor applicants and licensees. The notice invites public comments on the proposed guidance which are to be submitted to NRC in Washington D.C.
KW - LICENSES
KW - GOVERNMENT agencies
KW - PUBLIC opinion
KW - NUCLEAR reactors
KW - WASHINGTON (D.C.)
KW - JAPAN
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82191883; Skeen, David L. 1; Affiliations: 1: Director, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation.; Issue Info: 9/28/2012, Vol. 77 Issue 189, p59675; Thesaurus Term: LICENSES; Thesaurus Term: GOVERNMENT agencies; Thesaurus Term: PUBLIC opinion; Subject Term: NUCLEAR reactors; Subject: WASHINGTON (D.C.); Subject: JAPAN ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 913910 Other local, municipal and regional public administration; NAICS/Industry Codes: 912910 Other provincial and territorial public administration; NAICS/Industry Codes: 911910 Other federal government public administration; NAICS/Industry Codes: 921190 Other General Government Support; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82191883&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Reliability and PRA; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/28/
VL - 77
IS - 189
M3 - Article
SP - 59677
EP - 59678
SN - 00976326
AB - The article informs about a meeting of Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Reliability and PRA organized by the U.S. Nuclear Regulatory Commission (NRC) to be held on October 2, 2012 at Rockville, Maryland.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82191886; Santos, Cayetano 1; Affiliations: 1: Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards.; Issue Info: 9/28/2012, Vol. 77 Issue 189, p59677; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82191886&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards (ACRS), Meeting of the ACRS Subcommittee on Advanced Boiling Water Reactor; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/28/
VL - 77
IS - 189
M3 - Article
SP - 59678
EP - 59678
SN - 00976326
AB - The article informs about a meeting of Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Advanced Boiling Water Reactor organized by the U.S. Nuclear Regulatory Commission (NRC) to be held on October 2, 2012 at Rockville, Maryland.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82191887; Santos, Cayetano 1; Affiliations: 1: Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards.; Issue Info: 9/28/2012, Vol. 77 Issue 189, p59678; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82191887&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Leeds, Eric J.
T1 - Central Vermont Public Service Corporation (Millstone Power Station, Unit 3); Order Approving Application Regarding Corporate Restructuring and Conforming Amendment.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/09/28/
VL - 77
IS - 189
M3 - Article
SP - 59679
EP - 59680
SN - 00976326
AB - The article informs about informs about a notice issued by the U.S. Nuclear Regulatory Commission (NRC). The notice informs that the Dominion Nuclear Connecticut Inc. (DNC), Central Vermont Public Service Corp. (CVPS) and Massachusetts Municipal Wholesale Electric Co. (MMWE) as the co-holders of the Renewed Facility Operating License authorizing the use, possession and operation of Millstone Power Station, Unit 3 (MPS3) located in Waterford, Connecticut.
KW - MEETINGS
KW - LICENSES
KW - WATERFORD (Conn.)
KW - CONNECTICUT
KW - CENTRAL Vermont Public Service Corp.
KW - DOMINION Nuclear Connecticut Inc.
KW - MASSACHUSETTS Municipal Wholesale Electric Co.
N1 - Accession Number: 82191889; Leeds, Eric J. 1; Affiliations: 1: Director, Office of Nuclear Reactor Regulation.; Issue Info: 9/28/2012, Vol. 77 Issue 189, p59679; Thesaurus Term: MEETINGS; Thesaurus Term: LICENSES; Subject: WATERFORD (Conn.); Subject: CONNECTICUT ; Company/Entity: CENTRAL Vermont Public Service Corp. DUNS Number: 007939614 Ticker: CV ; Company/Entity: DOMINION Nuclear Connecticut Inc. ; Company/Entity: MASSACHUSETTS Municipal Wholesale Electric Co. DUNS Number: 071724900; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cool, D.A.
T1 - US NRC discussion of options to revise radiation protection recommendations
JO - Annals of the ICRP
JF - Annals of the ICRP
Y1 - 2012/10//
VL - 41
IS - 3/4
M3 - Article
SP - 313
EP - 317
SN - 01466453
AB - Abstract: The Nuclear Regulatory Commission (NRC) is continuing the process of engaging stakeholders on issues associated with possible changes to the radiation protection regulations contained in 10 CFR Part 20, and other parts of the NRC regulations, to increase alignment with international recommendations. The Commission is particularly seeking to explore implications, as appropriate and where scientifically justified, of greater alignment with the 2007 Recommendations of the International Commission for Radiological Protection. Other information from national and international sources is also being considered. Given that the NRC regulations provide adequate protection, the discussion has been focusing on discerning the benefits and burdens associated with revising the radiation protection regulatory framework. NRC, through three Federal Register Notices, has officially solicited comments on a series of key issues, and has conducted a series of facilitated workshops to encourage feedback from a wide range of stakeholders. The issues include the use of updated scientific methodologies and terminology, the occupational dose limits, and the use of the concepts of constraints in optimisation. NRC staff provided a policy paper with recommendations to the Commission on April 25, 2012 (NRC, 2012). [Copyright &y& Elsevier]
AB - Copyright of Annals of the ICRP is the property of Sage Publications Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RADIATION -- Safety measures
KW - STAKEHOLDERS
KW - RADIATION exposure
KW - UNITED States
KW - Dose limits
KW - Optimisation
KW - Regulation
KW - Stakeholder involvement
KW - U.S. Nuclear Regulatory Commission
KW - INTERNATIONAL Commission on Radiological Protection
N1 - Accession Number: 82598561; Cool, D.A. 1; Email Address: Donald.Cool@nrc.gov; Affiliation: 1: US Nuclear Regulatory Commission, Office of Federal and State Materials and Environmental Management Programs, Washington, DC 20555, USA; Source Info: Oct2012, Vol. 41 Issue 3/4, p313; Subject Term: RADIATION -- Safety measures; Subject Term: STAKEHOLDERS; Subject Term: RADIATION exposure; Subject Term: UNITED States; Author-Supplied Keyword: Dose limits; Author-Supplied Keyword: Optimisation; Author-Supplied Keyword: Regulation; Author-Supplied Keyword: Stakeholder involvement; Company/Entity: U.S. Nuclear Regulatory Commission Company/Entity: INTERNATIONAL Commission on Radiological Protection; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 5p; Document Type: Article
L3 - 10.1016/j.icrp.2012.06.006
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=82598561&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - WELLOCK, THOMAS R.
T1 - Engineering Uncertainty and Bureaucratic Crisis at the Atomic Energy Commission, 1964-1973.
JO - Technology & Culture
JF - Technology & Culture
Y1 - 2012/10//
VL - 53
IS - 4
M3 - Article
SP - 846
EP - 884
SN - 0040165X
AB - The article discusses the history of the U.S. Atomic Energy Commission (AEC) from 1964 to 1973, focusing on technical issues, engineering disputes, and a bureaucratic crisis, issues which led to the AEC's dissolution and the creation of the U.S. Joint Committee on Atomic Energy (JCAE). The author comments on the development of expertise among antinuclear activists and the work of economist Daniel Ford and lawyer Myron Cherry. Static safety systems and nuclear accident prevention are also discussed.
KW - NUCLEAR engineering -- History
KW - BUREAUCRACY
KW - HISTORY
KW - NUCLEAR accidents -- Prevention
KW - NUCLEAR energy -- Safety measures
KW - UNITED States
KW - U.S. Atomic Energy Commission
KW - UNITED States. Congress. Joint Committee on Atomic Energy
KW - FORD, Daniel
KW - CHERRY, Myron
N1 - Accession Number: 83392367; WELLOCK, THOMAS R. 1; Affiliation: 1: Historian, U.S. Nuclear Regulatory Commission; Source Info: Oct2012, Vol. 53 Issue 4, p846; Subject Term: NUCLEAR engineering -- History; Subject Term: BUREAUCRACY; Subject Term: HISTORY; Subject Term: NUCLEAR accidents -- Prevention; Subject Term: NUCLEAR energy -- Safety measures; Subject Term: UNITED States; Company/Entity: U.S. Atomic Energy Commission Company/Entity: UNITED States. Congress. Joint Committee on Atomic Energy; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; People: FORD, Daniel; People: CHERRY, Myron; Number of Pages: 39p; Document Type: Article
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Tran, Linh N.
T1 - Non-Power Reactor License Renewal.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/02/
VL - 77
IS - 191
M3 - Article
SP - 60039
EP - 60040
SN - 00976326
AB - The article presents information on the notice issued by the U.S. Nuclear Regulatory Commission on a final technical basis to support proceeding with rulemaking to streamline and enhance the Research and Test Reactor (RTR) License Renewal Process. It informs that the input from the public, licensees and stakeholders have been incorporated in the final regulatory basis (FRB). It further informs that objectives, conceptual approaches and related technical clarity issues are described by FRB.
KW - STAKEHOLDERS
KW - ADMINISTRATIVE procedure
KW - LICENSES
KW - GOAL (Psychology)
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82374075; Tran, Linh N. 1; Affiliations: 1: Acting Chief, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 10/2/2012, Vol. 77 Issue 191, p60039; Thesaurus Term: STAKEHOLDERS; Thesaurus Term: ADMINISTRATIVE procedure; Thesaurus Term: LICENSES; Subject Term: GOAL (Psychology); Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82374075&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Digital Instrumentation and Control Systems; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/03/
VL - 77
IS - 192
M3 - Article
SP - 60480
EP - 60480
SN - 00976326
AB - The article offers information on the notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding the Advisory Committee on Reactor Safeguards (ACRS) meeting to be held on October 30, 2012 in Rockville, Maryland.
KW - NUCLEAR reactors -- Safety measures -- Congresses
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82374308; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 10/3/2012, Vol. 77 Issue 192, p60480; Subject Term: NUCLEAR reactors -- Safety measures -- Congresses; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82374308&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Proposed Revision Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/09/
VL - 77
IS - 195
M3 - Article
SP - 61446
EP - 61447
SN - 00976326
AB - The article informs about a notice issued by the U.S. Nuclear RegulatoryCommission (NRC). The notice informs that NRC invites public comments on Standard review plan revision for Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors. The written comments are submitted to NRC in Washington D.C.
KW - RISK assessment
KW - PUBLIC opinion
KW - NUCLEAR reactors
KW - NUCLEAR accidents
KW - WASHINGTON (D.C.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82578496; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors.; Issue Info: 10/9/2012, Vol. 77 Issue 195, p61446; Thesaurus Term: RISK assessment; Thesaurus Term: PUBLIC opinion; Subject Term: NUCLEAR reactors; Subject Term: NUCLEAR accidents; Subject: WASHINGTON (D.C.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82578496&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Matthews, David B.
T1 - Exelon Generation Company, LLC, Victoria County Station Site; Notice of Withdrawal of Application for an Early Site Permit.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/10/
VL - 77
IS - 196
M3 - Article
SP - 61645
EP - 61645
SN - 00976326
AB - The article offers information about a notice issued by the U.S. Nuclear Regulatory Commission regarding the withdrawal of an application for an early site permit related to Exelon Generation Co. LLC.
KW - LICENSES
KW - U.S. Nuclear Regulatory Commission
KW - EXELON Generation Co. LLC
N1 - Accession Number: 82678959; Matthews, David B. 1; Affiliations: 1: Director, Division of New Reactor Licensing, Office of New Reactors.; Issue Info: 10/10/2012, Vol. 77 Issue 196, p61645; Thesaurus Term: LICENSES ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: EXELON Generation Co. LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82678959&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Sebrosky, Joseph M.
T1 - Pacific Gas and Electric; Diablo Canyon Power Plant, Units 1 and 2; Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/11/
VL - 77
IS - 197
M3 - Article
SP - 61790
EP - 61791
SN - 00976326
AB - The article informs about a notice issued by the U.S. Nuclear Regulatory Commission (NRC). The notice informs that NRC informs Pacific Gas and Electric Co. to withdraw the application for an amendment to Facility Operating License Nos. DPR-80 and DPR-82 for the Diablo Canyon Power Plant, Units 1 and 2 located at San Luis Obispo County in California.
KW - LICENSES
KW - SAN Luis Obispo County (Calif.)
KW - CALIFORNIA
KW - U.S. Nuclear Regulatory Commission
KW - PG & E Corp.
KW - DIABLO Canyon Nuclear Powerplant (Calif.)
N1 - Accession Number: 82585826; Sebrosky, Joseph M. 1; Affiliations: 1: Senior Project Manager, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/11/2012, Vol. 77 Issue 197, p61790; Thesaurus Term: LICENSES; Subject: SAN Luis Obispo County (Calif.); Subject: CALIFORNIA ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: PG & E Corp. DUNS Number: 006912877 ; Company/Entity: DIABLO Canyon Nuclear Powerplant (Calif.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82585826&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee On Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee On US-APWR; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/11/
VL - 77
IS - 197
M3 - Article
SP - 61791
EP - 61791
SN - 00976326
AB - The article informs about a meeting of the Advisory Committee on ReactorSafeguards (ACRS) Subcommittee on the U.S. Advanced Pressurized-Water Reactor (US-APWR) organized by the U.S. Nuclear Regulatory Commission to be held on October 18-19, 2012 at Rockville, Maryland.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82585827; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards.; Issue Info: 10/11/2012, Vol. 77 Issue 197, p61791; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82585827&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Proposed Revision Treatment of Non- Safety Systems for Passive Advanced Light Water Reactors.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/12/
VL - 77
IS - 198
M3 - Article
SP - 62270
EP - 62271
SN - 00976326
AB - The article offers information about a notice of proposed revision issued by the U.S. Nuclear Regulatory Commission seeking comments regarding treatment of non-safety systems related to passive advanced light water reactors. It mentions that NRC seeks comments on a proposed new section of its Standard Review Plan (SRP) entitled "Regulatory Treatment of Non-Safety Systems (RTNSS) for Passive Advanced Light Water Reactors" and states that the comments must be received by November 13, 2012.
KW - GOVERNMENT policy
KW - PUBLIC opinion
KW - GOVERNMENT agencies
KW - LIGHT water reactors -- Safety measures
KW - REVISIONS
KW - LIGHT water reactors
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82590983; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors.; Issue Info: 10/12/2012, Vol. 77 Issue 198, p62270; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: PUBLIC opinion; Thesaurus Term: GOVERNMENT agencies; Subject Term: LIGHT water reactors -- Safety measures; Subject Term: REVISIONS; Subject Term: LIGHT water reactors; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82590983&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit 2, Revocation of Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/15/
VL - 77
IS - 199
M3 - Article
SP - 62539
EP - 62540
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding exemption granted for license to Dominion Nuclear Connecticut Inc. which authorizes the operation of Millstone Power Station. The license for pressurized water reactor located in New London County, Connecticut was unable to prohibit the handling and storage of fuel assemblies under the adverse moderation conditions feasible by unborated water.
KW - LICENSES
KW - NUCLEAR power plants
KW - PRESSURIZED water reactors
KW - FUEL -- Storage
KW - NEW London County (Conn.)
KW - CONNECTICUT
KW - U.S. Nuclear Regulatory Commission
KW - DOMINION Nuclear Connecticut Inc.
N1 - Accession Number: 82831630; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/15/2012, Vol. 77 Issue 199, p62539; Thesaurus Term: LICENSES; Thesaurus Term: NUCLEAR power plants; Subject Term: PRESSURIZED water reactors; Subject Term: FUEL -- Storage; Subject: NEW London County (Conn.); Subject: CONNECTICUT ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: DOMINION Nuclear Connecticut Inc.; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82831630&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Sreenivas, V.
T1 - Virginia Electric and Power Company, Surry Power Station Units 1 and 2 and North Anna Power Station Units 1 and 2, Notice of Withdrawal of Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/16/
VL - 77
IS - 200
M3 - Article
SP - 63342
EP - 63343
SN - 00976326
AB - The article presents a notice issued by the U.S. Nuclear Regulatory Commission for granting the request filed by Virginia Electric and Power Co. to wihdraw its application related to a proposal for amending its facility operating license. The notice has been issued for two nucleear power plants located in Surry County and Mineral in Virginia.
KW - NUCLEAR power plants
KW - LICENSES
KW - DESIGN & construction
KW - SURRY County (Va.)
KW - MINERAL (Va.)
KW - VIRGINIA
KW - U.S. Nuclear Regulatory Commission
KW - VIRGINIA Electric & Power Co.
N1 - Accession Number: 82831754; Sreenivas, V. 1; Affiliations: 1: Project Manager, Plant Licensing Branch II-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/16/2012, Vol. 77 Issue 200, p63342; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: DESIGN & construction; Subject: SURRY County (Va.); Subject: MINERAL (Va.); Subject: VIRGINIA ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: VIRGINIA Electric & Power Co. DUNS Number: 007941446 Ticker: VEA; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82831754&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Gonzalez, Hipolito
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/18/
VL - 77
IS - 202
M3 - Article
SP - 64147
EP - 64148
SN - 00976326
AB - The article presents a notice issued by the U.S. Nuclear Regulatory Commission regarding a meeting of the Advisory Committee on Reactor Safeguards (ACRS) on Fukushima, Japan in which topics related to staff development will be discussed.
KW - NUCLEAR reactors -- Safety measures
KW - FUKUSHIMA-ken (Japan)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82767772; Gonzalez, Hipolito 1; Affiliations: 1: Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards.; Issue Info: 10/18/2012, Vol. 77 Issue 202, p64147; Subject Term: NUCLEAR reactors -- Safety measures; Subject: FUKUSHIMA-ken (Japan) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82767772&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Gonzalez, Hipolito
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Planning and Procedures; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/19/
VL - 77
IS - 203
M3 - Article
SP - 64361
EP - 64361
SN - 00976326
AB - The article offers information about a meeting of the U.S. Nuclear Regulatory Commission to be held in Rockville, Maryland on October 31, 2012.
KW - MEETINGS
KW - U.S. Nuclear Regulatory Commission -- Congresses
KW - ROCKVILLE (Md.)
N1 - Accession Number: 82832001; Gonzalez, Hipolito 1; Affiliations: 1: Acting Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards.; Issue Info: 10/19/2012, Vol. 77 Issue 203, p64361; Thesaurus Term: MEETINGS; Subject Term: U.S. Nuclear Regulatory Commission -- Congresses; Subject: ROCKVILLE (Md.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82832001&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Simpson, Jo Ann
T1 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/19/
VL - 77
IS - 203
M3 - Article
SP - 64361
EP - 64362
SN - 00976326
AB - The article reports on a notice issued by the U.S. Nuclear Regulatory Commission regarding a draft report on waste burial charges entitled "Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities." It mentions that the same involves Changes related to waste disposal costs at low-level burial facilities. It further states that the comment submission period regarding the same has been extended till November 15, 2012.
KW - WASTE management
KW - GOVERNMENT policy
KW - PUBLIC opinion
KW - EXTENSIONS
KW - COSTS
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 82832003; Simpson, Jo Ann 1; Affiliations: 1: Acting Chief, Financial Analysis and International Projects Branch. Division of Inspection and Regional Support, Office of Nuclear Reactor Regulation.; Issue Info: 10/19/2012, Vol. 77 Issue 203, p64361; Thesaurus Term: WASTE management; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: PUBLIC opinion; Thesaurus Term: EXTENSIONS; Subject Term: COSTS; Subject Term: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 562212 Solid Waste Landfill; NAICS/Industry Codes: 562119 Other Waste Collection; NAICS/Industry Codes: 562110 Waste collection; NAICS/Industry Codes: 924110 Administration of Air and Water Resource and Solid Waste Management Programs; NAICS/Industry Codes: 562210 Waste treatment and disposal; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=82832003&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Regulatory Policies and Practices; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/22/
VL - 77
IS - 204
M3 - Article
SP - 64563
EP - 64563
SN - 00976326
AB - The article offers information on a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Regulatory Policies and Practices to be held on October 31, 2012 in Maryland organized by the U.S. Nuclear Regulatory Commission (NRC).
KW - MEETINGS
KW - MARYLAND
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83094951; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 10/22/2012, Vol. 77 Issue 204, p64563; Thesaurus Term: MEETINGS; Subject: MARYLAND ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=83094951&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Cubbage, Amy E.
T1 - Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/22/
VL - 77
IS - 204
M3 - Article
SP - 64564
EP - 64565
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding solicitation of comments on the proposed interim staff guidance (ISG). ISG entitled "Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles" supplements the guidance on the design-basis hurricane and hurricane missiles for nuclear power plants.
KW - PUBLIC opinion
KW - NUCLEAR power plants
KW - INTERIM financial statements
KW - GUIDANCE systems (Flight)
KW - HURRICANE (Fighter plane)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83094953; Cubbage, Amy E. 1; Affiliations: 1: Chief, Policy Branch, Division of Advanced Reactor and Rulemaking, Office of New Reactors; Issue Info: 10/22/2012, Vol. 77 Issue 204, p64564; Thesaurus Term: PUBLIC opinion; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: INTERIM financial statements; Subject Term: GUIDANCE systems (Flight); Subject Term: HURRICANE (Fighter plane) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 334511 Search, Detection, Navigation, Guidance, Aeronautical, and Nautical System and Instrument Manufacturing; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=83094953&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Luehman, James
T1 - Solicitation of Feedback and Lessons- Learned from the Pilot of the Revised Construction Reactor Oversight Process.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/22/
VL - 77
IS - 204
M3 - Article
SP - 64565
EP - 64566
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding solicitation of feedback from members, licensees and groups on the effectiveness of the revised construction reactor oversight process (cROP) demonstrated during the pilot program. The feedback allows external stakeholder to support the staff assessment of the pilot results.
KW - PUBLIC opinion
KW - STAKEHOLDERS
KW - PILOT projects
KW - NUCLEAR reactors
KW - LEGISLATIVE oversight
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83094954; Luehman, James 1; Affiliations: 1: Deputy Director, Division of Construction Inspection & Operational Programs, Office of New Reactors; Issue Info: 10/22/2012, Vol. 77 Issue 204, p64565; Thesaurus Term: PUBLIC opinion; Thesaurus Term: STAKEHOLDERS; Thesaurus Term: PILOT projects; Subject Term: NUCLEAR reactors; Subject Term: LEGISLATIVE oversight ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/23/
VL - 77
IS - 205
M3 - Correction notice
SP - 64834
EP - 64835
SN - 00976326
AB - A correction to the notice of exemption issued by the U.S. Nuclear Regulatory Commission (NRC) to the Exelon Generation Co. LLC for the Oyster Creek Nuclear Generating Station published on April 8, 2011 is presented.
KW - U.S. Nuclear Regulatory Commission
KW - EXELON Generation Co. LLC
N1 - Accession Number: 83095170; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.; Issue Info: 10/23/2012, Vol. 77 Issue 205, p64834 ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: EXELON Generation Co. LLC; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Correction notice
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Tran, Linh N.
T1 - Final Interim Staff Guidance Augmenting NUREG-1537, ''Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors,'' Parts 1 and 2, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/10/30/
VL - 77
IS - 210
M3 - Article
SP - 65728
EP - 65729
SN - 00976326
AB - The article offers information about a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding the issuance of a final Interim Staff Guidance (ISG) that augments certain parts of nuclear regulations such as "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Format and Content" and "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Standard Review Plan and Acceptance Criteria."
KW - GOVERNMENT policy
KW - GOVERNMENT regulation
KW - NUCLEAR power plants
KW - LICENSES
KW - NUCLEAR facilities
KW - NUCLEAR reactors -- United States
KW - GUIDELINES
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83259388; Tran, Linh N. 1; Affiliations: 1: Acting Chief, Research and Test Reactor Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation.; Issue Info: 10/30/2012, Vol. 77 Issue 210, p65728; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: GOVERNMENT regulation; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: NUCLEAR facilities; Subject Term: NUCLEAR reactors -- United States; Subject Term: GUIDELINES; Subject: UNITED States ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Digital I&C; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/13/
VL - 77
IS - 219
M3 - Article
SP - 67688
EP - 67688
SN - 00976326
AB - The article offers information about a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Digital I&C organized by the U.S. Nuclear Regulatory Commission (NRC) to be held on November 16, 2012 at Rockville in Maryland focusing on Babcock & Wilcox (B&W) mPower reactor.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83850049; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 11/13/2012, Vol. 77 Issue 219, p67688; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=83850049&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Lyon, Carl F.
T1 - Callaway Plant, Unit 1; Application for Amendment to Facility Operating License.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/14/
VL - 77
IS - 220
M3 - Article
SP - 67837
EP - 67838
SN - 00976326
AB - The article offers information about a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding the application for amendment to facility operating license for Unit 1 of the Callaway Plant, located in Callaway County, Missouri. It mentions that NRC has granted approval Union Electric Co.'s request to withdraw its application regarding the amendment to operating license.
KW - NUCLEAR power plants
KW - LICENSES
KW - MODIFICATIONS
KW - CALLAWAY County (Mo.)
KW - MISSOURI
KW - U.S. Nuclear Regulatory Commission
KW - CALLAWAY Power Plant (Fulton, Mo.)
KW - UNION Electric Co.
N1 - Accession Number: 83850147; Lyon, Carl F. 1; Affiliations: 1: Project Manager, Plant Licensing Branch IV, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 11/14/2012, Vol. 77 Issue 220, p67837; Thesaurus Term: NUCLEAR power plants; Thesaurus Term: LICENSES; Subject Term: MODIFICATIONS; Subject: CALLAWAY County (Mo.); Subject: MISSOURI ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: CALLAWAY Power Plant (Fulton, Mo.) ; Company/Entity: UNION Electric Co. DUNS Number: 004842845; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=83850147&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Regulatory Policies and Practices; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/15/
VL - 77
IS - 221
M3 - Article
SP - 68160
EP - 68160
SN - 00976326
AB - The article offers information about a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Regulatory Policies and Practices organized by the U.S. Nuclear Regulatory Commission (NRC) to be held on December 5, 2012 at Rockville in Maryland.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83850275; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 11/15/2012, Vol. 77 Issue 221, p68160; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Shukla, Girija
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Planning and Procedures; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/15/
VL - 77
IS - 221
M3 - Article
SP - 68160
EP - 68160
SN - 00976326
AB - The article offers information about a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Planning and Procedures organized by the U.S. Nuclear Regulatory Commission (NRC) to be held on December 5, 2012 at Rockville in Maryland.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83850274; Shukla, Girija 1; Affiliations: 1: Acting Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 11/15/2012, Vol. 77 Issue 221, p68160; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=83850274&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/15/
VL - 77
IS - 221
M3 - Article
SP - 68161
EP - 68161
SN - 00976326
AB - The article offers information about a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Fukushima organized by the U.S. Nuclear Regulatory Commission (NRC) to be held on December 5, 2012 at Rockville in Maryland concerning Near-Term Task Force (NTTF) report.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83850277; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 11/15/2012, Vol. 77 Issue 221, p68161; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=83850277&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Shukla, Girija
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/15/
VL - 77
IS - 221
M3 - Article
SP - 68161
EP - 68161
SN - 00976326
AB - The article offers information about a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Fukushima organized by the U.S. Nuclear Regulatory Commission (NRC) to be held on December 4, 2012 at Rockville in Maryland concerning Near-Term Task Force (NTTF) recommendation.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83850276; Shukla, Girija 1; Affiliations: 1: Acting Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards; Issue Info: 11/15/2012, Vol. 77 Issue 221, p68161; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/2p; Document Type: Article
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=buh&AN=83850276&site=ehost-live&scope=site
DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Regulatory Policies and Practices; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/15/
VL - 77
IS - 221
M3 - Article
SP - 68162
EP - 68162
SN - 00976326
AB - The article offers information about a meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Regulatory Policies and Practices organized by the U.S. Nuclear Regulatory Commission (NRC) to be held on December 3, 2012 at Rockville in Maryland.
KW - MEETINGS
KW - ROCKVILLE (Md.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83850279; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 11/15/2012, Vol. 77 Issue 221, p68162; Thesaurus Term: MEETINGS; Subject: ROCKVILLE (Md.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Stuchell, Sheldon D.
T1 - Proposed Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-535, Revision 0, ''Revise Shutdown Margin Definition To Address Advanced Fuel Designs''.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/19/
VL - 77
IS - 223
M3 - Article
SP - 69507
EP - 69508
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission (NRC) regarding solicitation of comments on the proposed model safety evaluation (SE) for plant-specific adoption of Technical Specifications (TS) Task Force (TSTF) Traveler TSTF. TSTF entitled "Revise Shutdown Margin Definition to Address Advanced Fuel Designs" applicable to boiling water reactor (BWR) power plants calculates shutdown margin (SDM) at the reactor moderator temperature for BWR fuel designs.
KW - PUBLIC opinion
KW - TASK forces
KW - EVALUATION
KW - FUEL
KW - BOILING water reactors
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 83883431; Stuchell, Sheldon D. 1; Affiliations: 1: Acting Chief, Licensing Processes Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: 11/19/2012, Vol. 77 Issue 223, p69507; Thesaurus Term: PUBLIC opinion; Thesaurus Term: TASK forces; Subject Term: EVALUATION; Subject Term: FUEL; Subject Term: BOILING water reactors ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 454319 Other fuel dealers; NAICS/Industry Codes: 454310 Fuel Dealers; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Leeds, Eric J.
T1 - Entergy Nuclear Indian Point 2, LLC; Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit No. 2, Request for Action.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2012/11/27/
VL - 77
IS - 228
M3 - Article
SP - 70847
EP - 70848
SN - 00976326
AB - The article focuses on a notice issued by the U.S. Nuclear Regulatory Commission regarding an application filed by the Natural Resources Defense Council. Petition requests for the action on Indian Point Nuclear Generating Unit Number two to remove the passive autocatalytic recombiners (PARs) due to unintended ignitions in the event of a severe accident causing a hydrogen detonation.
KW - ACCIDENT prevention
KW - PETITIONS
KW - ACOUSTIC phenomena in nature
KW - NEW York (N.Y.)
KW - U.S. Nuclear Regulatory Commission
KW - NATURAL Resources Defense Council
KW - INDIAN Point Nuclear Power Plant (N.Y.)
N1 - Accession Number: 84346188; Leeds, Eric J. 1; Affiliations: 1: Director, Office of Nuclear Reactor Regulation; Issue Info: 11/27/2012, Vol. 77 Issue 228, p70847; Thesaurus Term: ACCIDENT prevention; Subject Term: PETITIONS; Subject Term: ACOUSTIC phenomena in nature; Subject: NEW York (N.Y.) ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: NATURAL Resources Defense Council DUNS Number: 078615580 ; Company/Entity: INDIAN Point Nuclear Power Plant (N.Y.); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Yang, Y.
T1 - Spacecraft attitude determination and control: Quaternion based method
JO - Annual Reviews in Control
JF - Annual Reviews in Control
Y1 - 2012/12//
VL - 36
IS - 2
M3 - Article
SP - 198
EP - 219
SN - 13675788
AB - Abstract: In this review, we discuss in detail the quaternion based methods for spacecraft attitude determination and control. We summarize some recent developments on this research area. We start with some brief but complete discussions on the theory of quaternion which will be sufficient for the discussion in the remaining part of the review. We review the progress of quaternion based attitude determination which has been well recognized and achieved great success by using Newton’s method. We also present a different and more elegant treatment on an analytic solution to Wahba’s problem. For quaternion based control system design, we focus on some recently developed reduced quaternion models which use only vector component of the quaternion in the state space models. We discuss some new design method that has the following features: (a) it has an analytic solution of LQR, and (b) the designed system reduces disturbance effect, global stabilizes the nonlinear spacecraft system, and is robust to the modeling uncertainty. The presentation of the review is self-complete. It includes all the background information that is needed to understand the development involving the system modeling, the attitude determination, and the attitude control system design methods. [Copyright &y& Elsevier]
AB - Copyright of Annual Reviews in Control is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SPACE vehicles -- Attitude control systems
KW - QUATERNIONS
KW - SYSTEMS design
KW - NEWTON-Raphson method
KW - ANALYTICAL solutions (Mathematical analysis)
KW - NONLINEAR systems
KW - Attitude determination
KW - Control
KW - Reduced quaternion model
KW - Spacecraft
N1 - Accession Number: 83299012; Yang, Y. 1; Email Address: yaguang.yang@verizon.net; Affiliation: 1: The Office of Research, US Nuclear Regulatory Commission, 21 Church Street, Rockville, MD 20850, United States; Source Info: Dec2012, Vol. 36 Issue 2, p198; Subject Term: SPACE vehicles -- Attitude control systems; Subject Term: QUATERNIONS; Subject Term: SYSTEMS design; Subject Term: NEWTON-Raphson method; Subject Term: ANALYTICAL solutions (Mathematical analysis); Subject Term: NONLINEAR systems; Author-Supplied Keyword: Attitude determination; Author-Supplied Keyword: Control; Author-Supplied Keyword: Reduced quaternion model; Author-Supplied Keyword: Spacecraft; Number of Pages: 22p; Document Type: Article
L3 - 10.1016/j.arcontrol.2012.09.003
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Frye Jr., Roland M.1
T1 - THE UNITED STATES NUCLEAR REGULATORY COMMISSION'S USE OF SCIENTIFIC AND TECHNICAL ADVISORY COMMITTEES.
JO - Albany Law Journal of Science & Technology
JF - Albany Law Journal of Science & Technology
J1 - Albany Law Journal of Science & Technology
PY - 2013/01//
Y1 - 2013/01//
VL - 23
IS - 1
CP - 1
M3 - Article
SP - 1
EP - 54
SN - 10594280
AB - The article focuses on the precluded technical and scientific issues regarding nuclear power reactors waste and the requirement of technical advisory committees to guard such fixes for the U.S. Nuclear Regulatory Commission (NRC). It also informs about several existing advisory committees chartered for NRC including the Advisory Committee on Reactor Safeguards (ACRS), the Licensing Support Network Advisory Review Panel (LSNARP), and the Advisory Committee on Medical Use of Isotopes (ACMUI).
KW - Radioactive wastes
KW - Citizens' advisory committees in technology
KW - Nuclear reactors -- United States
KW - Citizens' advisory committees in science
KW - United States. Advisory Committee on Reactor Safeguards
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 87074265; Authors:Frye Jr., Roland M. 1; Affiliations: 1: Senior Attorney, Office of Commission Appellate Adjudication, United States Nuclear Regulatory Commission. A.B. Princeton University, J.D. Cornell Law School; Subject: U.S. Nuclear Regulatory Commission; Subject: Radioactive wastes; Subject: Citizens' advisory committees in technology; Subject: Nuclear reactors -- United States; Subject: Citizens' advisory committees in science; Subject: United States. Advisory Committee on Reactor Safeguards; Number of Pages: 54p; Statute:Atomic Energy Act of 1954; 42 U.S.C. § 2039 (2012); Jurisdiction:United States; Statute:Federal Advisory Committee Act. Pub. L. No. 92-463, 86 Stat. 770; 5 U.S.C. app. 2 § 1 (2012); Jurisdiction:United States; Record Type: Article
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DP - EBSCOhost
DB - lft
ER -
TY - GEN
AU - Magwood, William
T1 - Looking at the Long-Term Future.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2013/01//Jan/Feb2013
VL - 31
IS - 1
M3 - Interview
SP - 18
EP - 20
PB - Presidents & Prime Ministers
SN - 08922055
AB - An interview is presented with William D. Magwood, Commissioner of the U.S. Nuclear Regulatory Commission (NRC). When asked about what is the U.S. NRC's position on the impact of low-dose radiation on evacuees affected due to Fukushima Daiichi nuclear accident in Japan, Magwood said that they had no position on the matter and referred to Japanese authorities to handle the situation. He discussed about policies related to disposal of nuclear wastes in the U.S.
KW - Nuclear accidents
KW - Commissioners
KW - Fukushima Nuclear Accident, Fukushima, Japan, 2011
KW - Dose-response relationship (Radiation)
KW - Radioactive waste disposal -- Government policy
KW - U.S. Nuclear Regulatory Commission
KW - Magwood, William D. -- Interviews
N1 - Accession Number: 85952582; Magwood, William 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: Jan/Feb2013, Vol. 31 Issue 1, p18; Thesaurus Term: Nuclear accidents; Subject Term: Commissioners; Subject Term: Fukushima Nuclear Accident, Fukushima, Japan, 2011; Subject Term: Dose-response relationship (Radiation); Subject Term: Radioactive waste disposal -- Government policy ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; People: Magwood, William D. -- Interviews; Number of Pages: 3p; Document Type: Interview
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Avramova, M.
AU - Velazquez-Lozada, A.
AU - Rubin, A.
T1 - Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database.
JO - Science & Technology of Nuclear Installations
JF - Science & Technology of Nuclear Installations
Y1 - 2013/01//
M3 - Article
SP - 1
EP - 12
SN - 16876075
AB - The international OECD/NRC PSBT benchmark has been established to provide a test bed for assessing the capabilities of thermalhydraulic codes and to encourage advancement in the analysis of fluid flow in rod bundles. The benchmark was based on one of the most valuable databases identified for the thermal-hydraulics modeling developed by NUPEC, Japan. The database includes void fraction and departure from nucleate boiling measurements in a representative PWR fuel assembly. On behalf of the benchmark team, PSU in collaboration with US NRC has performed supporting calculations using the PSU in-house advanced thermalhydraulic subchannel code CTF and the US NRC system code TRACE. CTF is a version of COBRA-TF whose models have been continuously improved and validated by the RDFMG group at PSU. TRACE is a reactor systems code developed by US NRC to analyze transient and steady-state thermal-hydraulic behavior in LWRs and it has been designed to perform best-estimate analyses of LOCA, operational transients, and other accident scenarios in PWRs and BWRs.The paper presents CTF and TRACE models for the PSBT void distribution exercises. Code-to-code and code-to-data comparisons are provided along with a discussion of the void generation and void distribution models available in the two codes. [ABSTRACT FROM AUTHOR]
AB - Copyright of Science & Technology of Nuclear Installations is the property of Hindawi Publishing Corporation and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - DATABASES
KW - EBULLITION
KW - WATER -- Distribution
KW - FLUID mechanics
KW - NUCLEATE boiling
N1 - Accession Number: 95294712; Avramova, M. 1; Email Address: mna109@psu.edu Velazquez-Lozada, A. 2 Rubin, A. 1; Affiliation: 1: Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, PA 16802, USA 2: RES/DSA/CDB, US Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Source Info: 2013, p1; Subject Term: DATABASES; Subject Term: EBULLITION; Subject Term: WATER -- Distribution; Subject Term: FLUID mechanics; Subject Term: NUCLEATE boiling; NAICS/Industry Codes: 237110 Water and Sewer Line and Related Structures Construction; NAICS/Industry Codes: 221310 Water Supply and Irrigation Systems; Number of Pages: 12p; Document Type: Article
L3 - 10.1155/2013/725687
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - MILLIGAN, P.
AU - OKYAR, H. B.
T1 - Recent Recommendations on Emergency Exposure Situations and a Discussion on Setting Reference Levels with the NEA Perspective.
JO - Radioprotection (EDP Sciences)
JF - Radioprotection (EDP Sciences)
Y1 - 2013/01/02/2013 Supplement 1
VL - 48
IS - S1
M3 - Article
SP - S35
EP - S35
SN - 00338451
AB - Expert Group on Implementation of New International Recommendations for Emergency Exposure Situations (EGIRES) of the Working Party on Nuclear Emergency Matter (WPNEM) has been mandated by the Committee of Radiation Protection and Public Health (CRPPH) of the OECD Nuclear Energy Agency to investigate issues in, and approaches to, the implementation of the new ICRP recommendations and revised Basic Safety Standards of the IAEA for emergency exposure situations, specifically nuclear/radiological emergencies including accidents and consequence management for malicious acts. This also includes the application of optimisation of protection strategies, setting of reference levels and the inclusion of stakeholder input in this process. The expected output of the expert group is to prepare a report on issues covering mentioned topics. Emergency exposure situations, as defined by the ICRP, are unexpected situations that may require urgent protective actions, and perhaps longer-term protective actions to be implemented. The Commission continues to recommend optimisation and the use of reference levels to ensure an adequate degree of protection with respect to exposure to ionising radiation in emergency exposure situations. Setting reference levels is a responsibility of national authorities and reference levels represent the level of dose or risk, above which it is judged to be inappropriate to plan to allow exposures to occur and for which therefore protective actions should be planned and optimized. EGIRES decided to analyze the established processes for optimization of the protection strategy for emergency exposure situations and practical implementation of reference levels concept in several member states of the NEA by performing a survey. It is planned to collect information on the definition of optimization strategy in different countries, optimization of protection for different protective actions and also optimization of urgent protective actions. In addition, national criteria in setting reference levels, its use, relevant processes including specific triggers and dosimetric quantities in setting reference levels are focus points that will be evaluated. Benefits expected from the work of the expert group will be useful to find a path and even common understanding of surrounding issues in emergency exposure situations with the inclusion of national perspectives and also to discuss stakeholder involvement. [ABSTRACT FROM AUTHOR]
AB - Copyright of Radioprotection (EDP Sciences) is the property of EDP Sciences and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RADIATION -- Safety measures
KW - EMERGENCY management
KW - PUBLIC health
KW - STAKEHOLDERS
KW - RADIATION dosimetry
KW - RADIATION exposure
KW - CRPPH
KW - EGIRES
KW - Exposure situation
KW - reference level
KW - WPNEM
N1 - Accession Number: 88127293; MILLIGAN, P. 1 OKYAR, H. B. 2; Affiliation: 1: Office of Nuclear Security and Incident Response, MS T3B46M, U.S. Nuclear Regulatory Commission, Washington DC 20555, United States 2: Radiation Protection and Radioactive Waste Management Division, OECD Nuclear Energy Agency, Le Seine Saint-Germain, 12, boulevard des Îles, 92130 Issy-les-Moulineaux, France; Source Info: 2013 Supplement 1, Vol. 48 Issue S1, pS35; Subject Term: RADIATION -- Safety measures; Subject Term: EMERGENCY management; Subject Term: PUBLIC health; Subject Term: STAKEHOLDERS; Subject Term: RADIATION dosimetry; Subject Term: RADIATION exposure; Author-Supplied Keyword: CRPPH; Author-Supplied Keyword: EGIRES; Author-Supplied Keyword: Exposure situation; Author-Supplied Keyword: reference level; Author-Supplied Keyword: WPNEM; NAICS/Industry Codes: 912190 Other provincial protective services; NAICS/Industry Codes: 922190 Other Justice, Public Order, and Safety Activities; NAICS/Industry Codes: 913190 Other municipal protective services; NAICS/Industry Codes: 911290 Other federal protective services; NAICS/Industry Codes: 624230 Emergency and Other Relief Services; NAICS/Industry Codes: 525120 Health and Welfare Funds; NAICS/Industry Codes: 541380 Testing Laboratories; Number of Pages: 1p; Document Type: Article
L3 - 10.1051/radiopro/20139905
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Prokofiev, Iouri
AU - Cumblidge, Stephen E.
AU - Csontos, Aladar A.
AU - Braatz, Brett G.
AU - Doctor, Steven R.
T1 - New international Program to Assess the Reliability of Emerging Nondestructive Techniques (PARENT).
JO - AIP Conference Proceedings
JF - AIP Conference Proceedings
Y1 - 2013/01/24/
VL - 1511
IS - 1
M3 - Article
SP - 1097
EP - 1103
PB - American Institute of Physics
SN - 0094243X
AB - The Nuclear Regulatory Commission established the Program to Assess the Reliability of Emerging Nondestructive Techniques (PARENT) to follow on from the successful Program for the Inspection of Nickel alloy Components. The goals of PARENT are to conduct a confirmatory assessment of the reliability of nondestructive evaluation (NDE) techniques for detecting and sizing primary water stress corrosion cracks and apply the lessons learned from PINC to a series of round-robin tests. These open and blind round-robin tests will comprise a new set of typical pressure boundary components including dissimilar metal welds and bottom-mounted instrumentation penetrations. Open round-robin tests will engage research and industry teams worldwide to investigate and demonstrate the reliability of emerging NDE techniques to detect and size flaws with a wide range of lengths, depths, orientations, and locations. Blind round-robin tests will utilize various testing organizations, whose inspectors and procedures are certified by the standards for the nuclear industry in their respective countries, to investigate the ability of established NDE techniques to detect and size flaws whose characteristics range from relatively easy to very difficult for detection and sizing. Blind and open round-robin testing started in late 2011 and early 2012, respectively. This paper will present the work scope with reports on progress, NDE methods evaluated, and project timeline for PARENT. [ABSTRACT FROM AUTHOR]
AB - Copyright of AIP Conference Proceedings is the property of American Institute of Physics and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NONDESTRUCTIVE testing
KW - RELIABILITY (Engineering)
KW - STRESS corrosion cracking
KW - NICKEL alloys
KW - WELDED joints
KW - NUCLEAR industry
KW - UNITED States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 85094099; Prokofiev, Iouri 1 Cumblidge, Stephen E. 1 Csontos, Aladar A. 1 Braatz, Brett G. 2 Doctor, Steven R. 2; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, DC, 2: Pacific Northwest National Laboratory, Richland, WA 99352,; Source Info: Jan2013, Vol. 1511 Issue 1, p1097; Subject Term: NONDESTRUCTIVE testing; Subject Term: RELIABILITY (Engineering); Subject Term: STRESS corrosion cracking; Subject Term: NICKEL alloys; Subject Term: WELDED joints; Subject Term: NUCLEAR industry; Subject Term: UNITED States; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 331490 Non-ferrous metal (except copper and aluminum) rolling, drawing, extruding and alloying; NAICS/Industry Codes: 541380 Testing Laboratories; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 7p; Illustrations: 4 Charts; Document Type: Article
L3 - 10.1063/1.4789165
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Billone, M.C.
AU - Burtseva, T.A.
AU - Einziger, R.E.
T1 - Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2013/02//
VL - 433
IS - 1-3
M3 - Article
SP - 431
EP - 448
SN - 00223115
AB - Abstract: Structural analyses of dry casks containing high-burnup fuel require cladding mechanical properties and failure limits to assess fuel behavior. Pre-storage drying-transfer operations and early stage storage subject cladding to higher temperatures and much higher pressure-induced tensile hoop stresses relative to in-reactor operation and pool storage. Under these conditions, radial hydrides may precipitate during slow cooling and provide an additional embrittlement mechanism as the cladding temperature decreases below the ductile-to-brittle transition temperature (DBTT). A test procedure was developed to simulate the effects of drying-storage temperature histories. Following drying-storage simulation, samples were subjected to ring-compression test (RCT) loading, which was used as a ductility screening test and to simulate pinch-type loading that may occur during cask transport. RCT samples with <2% offset strain prior to >50% wall cracking were assessed as brittle. Prior to testing high-burnup cladding, many tests were conducted with pre-hydrided Zircaloy-4 (Zry-4) and ZIRLO™ to determine target 400°C hoop stresses for high-burnup rodlets. Zry-4 cladding segments, from a 67-GWd/MTU fuel rod, with 520–620wppm hydrogen and ZIRLO™ cladding segments from a 70-GWd/MTU fuel rod, with 350–650wppm hydrogen were defueled and tested. Following drying-storage simulation, the extent of radial-hydride precipitation was characterized by the radial-hydride continuity factor. It was found that the DBTT was dependent on: cladding material, irradiation conditions, and drying-storage histories (stress at maximum temperature). High-burnup ZIRLO™ exhibited higher susceptible to radial-hydride formation and embrittlement than high-burnup Zry-4. It was also observed that uniformly pre-hydrided, non-irradiated cladding was not a good surrogate for high-burnup cladding because of the high density of circumferential hydrides across the wall and the high metal-matrix ductility for pre-hydrided cladding. [Copyright &y& Elsevier]
AB - Copyright of Journal of Nuclear Materials is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - METALS -- Ductility
KW - TRANSITION temperature
KW - FUEL burnup (Nuclear engineering)
KW - METAL cladding
KW - STRUCTURAL analysis (Engineering)
KW - METALS -- Mechanical properties
KW - TENSILE strength
N1 - Accession Number: 85398598; Billone, M.C. 1; Email Address: billone@anl.gov Burtseva, T.A. 1 Einziger, R.E. 2; Email Address: Robert.Einziger@nrc.gov; Affiliation: 1: Nuclear Engineering Division, Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439, United States 2: Division of Spent Fuel Storage and Transportation, US Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, MD 20852, United States; Source Info: Feb2013, Vol. 433 Issue 1-3, p431; Subject Term: METALS -- Ductility; Subject Term: TRANSITION temperature; Subject Term: FUEL burnup (Nuclear engineering); Subject Term: METAL cladding; Subject Term: STRUCTURAL analysis (Engineering); Subject Term: METALS -- Mechanical properties; Subject Term: TENSILE strength; Number of Pages: 18p; Document Type: Article
L3 - 10.1016/j.jnucmat.2012.10.002
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Evans, Michele G.
T1 - Biweekly Notice, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/02/19/
VL - 78
IS - 33
M3 - Article
SP - 11688
EP - 11699
SN - 00976326
AB - The article presents a biweekly notice issued by the U.S. Nuclear Regulatory Commission (NRC) and published in the Federal Register on February 19, 2013 for applications and amendments to facility operating licenses and combined licenses involving no significant hazards considerations. The notice was published pursuant to the Atomic Energy Act of 1954. The last biweekly notice was published on February 5, 2013.
KW - LICENSES
KW - NUCLEAR energy -- Law & legislation
KW - HAZARDS
KW - U.S. Nuclear Regulatory Commission
KW - FEDERAL Register (Periodical)
N1 - Accession Number: 86932456; Evans, Michele G. 1; Affiliations: 1: Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 2/19/2013, Vol. 78 Issue 33, p11688; Thesaurus Term: LICENSES; Subject Term: NUCLEAR energy -- Law & legislation; Subject Term: HAZARDS ; Company/Entity: U.S. Nuclear Regulatory Commission; Reviews & Products: FEDERAL Register (Periodical); NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 12p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Lubinski, John W.
T1 - Tennessee Valley Authority; Notice of Receipt and Availability of Application for Renewal of Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 for an Additional 20-Year Period.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/02/22/
VL - 78
IS - 36
M3 - Article
SP - 12365
EP - 12365
SN - 00976326
AB - The article presents a notice from the U.S. Nuclear Regulatory Commission (NRC) regarding an application filed on January 7, 2013 by the Tennessee Valley Authority to renew the operating licenses for Units 1 and 2 of the Sequoyah Nuclear Plant.
KW - LICENSES
KW - NUCLEAR power plants
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 86933533; Lubinski, John W. 1; Affiliations: 1: Director, Division of License Renewal, Office of Nuclear Reactor Regulation; Issue Info: 2/22/2013, Vol. 78 Issue 36, p12365; Thesaurus Term: LICENSES; Thesaurus Term: NUCLEAR power plants ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 1/3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee On Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Radiation Protection and Nuclear Materials; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/03/25/
VL - 78
IS - 57
M3 - Article
SP - 17944
EP - 17945
SN - 00976326
AB - This article presents a notice of a meeting of the U.S. Advisory Committee on Reactor Safeguards' Subcommittee on Radiation Protection and Nuclear Materials to be held in Rockville, Maryland on April 9, 2013.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards
N1 - Accession Number: 86876969; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 3/25/2013, Vol. 78 Issue 57, p17944; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Santos, Cayetano
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Planning and Procedures; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/03/25/
VL - 78
IS - 57
M3 - Article
SP - 17944
EP - 17944
SN - 00976326
AB - This article presents a notice of a meeting of the U.S. Advisory Committee on Reactor Safeguards' Subcommittee on Planning and Procedures.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards
N1 - Accession Number: 86876968; Santos, Cayetano 1; Affiliations: 1: Chief, Reactor Safety Branch, Advisory Committee on Reactor Safeguards; Issue Info: 3/25/2013, Vol. 78 Issue 57, p17944; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards; Number of Pages: 1/3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Fukushima; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/03/25/
VL - 78
IS - 57
M3 - Article
SP - 17945
EP - 17945
SN - 00976326
AB - This article presents a notice of a meeting of the U.S. Advisory Committee on Reactor Safeguards' Subcommittee on Fukushima to be held in Rockville, Maryland on April 10, 2013.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards
N1 - Accession Number: 86876970; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 3/25/2013, Vol. 78 Issue 57, p17945; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards; Number of Pages: 1/2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Dias, Antonio
T1 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Future Plant Designs; Notice of Meeting.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/03/25/
VL - 78
IS - 57
M3 - Article
SP - 17945
EP - 17946
SN - 00976326
AB - This article presents a notice of a meeting of the U.S. Advisory Committee on Reactor Safeguards' Subcommittee on Future Plant Designs to be held in Rockville, Maryland on April 9, 2013.
KW - MEETINGS
KW - UNITED States. Advisory Committee on Reactor Safeguards
N1 - Accession Number: 86876971; Dias, Antonio 1; Affiliations: 1: Technical Advisor, Advisory Committee on Reactor Safeguards; Issue Info: 3/25/2013, Vol. 78 Issue 57, p17945; Thesaurus Term: MEETINGS; Subject Term: UNITED States. Advisory Committee on Reactor Safeguards; Number of Pages: 2p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Frye, Roland M.1,2,3
T1 - USE OF EXPERT ELICITATION AT THE U.S. NUCLEAR REGULATORY COMMISSION.
JO - Albany Law Journal of Science & Technology
JF - Albany Law Journal of Science & Technology
J1 - Albany Law Journal of Science & Technology
PY - 2013/04//
Y1 - 2013/04//
VL - 23
IS - 2
CP - 2
M3 - Article
SP - 309
EP - 382
SN - 10594280
AB - The article focuses on the use of the expert elicitation process by the U.S. Nuclear Regulatory Commission. It discusses the history of expert elicitation process at the Commission since 1996 and mentions that it is a formal and well-documented process for obtaining the judgments of multiple experts. It provides recommendations for making the best use of this process in the future.
KW - Judgments (Law)
KW - Evocation
KW - Specialists
KW - Law -- United States
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 88004047; Authors:Frye, Roland M. 1,2,3; Affiliations: 1: Senior Attorney, Office of Commission Appellate Adjudication, United States Nuclear Regulatory Commission (NRC); 2: A.B. Princeton University; 3: J.D. Cornell Law School; Subject: Evocation; Subject: U.S. Nuclear Regulatory Commission; Subject: Judgments (Law); Subject: Specialists; Subject: Law -- United States; Number of Pages: 74p; Record Type: Article
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DP - EBSCOhost
DB - lft
ER -
TY - JOUR
AU - Kokajko, Lawrence E.
T1 - SHINE Medical Technologies, Inc.; Exemption.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/04//
VL - 78
IS - 62
M3 - Article
SP - 19537
EP - 19539
SN - 00976326
AB - The article offers information on Shine Medical Technologies Inc. that has deposited an application for constructing a medical isotope production faculty and producing molybdenum-99 (Mo-99). It explains that the company has to be taken permission from the U.S. Nuclear Regulatory Commission (NRC). It further informs that Shine wants to construct its production faculty in Rock County, Wisconsin.
KW - MOLYBDENUM
KW - ISOTOPES
KW - BUILDING
KW - ROCK County (Wis.)
KW - SHINE Medical Technologies Inc.
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 86972789; Kokajko, Lawrence E. 1; Affiliations: 1: Director, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation; Issue Info: Apr2013, Vol. 78 Issue 62, p19537; Subject Term: MOLYBDENUM; Subject Term: ISOTOPES; Subject Term: BUILDING; Subject: ROCK County (Wis.) ; Company/Entity: SHINE Medical Technologies Inc. ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 212299 All Other Metal Ore Mining; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - CONF
AU - Feintuch, Karl D.
T1 - Dominion Energy Kewaunee, Inc., Kewaunee Power Station Post- Shutdown Decommissioning Activities Report.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/04//
VL - 78
IS - 62
M3 - Proceeding
SP - 19540
EP - 19540
SN - 00976326
AB - The article offers information on a meeting to be conducted by the U.S. Nuclear Regulatory Commission (NRC) on April 24, 2013 in Kewaunee County, Wisconsin.
KW - MEETINGS
KW - KEWAUNEE County (Wis.)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 86972790; Feintuch, Karl D. 1; Affiliations: 1: Acting Chief, Plant Licensing Branch III-1, Division of Operator Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: Apr2013, Vol. 78 Issue 62, p19540; Thesaurus Term: MEETINGS; Subject: KEWAUNEE County (Wis.) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3/5p; Document Type: Proceeding
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
AU - Bensi, Michelle
AU - Kiureghian, Armen Der
AU - Straub, Daniel
T1 - Efficient Bayesian network modeling of systems
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2013/04//
VL - 112
M3 - Article
SP - 200
EP - 213
SN - 09518320
AB - Abstract: The Bayesian network (BN) is a convenient tool for probabilistic modeling of system performance, particularly when it is of interest to update the reliability of the system or its components in light of observed information. In this paper, BN structures for modeling the performance of systems that are defined in terms of their minimum link or cut sets are investigated. Standard BN structures that define the system node as a child of its constituent components or its minimum link/cut sets lead to converging structures, which are computationally disadvantageous and could severely hamper application of the BN to real systems. A systematic approach to defining an alternative formulation is developed that creates chain-like BN structures that are orders of magnitude more efficient, particularly in terms of computational memory demand. The formulation uses an integer optimization algorithm to identify the most efficient BN structure. Example applications demonstrate the proposed methodology and quantify the gained computational advantage. [Copyright &y& Elsevier]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - BAYESIAN analysis
KW - COMPUTER networks
KW - COMPUTER systems
KW - PROBABILITY theory
KW - PERFORMANCE evaluation
KW - RELIABILITY (Engineering)
KW - INFORMATION theory
KW - Bayesian network
KW - Integer optimization
KW - Max-flow min-cut theorem
KW - Minimum cut sets
KW - Minimum link sets
KW - Parallel systems
KW - Series systems
KW - Systems
N1 - Accession Number: 85279683; Bensi, Michelle 1; Email Address: michelle.bensi@nrc.gov Kiureghian, Armen Der 2 Straub, Daniel 3; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, USA 2: Department of Civil and Environmental Engineering, University of California, Berkeley, CA 94720, USA 3: Engineering Risk Analysis Group, Technische Universität München, Munich, Germany; Source Info: Apr2013, Vol. 112, p200; Subject Term: BAYESIAN analysis; Subject Term: COMPUTER networks; Subject Term: COMPUTER systems; Subject Term: PROBABILITY theory; Subject Term: PERFORMANCE evaluation; Subject Term: RELIABILITY (Engineering); Subject Term: INFORMATION theory; Author-Supplied Keyword: Bayesian network; Author-Supplied Keyword: Integer optimization; Author-Supplied Keyword: Max-flow min-cut theorem; Author-Supplied Keyword: Minimum cut sets; Author-Supplied Keyword: Minimum link sets; Author-Supplied Keyword: Parallel systems; Author-Supplied Keyword: Series systems; Author-Supplied Keyword: Systems; NAICS/Industry Codes: 541512 Computer Systems Design Services; NAICS/Industry Codes: 541514 Computer systems design and related services (except video game design and development); Number of Pages: 14p; Document Type: Article
L3 - 10.1016/j.ress.2012.11.017
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Monninger, John D.
T1 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations.
JO - Federal Register (National Archives & Records Service, Office of the Federal Register)
JF - Federal Register (National Archives & Records Service, Office of the Federal Register)
Y1 - 2013/04/02/
VL - 78
IS - 63
M3 - Article
SP - 19746
EP - 19757
SN - 00976326
AB - The article offers information on a public notice issued by the U.S. Nuclear Regulatory Commission. It discusses various applications and amendments made for the Facility Operating Licenses and Combined Licenses involving workplace hazards regulations under the U.S. Atomic Energy Act of 1954. It informs that the all the amendments are available on online information resources of the agency.
KW - GOVERNMENT policy
KW - INFORMATION resources
KW - NUCLEAR facilities
KW - NUCLEAR facilities -- Safety measures
KW - NUCLEAR energy -- Law & legislation
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 86972905; Monninger, John D. 1; Affiliations: 1: Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation; Issue Info: 4/2/2013, Vol. 78 Issue 63, p19746; Thesaurus Term: GOVERNMENT policy; Thesaurus Term: INFORMATION resources; Subject Term: NUCLEAR facilities; Subject Term: NUCLEAR facilities -- Safety measures; Subject Term: NUCLEAR energy -- Law & legislation ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 12p; Document Type: Article
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DP - EBSCOhost
DB - buh
ER -
TY - JOUR
ID - 104175604
T1 - Full Story Not Conveyed By Stat.
AU - McIntyre, David
Y1 - 2013/06//Jun/Jul2013
N1 - Accession Number: 104175604. Language: English. Entry Date: 20130611. Revision Date: 20150711. Publication Type: Journal Article; letter. Journal Subset: Allied Health; USA. Special Interest: Diagnostic Imaging.
KW - Radiation Safety
KW - Hospitals
KW - Government Regulations
KW - United States
SP - 6
EP - 6
JO - ASRT Scanner
JF - ASRT Scanner
JA - ASRT SCANNER
VL - 45
IS - 5
CY - Alburquerque, New Mexico
PB - American Society of Radiologic Technologists
SN - 0161-3863
AD - Public Affairs Officer U.S. Nuclear Regulatory Commission
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DP - EBSCOhost
DB - rzh
ER -
TY - JOUR
AU - Burbank, Malcolm
AU - Weaver, Thomas
AU - Lewis, Ryan
AU - Williams, Thomas
AU - Williams, Barbara
AU - Crawford, Ronald
T1 - Geotechnical Tests of Sands Following Bioinduced Calcite Precipitation Catalyzed by Indigenous Bacteria.
JO - Journal of Geotechnical & Geoenvironmental Engineering
JF - Journal of Geotechnical & Geoenvironmental Engineering
Y1 - 2013/06//
VL - 139
IS - 6
M3 - Article
SP - 928
EP - 936
SN - 10900241
AB - The article reports on geotechnical testing to measure changes in sand properties after calcite precipitation was induced using indigenous bacteria as the catalyst. The research methods include cyclic triaxial sheer tests and microcosm experiment with cone-penetration testing. The test results show calcite precipitation changes geotechnical soil properties and also show the cyclic resistance ratio increases significantly with moderate amounts of calcite precipitation.
KW - RESEARCH
KW - Soil research
KW - Bacteria
KW - Soil liquefaction
KW - Engineering
KW - Soil stabilization
KW - Soil microbiology
KW - Soil liquefaction
KW - Calcite
KW - Bacteria -- Environmental aspects
KW - Seismology
KW - Microbiologists
KW - Engineering geology
KW - Biological processes
KW - Cement
KW - Cementation
KW - Earthquake
KW - Liquefaction
KW - Soil improvement
KW - Stabilization
N1 - Accession Number: 87584858; Burbank, Malcolm; Weaver, Thomas 1; Lewis, Ryan 2; Williams, Thomas 3; Williams, Barbara 4; Crawford, Ronald 5; Affiliations: 1: Geotechnical Engineer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 (corresponding author). E-mail:; 2: Geotechnical Engineer, Coeur d'Alene, ID 83815. E-mail:; 3: Assistant Dean and Director of Research Facilities, College of Sciences, Univ. of Idaho, Moscow, ID 83844. E-mail:; 4: Associate Professor, Dept. of Biological and Agricultural Engineering, Univ. of Idaho, Moscow, ID 83844. E-mail:; 5: Professor Emeritus, Univ. of Idaho, Moscow, ID 83844. E-mail:; Issue Info: Jun2013, Vol. 139 Issue 6, p928; Thesaurus Term: RESEARCH; Thesaurus Term: Soil research; Thesaurus Term: Bacteria; Thesaurus Term: Soil liquefaction; Thesaurus Term: Engineering; Thesaurus Term: Soil stabilization; Thesaurus Term: Soil microbiology; Subject Term: Soil liquefaction; Subject Term: Calcite; Subject Term: Bacteria -- Environmental aspects; Subject Term: Seismology; Subject Term: Microbiologists; Subject Term: Engineering geology; Author-Supplied Keyword: Biological processes; Author-Supplied Keyword: Cement; Author-Supplied Keyword: Cementation; Author-Supplied Keyword: Earthquake; Author-Supplied Keyword: Liquefaction; Author-Supplied Keyword: Soil improvement; Author-Supplied Keyword: Stabilization; NAICS/Industry Codes: 212398 All other non-metallic mineral mining and quarrying; NAICS/Industry Codes: 212399 All Other Nonmetallic Mineral Mining; Number of Pages: 9p; Illustrations: 1 Black and White Photograph, 2 Charts, 7 Graphs; Document Type: Article
L3 - 10.1061/(ASCE)GT.1943-5606.0000781
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Mohanty, Subhasish
AU - Majumdar, Saurindranath
AU - Srinivasan, Makuteswara
T1 - Constitutive modeling and finite element procedure development for stress analysis of prismatic high temperature gas cooled reactor graphite core components.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2013/07//
VL - 260
M3 - Article
SP - 145
EP - 154
SN - 00295493
AB - Highlights: [•] Finite element procedure developed for stress analysis of HTGR graphite component. [•] Realistic fluence profile and reflector brick shape considered for the simulation. [•] Also realistic H-451 grade material properties considered for simulation. [•] Typical outer reflector of a GT-MHR type reactor considered for numerical study. [•] Based on the simulation results replacement of graphite bricks can be scheduled. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - FINITE element method
KW - STRAINS & stresses (Mechanics)
KW - HIGH temperatures
KW - GAS cooled reactors
KW - GRAPHITE
KW - SIMULATION methods & models
N1 - Accession Number: 89218641; Mohanty, Subhasish 1; Email Address: smohanty@anl.gov Majumdar, Saurindranath 1 Srinivasan, Makuteswara 2; Affiliation: 1: Argonne National Laboratory, South Cass Avenue, Argonne, IL 60439, United States 2: U.S. Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Jul2013, Vol. 260, p145; Subject Term: FINITE element method; Subject Term: STRAINS & stresses (Mechanics); Subject Term: HIGH temperatures; Subject Term: GAS cooled reactors; Subject Term: GRAPHITE; Subject Term: SIMULATION methods & models; NAICS/Industry Codes: 327990 All other non-metallic mineral product manufacturing; NAICS/Industry Codes: 212399 All Other Nonmetallic Mineral Mining; NAICS/Industry Codes: 212398 All other non-metallic mineral mining and quarrying; NAICS/Industry Codes: 327992 Ground or Treated Mineral and Earth Manufacturing; Number of Pages: 10p; Document Type: Article
L3 - 10.1016/j.nucengdes.2013.03.003
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Kim, Seungjin
AU - Yadav, Mohan S.
AU - Talley, Justin D.
AU - Ireland, Andrew
AU - Bajorek, Stephen M.
T1 - Separate effects experiments for air-ingress in helium filled vessel.
JO - Experimental Thermal & Fluid Science
JF - Experimental Thermal & Fluid Science
Y1 - 2013/09//
VL - 49
M3 - Article
SP - 1
EP - 13
SN - 08941777
AB - Highlights: [•] Separate effects experiments on gravity-driven air-ingress in helium filled vessel. [•] Effect of pipe-breaks’ geometric parameters on air-ingress is investigated. [•] Gravity-driven air-ingress demonstrates three characteristic stages. [•] A unique non-dimensional density ratio characterizes the transition between stages. [•] Predictive models are developed for gravity-driven exchange between air and helium. [ABSTRACT FROM AUTHOR]
AB - Copyright of Experimental Thermal & Fluid Science is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - HELIUM
KW - GRAVITY
KW - SEPARATION (Technology)
KW - FLUID dynamics
KW - FLUID mechanics
KW - PIPE
KW - Air-ingress
KW - Gravity-driven flows
N1 - Accession Number: 89295614; Kim, Seungjin 1 Yadav, Mohan S. 1; Email Address: mohan@psu.edu Talley, Justin D. 1 Ireland, Andrew 2 Bajorek, Stephen M. 2; Affiliation: 1: Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, 31 Hammond Building, University Park, PA 16802, United States 2: The United States Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Sep2013, Vol. 49, p1; Subject Term: HELIUM; Subject Term: GRAVITY; Subject Term: SEPARATION (Technology); Subject Term: FLUID dynamics; Subject Term: FLUID mechanics; Subject Term: PIPE; Author-Supplied Keyword: Air-ingress; Author-Supplied Keyword: Gravity-driven flows; NAICS/Industry Codes: 325120 Industrial Gas Manufacturing; NAICS/Industry Codes: 331210 Iron and Steel Pipe and Tube Manufacturing from Purchased Steel; NAICS/Industry Codes: 326122 Plastics Pipe and Pipe Fitting Manufacturing; Number of Pages: 13p; Document Type: Article
L3 - 10.1016/j.expthermflusci.2013.02.022
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Wang, Hong
AU - Wang, Jy-An John
AU - Tan, Ting
AU - Jiang, Hao
AU - Cox, Thomas S.
AU - Howard, Rob L.
AU - Bevard, Bruce B.
AU - Flanagan, Michelle
T1 - Development of U-frame bending system for studying the vibration integrity of spent nuclear fuel.
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2013/09//
VL - 440
IS - 1-3
M3 - Article
SP - 201
EP - 213
SN - 00223115
AB - Abstract: A bending fatigue system developed to evaluate the response of spent nuclear fuel rods to vibration loads is presented. A U-frame testing setup is used for imposing bending loads on the fuel rod specimen. The U-frame setup consists of two rigid arms, side connecting plates to the rigid arms, and linkages to a universal testing machine. The test specimen’s curvature is obtained through a three-point deflection measurement method. The tests using surrogate specimens with stainless steel cladding revealed increased flexural rigidity under unidirectional cyclic bending, significant effect of cladding-pellets bonding on the response of surrogate rods, and substantial cyclic softening in reverse bending mode. These phenomena may cast light on the expected response of a spent nuclear fuel rod. The developed U-frame system is thus verified and demonstrated to be ready for further pursuit in hot-cell tests. [Copyright &y& Elsevier]
AB - Copyright of Journal of Nuclear Materials is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - BENDING (Metalwork)
KW - VIBRATION (Mechanics)
KW - NUCLEAR fuels
KW - NUCLEAR fuel rods
KW - METALS -- Fatigue
KW - METAL cladding
KW - STAINLESS steel
N1 - Accession Number: 89351573; Wang, Hong 1 Wang, Jy-An John 1; Email Address: wangja@ornl.gov Tan, Ting 1 Jiang, Hao 1 Cox, Thomas S. 1 Howard, Rob L. 2 Bevard, Bruce B. 2 Flanagan, Michelle 3; Affiliation: 1: Materials Science and Technology Division, Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831, United States 2: Reactor and Nuclear Systems Division, Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831, United States 3: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Sep2013, Vol. 440 Issue 1-3, p201; Subject Term: BENDING (Metalwork); Subject Term: VIBRATION (Mechanics); Subject Term: NUCLEAR fuels; Subject Term: NUCLEAR fuel rods; Subject Term: METALS -- Fatigue; Subject Term: METAL cladding; Subject Term: STAINLESS steel; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 331110 Iron and Steel Mills and Ferroalloy Manufacturing; Number of Pages: 13p; Document Type: Article
L3 - 10.1016/j.jnucmat.2013.05.009
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=89351573&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Kerr, M.
AU - Hill, M. R.
AU - Olson, M. D.
T1 - Study of Residual Stresses in Compact Tension Specimens Fabricated from Weld Metal.
JO - Corrosion
JF - Corrosion
Y1 - 2013/10//
VL - 69
IS - 10
M3 - Article
SP - 975
EP - 985
SN - 00109312
AB - This paper describes a preliminary investigation into the residual stress levels in welded nickel alloy compact tension specimens used in stress corrosion cracking (SCC) growth rate experiments. Results from this work document the effect of specimen size and location on residual stress profiles. The methodology outlined in this paper is appropriate to determine the degree to which residual stresses affect crack growth measurements made in coupons containing welds. Slitting method residual stress measurements and finite element weld simulation have been conducted to evaluate both the residual stress intensity factor and residual stress profiles for two compact tension coupon blanks containing welds. The two compact tension coupon blanks were used and are similar to coupons used in on-going SCC studies in weld metal. The experimental data and finite element results are in reasonable agreement, showing similar trends in calculated residual stress profiles. [ABSTRACT FROM AUTHOR]
AB - Copyright of Corrosion is the property of NACE International and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RESEARCH
KW - Residual stresses
KW - Strains & stresses (Mechanics)
KW - Stress corrosion cracking
KW - Stress corrosion
KW - Fracture mechanics
KW - compact tension
KW - finite element weld simulation
KW - residual stress
KW - residual stress intensity factor
KW - slitting
KW - stress corrosion cracking
N1 - Accession Number: 90669039; Kerr, M. 1,2; Email Address: kerr.contractor@unnpp.gov; Hill, M. R. 3; Olson, M. D. 4; Affiliations: 1: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC; 2: Knolls Atomic Power Laboratory, Schenectady, NY; 3: Hill Engineering, LLC Rancho Cordova, CA; 4: University of California-Davis, Davis, CA; Issue Info: Oct2013, Vol. 69 Issue 10, p975; Thesaurus Term: RESEARCH; Subject Term: Residual stresses; Subject Term: Strains & stresses (Mechanics); Subject Term: Stress corrosion cracking; Subject Term: Stress corrosion; Subject Term: Fracture mechanics; Author-Supplied Keyword: compact tension; Author-Supplied Keyword: finite element weld simulation; Author-Supplied Keyword: residual stress; Author-Supplied Keyword: residual stress intensity factor; Author-Supplied Keyword: slitting; Author-Supplied Keyword: stress corrosion cracking; Number of Pages: 11p; Document Type: Article
L3 - 10.5006/0832
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=90669039&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Wang, Dean
AU - Mahaffy, John H.
AU - Staudenmeier, Joseph
AU - Thurston, Carl G.
T1 - Implementation and assessment of high-resolution numerical methods in TRACE.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2013/10//
VL - 263
M3 - Article
SP - 327
EP - 341
SN - 00295493
AB - Highlights: [•] Study and implement high-resolution numerical methods for two-phase flow. [•] They can achieve better numerical accuracy than the 1st-order upwind scheme. [•] They are of great numerical robustness and efficiency. [•] Great application for BWR stability analysis and boron injection. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - TWO-phase flow
KW - MATHEMATICAL models
KW - NUMERICAL analysis
KW - NUCLEAR reactors -- Software
KW - ROBUST control
KW - BOILING water reactors
KW - NUCLEAR reactors -- Stability
N1 - Accession Number: 89899035; Wang, Dean 1; Email Address: wangda@ornl.gov Mahaffy, John H. 2 Staudenmeier, Joseph 2 Thurston, Carl G. 2; Affiliation: 1: Oak Ridge National Laboratory, 1 Bethel Valley RD #6167, Oak Ridge, TN 37831, USA 2: U.S. Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Oct2013, Vol. 263, p327; Subject Term: TWO-phase flow; Subject Term: MATHEMATICAL models; Subject Term: NUMERICAL analysis; Subject Term: NUCLEAR reactors -- Software; Subject Term: ROBUST control; Subject Term: BOILING water reactors; Subject Term: NUCLEAR reactors -- Stability; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 15p; Document Type: Article
L3 - 10.1016/j.nucengdes.2013.05.015
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=89899035&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Powers, D.A.
AU - Lee, R.Y.
AU - Salay, M.A.
T1 - Applications of results from the Phébus-FP programme in the US regulatory process.
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
Y1 - 2013/11//
VL - 61
M3 - Article
SP - 225
EP - 229
SN - 03064549
AB - Highlights: [•] Phébus-FP test results are being used in the U.S. regulatory process. [•] Core degradation is predicted to taken longer. [•] Cesium is predicted to be in a less volatile chemical form. [•] Larger molybdenum and tellurium releases are predicted now. [•] The chemical form of iodine is an issue requiring further resolution. [ABSTRACT FROM AUTHOR]
AB - Copyright of Annals of Nuclear Energy is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Cesium
KW - Molybdenum
KW - Tellurium
KW - Iodine
KW - Fission products
KW - Accident source term
KW - Reactor regulation
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 90214027; Powers, D.A. 1; Email Address: dapower@sandia.gov; Lee, R.Y. 2; Salay, M.A. 2; Affiliations: 1: Advisory Committee on Reactor Safeguards, Washington, DC 20555-0001, United States; 2: US Nuclear Regulatory Commission, Washington, DC 20555-0001, United States; Issue Info: Nov2013, Vol. 61, p225; Thesaurus Term: Cesium; Thesaurus Term: Molybdenum; Thesaurus Term: Tellurium; Thesaurus Term: Iodine; Subject Term: Fission products; Author-Supplied Keyword: Accident source term; Author-Supplied Keyword: Reactor regulation ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 212299 All Other Metal Ore Mining; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 5p; Document Type: Article
L3 - 10.1016/j.anucene.2013.03.025
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=90214027&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Miller, D.J.
AU - Cheung, F.B.
AU - Bajorek, S.M.
T1 - On the development of a grid-enhanced single-phase convective heat transfer correlation.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2013/11//
VL - 264
M3 - Article
SP - 56
EP - 60
SN - 00295493
AB - Abstract: A new single-phase convective heat transfer augmentation correlation has been developed using single phase steam cooling experimental data obtained from the Penn State/NRC Rod Bundle Heat Transfer (RBHT) facility. New findings of physical significance have been identified in evaluating the RBHT steam cooling data. The results clearly indicate that the grid-enhanced heat transfer depends not only on the grid blockage ratio but also on the flow Reynolds number. The latter is found to have a strong effect on the process of flow restructuring. Existing correlations currently employed in transient analysis codes, though accounted for the effect of grid blockage ratio, did not include the Reynolds number effect. The new correlation developed in the present study which adequately accounts for the effect of Reynolds number on the maximum heat transfer augmentation at the grid and the rate of decay of the grid-enhanced heat transfer in the downstream locations correctly captures the physics of flow restructuring as the flow passes through a spacer grid. The present work represents the first attempt to quantitatively account for the dependence of the grid-enhanced heat transfer on the flow Reynolds number that had not been considered in previous studies. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - COMPUTATIONAL grids (Computer systems)
KW - SINGLE-phase flow
KW - HEAT -- Convection
KW - HEAT transfer
KW - DATA analysis
KW - TRANSIENT analysis
N1 - Accession Number: 90434736; Miller, D.J. 1 Cheung, F.B. 1; Email Address: fxc4@psu.edu Bajorek, S.M. 2; Affiliation: 1: Department of Mechanical & Nuclear Engineering, Pennsylvania State University, University Park, PA 16802, United States 2: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Nov2013, Vol. 264, p56; Subject Term: COMPUTATIONAL grids (Computer systems); Subject Term: SINGLE-phase flow; Subject Term: HEAT -- Convection; Subject Term: HEAT transfer; Subject Term: DATA analysis; Subject Term: TRANSIENT analysis; Number of Pages: 5p; Document Type: Article
L3 - 10.1016/j.nucengdes.2012.11.023
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=90434736&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Talley, Justin D.
AU - Worosz, Ted
AU - Kim, Seungjin
AU - Bajorek, Stephen M.
AU - Tien, Kirk
T1 - Effect of bubble interactions on the prediction of interfacial area in TRACE.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2013/11//
VL - 264
M3 - Article
SP - 135
EP - 145
SN - 00295493
AB - Abstract: The conventional thermal-hydraulic nuclear reactor system analysis codes utilize a two-field, two-fluid formulation for two-phase flows. To provide closure, static flow regime transition criteria and algebraic relations are employed to estimate the interfacial area concentration (a i ). To better reflect the dynamic evolution of two-phase flow, an experimental version of TRACE is developed to estimate the a i using the one-group interfacial area transport equation (IATE), which includes mechanistic models for bubble coalescence and disintegration. These models account for: (1) bubble break-up due to impact of a turbulent eddy, (2) bubble coalescence due to random collision driven by turbulent eddies, and (3) bubble coalescence due to the acceleration of a bubble in the wake region of a preceding bubble. To assess the impact of including bubble interaction models in TRACE, code predictions of experimental data measured by a multi-sensor conductivity probe are compared to both the IATE and flow regime based predictions. In total, 50 air–water vertical co-current upward and downward bubbly flow conditions in pipes with diameters ranging from 2.54 to 20.32cm are evaluated. It is found that TRACE, using the conventional flow regime relation, always underestimates a i by predicting a larger bubble size than observed in the experimental data. Additionally, the axial trend of the a i prediction is always linear because a i in the conventional code is predominantly determined by the pressure. However, TRACE with the one-group IATE significantly improves the prediction results, yielding a ±13.0% difference with the data. It is found that the non-linear developments observed in the experimental data, which reflect bubble interactions, are predicted well using the IATE. Moreover, in several conditions dominated by bubble interactions, the a i trend displayed is opposite to the effect of pressure. In these cases, the conventional TRACE relation predicts an incorrect trend in a i , while the IATE predicts the experimental data well. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - HYDRAULICS
KW - NUCLEAR reactors
KW - ESTIMATION theory
KW - COLLISIONS (Nuclear physics)
KW - NONLINEAR analysis
N1 - Accession Number: 90434746; Talley, Justin D. 1 Worosz, Ted 1 Kim, Seungjin 1; Email Address: skim@psu.edu Bajorek, Stephen M. 2 Tien, Kirk 2; Affiliation: 1: Mechanical and Nuclear Engineering Department, The Pennsylvania State University, University Park, PA 16802, United States 2: The United States Nuclear Regulatory Commission, Two White Flint North, 11545 Rockville Pike, Rockville, MD 20852, United States; Source Info: Nov2013, Vol. 264, p135; Subject Term: HYDRAULICS; Subject Term: NUCLEAR reactors; Subject Term: ESTIMATION theory; Subject Term: COLLISIONS (Nuclear physics); Subject Term: NONLINEAR analysis; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.nucengdes.2013.02.012
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=90434746&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Pabalan, R. T.
AU - Alexander, G. W.
AU - Waiting, D. J.
AU - Barr, C. S.
T1 - Experimental Study of Contaminant Release from Reducing Grout.
JO - EPJ Web of Conferences
JF - EPJ Web of Conferences
Y1 - 2013/12/08/
IS - 56
M3 - Article
SP - 1
EP - 9
SN - 2100014X
AB - A column experiment was conducted to study the release behavior of technetium, uranium, and selenium initially sequestered in reducing grout similar in composition to Savannah River Site (SRS) saltstone, a cementitious waste form made by mixing salt solution from SRS liquid waste storage tanks with a dry mix containing blast furnace slag, fly ash, and Portland cement. The data suggest that uranium was retained in the grout possibly as a CaUO4 phase, whereas most of the selenium was released. Technetium release initially was relatively constant, and then increased significantly after 26 pore volumes. The increase in technetium release was slightly delayed relative to the observed Eh increase. The system Eh-pH started under conditions in which technetium solubility is low, constrained by Tc3O4 solubility, but eventually transitioned into the stability field of the pertechnetate ion. The delay in technetium release relative to the Eh increase was possibly due to slow oxidation of technetium at depth within the grout particles, which in turn was likely controlled by O2 diffusion into the particles. In contrast to technetium and uranium, selenium release was not solubility limited and selenium likely was present in the pore solution initially as a HSe- species. [ABSTRACT FROM AUTHOR]
AB - Copyright of EPJ Web of Conferences is the property of EDP Sciences and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - GROUT (Mortar)
KW - RESEARCH
KW - POLLUTANTS -- Research
KW - SLAG
KW - FLY ash
KW - PORTLAND cement
KW - HYDROGEN-ion concentration
KW - SOLUBILITY
KW - SAVANNAH River Site (S.C.)
N1 - Accession Number: 90226723; Pabalan, R. T. 1 Alexander, G. W. 2 Waiting, D. J. 1 Barr, C. S. 2; Affiliation: 1: Center for Nuclear Waste Regulatory Analyses, San Antonio, Texas, U.S.A. 2: U.S. Nuclear Regulatory Commission, Washington, D.C., U.S.A.; Source Info: 2013, Issue 56, p1; Subject Term: GROUT (Mortar); Subject Term: RESEARCH; Subject Term: POLLUTANTS -- Research; Subject Term: SLAG; Subject Term: FLY ash; Subject Term: PORTLAND cement; Subject Term: HYDROGEN-ion concentration; Subject Term: SOLUBILITY; Subject Term: SAVANNAH River Site (S.C.); NAICS/Industry Codes: 327310 Cement Manufacturing; NAICS/Industry Codes: 327990 All other non-metallic mineral product manufacturing; NAICS/Industry Codes: 327992 Ground or Treated Mineral and Earth Manufacturing; Number of Pages: 9p; Document Type: Article
L3 - 10.1051/epjconf/20135601010
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=90226723&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Snyder, K. A.
AU - Stutzman, P. E.
AU - Philip, J.
AU - Esh, D.
T1 - Hydrated phases and pore solution composition in cement-solidified saltstone waste forms.
JO - EPJ Web of Conferences
JF - EPJ Web of Conferences
Y1 - 2013/12/08/
IS - 56
M3 - Article
SP - 1
EP - 8
SN - 2100014X
AB - The mineral phases and pore solution composition of hydrated cement-solidified synthetic saltstone waste forms are quantified using thermogravimetric analysis, quantitative X-ray powder diffraction, and inductively coupled plasma atomic emission spectroscopy. Although the synthetic waste contained additional sulfate, the overall chemistry of the system suppressed the formation of sulfate-bearing mineral phases. This was corroborated by the pore solution analysis that indicated very high sulfur concentrations. After one year of hydration, the mineral phases present and the composition of the pore solution are stable, and are generally consistent with expectations based on the hydration of high volume portland cement replacement mixtures. [ABSTRACT FROM AUTHOR]
AB - Copyright of EPJ Web of Conferences is the property of EDP Sciences and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SOLID waste
KW - RESEARCH
KW - CEMENT -- Research
KW - MINERALS
KW - THERMOGRAVIMETRY
KW - X-ray diffraction
KW - INDUCTIVELY coupled plasma atomic emission spectrometry
KW - SULFATES
KW - HYDRATION
N1 - Accession Number: 90226714; Snyder, K. A. 1; Email Address: kenneth.snyder@nist.gov Stutzman, P. E. 1 Philip, J. 2 Esh, D. 2; Affiliation: 1: National Institute of Standards and Technology, Gaithersburg, MD USA 2: U.S. Nuclear Regulatory Commission, Washington, D.C. USA; Source Info: 2013, Issue 56, p1; Subject Term: SOLID waste; Subject Term: RESEARCH; Subject Term: CEMENT -- Research; Subject Term: MINERALS; Subject Term: THERMOGRAVIMETRY; Subject Term: X-ray diffraction; Subject Term: INDUCTIVELY coupled plasma atomic emission spectrometry; Subject Term: SULFATES; Subject Term: HYDRATION; NAICS/Industry Codes: 416390 Other specialty-line building supplies merchant wholesalers; NAICS/Industry Codes: 327310 Cement Manufacturing; NAICS/Industry Codes: 418920 Mineral, ore and precious metal merchant wholesalers; NAICS/Industry Codes: 327999 All Other Miscellaneous Nonmetallic Mineral Product Manufacturing; NAICS/Industry Codes: 327992 Ground or Treated Mineral and Earth Manufacturing; NAICS/Industry Codes: 423520 Coal and Other Mineral and Ore Merchant Wholesalers; Number of Pages: 8p; Document Type: Article
L3 - 10.1051/epjconf/20135601001
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=90226714&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - Gen
ID - 9999-36404-000
AN - 9999-36404-000
AU - Morrow, Stephanie L.
AU - Koves, G. Kenneth
AU - Barnes, Valerie E.
T1 - Organizational Safety Culture Survey
JF - PsycTESTS
JO - PsycTESTS
Y1 - 2014///
AD - Morrow, Stephanie L., Nuclear Regulatory Commission, 11555 Rockville Pike, MailStop O-4A15A, Rockville, Maryland, United States, 20852-2738
AV - Commercial: No; Permissions: May use for Research/Teaching; Fee: No. Test Items: Yes
N1 - Accession Number: 9999-36404-000. Partial author list: First Author & Affiliation: Morrow, Stephanie L.; United States Nuclear Regulatory Commission, Washington, District of Columbia, United States. Release Date: 20150209. Correction Date: 20160808. Instrument Type: Rating Scale. Test Location: Table 1, Page 42. Test Format: The Organizational Safety Culture Survey consists of 60 items rated on a 7-point Likert scale ranging from strongly disagree to strongly agree. Each item also included a ‘‘do not know/no opportunity to observe’’ response option.. Language: English. Constructs: Nuclear Power Plant Organizational Safety Culture; Classification: Organizational, Occupational, and Career Development (7000). Population: Human (10). Age Group: Adulthood (18 yrs & older) (300).
N2 - Administration Method: Electronic
AB - Purpose: The purpose of the Organizational Safety Culture Survey is to assess perceptions of organizational safety culture and other safety factors from the perspective of personnel at nuclear power plants in the U.S.
AB - Description: Developed in the context of a study exploring the relationship between safety culture and safety performance in U.S. nuclear power operations, the Organizational Safety Culture Survey (Morrow, Koves, & Barnes, 2014) assesses perceptions of organizational safety culture and other safety factors from the perspective of personnel at nuclear power plants in the U.S. The initial survey consisted of 110 items drafted from multiple sources, including INPO’s Principles for a Strong Nuclear Safety Culture (INPO, 2004), IAEA’s safety culture characteristics and attributes (IAEA, 2006), inputs from the NRC’s inspection program, relevant items from published surveys in the safety culture research literature, and behaviors characterizing a positive safety culture developed by subject matter experts in the nuclear industry. Survey participants were asked to rate their degree of agreement with each statement using a 7-point Likert scale ranging from strongly disagree to strongly agree. Each item also included a ‘‘do not know/no opportunity to observe’’ response option. Exploratory factor analysis found 9 factors and revised the item count to sixty. Confirmatory factor analysis confirmed the 60-item 9-factor solution: management commitment to safety, willingness to raise safety concerns, decision making, supervisor responsibility for safety, questioning attitude, safety communication, personal responsibility for safety, prioritizing safety, and training quality. The overall measure demonstrated adequate internal consistency with a Cronbach’s alpha of .98, with factor alpha values ranging from .77 to .96. (PsycTESTS Database Record (c) 2016 APA, all rights reserved)
KW - Decision-Making Factor
KW - Employee Perceptions
KW - Factor Analysis
KW - Internal Consistency
KW - Management Commitment to Safety Factor
KW - Organizational Safety Culture Survey
KW - Personal Responsibility for Safety Factor
KW - Personnel from Nuclear Power Plants
KW - Prioritizing Safety Factor
KW - Questioning Attitude Factor
KW - Safety Communication Factor
KW - Self-Report
KW - Supervisor Responsibility Factor
KW - Test Development
KW - Training Quality Factor
KW - Willingness to Raise Safety Concerns Factor
U5 - Organizational Safety Culture Survey [Test Development]Exploring the relationship between safety culture and safety performance in U. S. nuclear power operations. (AN: 2014-28700-006 from PsycINFO) Morrow, Stephanie L.; Koves, G. Kenneth; Barnes, Valerie E.; Nov, 2014. Source: Safety Science. 69, Elsevier Science, Netherlands; Nov, 2014; Administration: Electronic Age Group: Adulthood (18 yrs & older); Population: Human; Location: United States; Sample: Personnel from Nuclear Power Plants Keywords: Decision-Making Factor; Employee Perceptions; Factor Analysis; Internal Consistency; Management Commitment to Safety Factor; Organizational Safety Culture Survey; Personal Responsibility for Safety Factor; Personnel from Nuclear Power Plants; Prioritizing Safety Factor; Questioning Attitude Factor; Safety Communication Factor; Self-Report; Supervisor Responsibility Factor; Test Development; Training Quality Factor; Willingness to Raise Safety Concerns Factor; Subjects: Attitude Measures; Communication Skills; Decision Making; Employee Attitudes; Management Personnel; Nuclear Technology; Occupational Safety; Organizational Behavior; Organizational Climate; Organizational Commitment; Responsibility; Self-Report; Supervisor Employee Interaction; Test Construction; Test Reliability; Training; Working Conditions;
DO - 10.1037/t36404-000
L3 - Partial; Full text; 999936404_partial_001.pdf
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=pst&AN=9999-36404-000&site=ehost-live&scope=site
UR - Stephanie.Morrow@nrc.gov
DP - EBSCOhost
DB - pst
ER -
TY - JOUR
AU - Pulvirentia, April L.
AU - Barkatta, Aaron
AU - Adel-Hadadia, Mohamad A.
AU - Thorpec, Arthur N.
AU - Senftlec, Frank E.
AU - Grantc, Julius R.
T1 - Removal of superparamagnetic corrosion products and contaminants from drinking water using activated carbon.
JO - Desalination & Water Treatment
JF - Desalination & Water Treatment
Y1 - 2014/04//
VL - 52
IS - 16-18
M3 - Article
SP - 3096
EP - 3103
SN - 19443994
AB - Particulate matter separated from tap water using columns of coarse and fine activated carbon was characterized by means of chemical analysis, magnetization measurements, X-ray diffraction (XRD) and scanning electron microscopy (SEM)--energy dispersive X-ray spectrometry (EDS). A large fraction of the solids accumulated on the activated carbon consisted of iron oxides, in particular magnetite nanoparticles, and of iron oxyhydroxides, specifically goethite and lepidocrocite. These species formed as a result of corrosion of iron or carbon steel pipes. The removal of various iron species was measured using a two-column system consisting of a column of coarse activated carbon followed by a column of fine activated carbon. The results indicated that coarse activated carbon was only effective in removing oxyhydroxide particles, while the fine activated carbon was also able to remove nanoparticles of anhydrous iron oxides such as magnetite and maghemite. In addition, it was observed that while a majority of the content of contaminants, such as lead and copper, was removed upon passing the water through the coarse activated carbon, a significant fraction of the contaminant content was only removed upon subsequently passing the water through the fine activated carbon. It was concluded that most of the content of lead, copper, and other contaminants was associated with the iron oxyhydroxides, but a sizeable fraction was associated with the magnetite nanoparticles. Thus, the results supported the assumption that the presence of contaminants associated with magnetite nanoparticles in drinking water can be a significant mode of contaminant transport through water distribution systems. [ABSTRACT FROM AUTHOR]
AB - Copyright of Desalination & Water Treatment is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Drinking water -- Purification
KW - Activated carbon
KW - Iron
KW - Superparamagnetic materials
KW - X-ray diffraction
KW - Contaminants
KW - Drinking water
KW - Nanoparticles
N1 - Accession Number: 96332309; Pulvirentia, April L. 1,2; Barkatta, Aaron 1; Adel-Hadadia, Mohamad A. 1; Thorpec, Arthur N. 3; Senftlec, Frank E. 3,4; Grantc, Julius R. 3; Email Address: jgrant@howard.edu; Affiliations: 1: Department of Chemistry, The Catholic University of America, Washington, DC, USA; 2: US Nuclear Regulatory Commission, Rockville, MD, USA; 3: Department of Physics and Astronomy, Howard University, Washington, DC, USA; 4: General Research Laboratory, Gaithersburg, MD, USA; Issue Info: Apr2014, Vol. 52 Issue 16-18, p3096; Thesaurus Term: Drinking water -- Purification; Thesaurus Term: Activated carbon; Thesaurus Term: Iron; Subject Term: Superparamagnetic materials; Subject Term: X-ray diffraction; Author-Supplied Keyword: Contaminants; Author-Supplied Keyword: Drinking water; Author-Supplied Keyword: Nanoparticles; NAICS/Industry Codes: 325998 All Other Miscellaneous Chemical Product and Preparation Manufacturing; NAICS/Industry Codes: 325999 All other miscellaneous chemical product manufacturing; NAICS/Industry Codes: 312112 Bottled Water Manufacturing; NAICS/Industry Codes: 331110 Iron and Steel Mills and Ferroalloy Manufacturing; NAICS/Industry Codes: 416210 Metal service centres; Number of Pages: 8p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Wellock, Thomas
T1 - Hope, Promise, and Risk in the Nuclear Era.
JO - H-Net Reviews in the Humanities & Social Sciences
JF - H-Net Reviews in the Humanities & Social Sciences
Y1 - 2014/04//
M3 - Book Review
SP - 1
EP - 3
SN - 15380661
KW - NUCLEAR weapons -- History
KW - NONFICTION
KW - MELOSI, Martin Victor, 1947-
KW - ATOMIC Age America (Book)
N1 - Accession Number: 95824327; Wellock, Thomas 1; Affiliations: 1 : US Nuclear Regulatory Commission; Source Info: Apr2014, p1; Historical Period: ca 1945 to 2012; Subject Term: NUCLEAR weapons -- History; Subject Term: NONFICTION; Number of Pages: 3p; Document Type: Book Review
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DP - EBSCOhost
DB - hia
ER -
TY - JOUR
AU - Chen, Y.
AU - Rao, A.S.
AU - Alexandreanu, B.
AU - Natesan, K.
T1 - Slow strain rate tensile tests on irradiated austenitic stainless steels in simulated light water reactor environments.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2014/04//
VL - 269
M3 - Article
SP - 38
EP - 44
SN - 00295493
AB - Abstract: Irradiation stress corrosion cracking (IASCC) is a critical degradation mechanism for reactor internal components that contributes to the safe and economic operation of reactors. As nuclear power plants age and irradiation dose increases, IASCC becomes an increasingly important issue because of its potential impact on the integrity of reactor internal components. In this study, slow strain rate tensile tests were conducted on irradiated tensile specimens at strain rates between 3 and 7×10−7 s−1 to evaluate cracking susceptibility of austenitic stainless steels in simulated light water reactor (LWR) environments. Significant increases in yield strength were observed for all irradiated specimens and a dose dependence of irradiation hardening was obtained at temperatures relevant to LWRs. Ductility and strain hardening capability were also found decrease rapidly with the increase of dose. After the tests, the specimens were examined using a scanning electron microscopy to characterize fracture morphology. The area fractions of non-ductility fracture were used to evaluate the IASCC susceptibility along with the tensile properties. IASCC susceptibility was also compared for several stainless steels irradiated in the Halden and BOR-60 reactors. A possible neutron spectrum effect was discussed. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SLOW strain rate tests
KW - TENSILE test (Materials)
KW - AUSTENITIC stainless steel
KW - LIGHT water reactors
KW - FRACTURE mechanics
KW - MAGNETIC susceptibility
N1 - Accession Number: 94795020; Chen, Y. 1; Email Address: yiren_chen@anl.gov Rao, A.S. 2 Alexandreanu, B. 1 Natesan, K. 1; Affiliation: 1: Nuclear Engineering Division, Argonne National Laboratory, Argonne, IL 60439, USA 2: US Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Apr2014, Vol. 269, p38; Subject Term: SLOW strain rate tests; Subject Term: TENSILE test (Materials); Subject Term: AUSTENITIC stainless steel; Subject Term: LIGHT water reactors; Subject Term: FRACTURE mechanics; Subject Term: MAGNETIC susceptibility; Number of Pages: 7p; Document Type: Article
L3 - 10.1016/j.nucengdes.2013.08.003
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=94795020&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Rao, Appajosula S.
T1 - Degradation of austenitic stainless steel (SS) light water ractor (LWR) core internals due to neutron irradiation.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2014/04//
VL - 269
M3 - Article
SP - 78
EP - 82
SN - 00295493
AB - Abstract: Austenitic stainless steels (SSs) are extensively being used in the fabrication of light water reactor (LWR) core internal components. It is because these steels have relatively high ductility, fracture toughness and moderate strength. However, the LWR internal components exposure to neutron irradiation over an extended period of plant operation degrades the materials mechanical properties such as the fracture toughness. This paper summarizes some of the results of the existing open literature data on irradiation assisted stress corrosion cracking (IASCC) of 316 CW steels that have been published by the United States Nuclear Regulatory Commission (USNRC), industry, academia, and other research agencies. [Copyright &y& Elsevier]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - AUSTENITIC stainless steel
KW - LIGHT water reactors
KW - NEUTRON irradiation
KW - DUCTILITY
KW - FRACTURE toughness
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 94795026; Rao, Appajosula S. 1; Email Address: Appajosula.Rao@nrc.gov; Affiliation: 1: Division of Engineering, Office of the Nuclear Regulatory Research US Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Apr2014, Vol. 269, p78; Subject Term: AUSTENITIC stainless steel; Subject Term: LIGHT water reactors; Subject Term: NEUTRON irradiation; Subject Term: DUCTILITY; Subject Term: FRACTURE toughness; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 5p; Document Type: Article
L3 - 10.1016/j.nucengdes.2013.08.010
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=94795026&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - James Chang, Y.
AU - Bley, Dennis
AU - Criscione, Lawrence
AU - Kirwan, Barry
AU - Mosleh, Ali
AU - Madary, Todd
AU - Nowell, Rodney
AU - Richards, Robert
AU - Roth, Emilie M.
AU - Sieben, Scott
AU - Zoulis, Antonios
T1 - The SACADA database for human reliability and human performance.
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2014/05//
VL - 125
M3 - Article
SP - 117
EP - 133
SN - 09518320
AB - Abstract: Lack of appropriate and sufficient human performance data has been identified as a key factor affecting human reliability analysis (HRA) quality especially in the estimation of human error probability (HEP). The Scenario Authoring, Characterization, and Debriefing Application (SACADA) database was developed by the U.S. Nuclear Regulatory Commission (NRC) to address this data need. An agreement between NRC and the South Texas Project Nuclear Operating Company (STPNOC) was established to support the SACADA development with aims to make the SACADA tool suitable for implementation in the nuclear power plants' operator training program to collect operator performance information. The collected data would support the STPNOC's operator training program and be shared with the NRC for improving HRA quality. This paper discusses the SACADA data taxonomy, the theoretical foundation, the prospective data to be generated from the SACADA raw data to inform human reliability and human performance, and the considerations on the use of simulator data for HRA. Each SACADA data point consists of two information segments: context and performance results. Context is a characterization of the performance challenges to task success. The performance results are the results of performing the task. The data taxonomy uses a macrocognitive functions model for the framework. At a high level, information is classified according to the macrocognitive functions of detecting the plant abnormality, understanding the abnormality, deciding the response plan, executing the response plan, and team related aspects (i.e., communication, teamwork, and supervision). The data are expected to be useful for analyzing the relations between context, error modes and error causes in human performance. [Copyright &y& Elsevier]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - DATABASES
KW - RELIABILITY (Engineering)
KW - PERFORMANCE evaluation
KW - NUCLEAR power plants -- Employees
KW - INFORMATION processing
KW - TRAINING of
KW - HRA database performance
KW - Human reliability analysis
KW - Operator training
KW - SOUTH Texas Project Nuclear Operating Co.
N1 - Accession Number: 94792736; James Chang, Y. 1; Email Address: james.chang@nrc.gov Bley, Dennis 2 Criscione, Lawrence 1 Kirwan, Barry 3 Mosleh, Ali 4 Madary, Todd 5 Nowell, Rodney 5 Richards, Robert 6 Roth, Emilie M. 7 Sieben, Scott 5 Zoulis, Antonios 1; Affiliation: 1: U.S. Nuclear Regulatory Commission, Rockville, USA 2: The WreathWood Group, Virginia, USA 3: Eurocontrol, France 4: University of Maryland, College Park, USA 5: South Texas Project Nuclear Operating Company, USA 6: The Idaho National Laboratory, Idaho Falls, USA 7: Roth Cognitive Engineering, Menlo Park, California, USA; Source Info: May2014, Vol. 125, p117; Subject Term: DATABASES; Subject Term: RELIABILITY (Engineering); Subject Term: PERFORMANCE evaluation; Subject Term: NUCLEAR power plants -- Employees; Subject Term: INFORMATION processing; Subject Term: TRAINING of; Author-Supplied Keyword: HRA database performance; Author-Supplied Keyword: Human reliability analysis; Author-Supplied Keyword: Operator training; Company/Entity: SOUTH Texas Project Nuclear Operating Co.; Number of Pages: 17p; Document Type: Article
L3 - 10.1016/j.ress.2013.07.014
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=94792736&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Justin A Vazquez
AU - Peter F Caracappa
AU - X George Xu
T1 - Development of posture-specific computational phantoms using motion capture technology and application to radiation dose-reconstruction for the 1999 Tokai-Mura nuclear criticality accident.
JO - Physics in Medicine & Biology
JF - Physics in Medicine & Biology
Y1 - 2014/09/21/
VL - 59
IS - 18
M3 - Article
SP - 1
EP - 1
SN - 00319155
AB - The majority of existing computational phantoms are designed to represent workers in typical standing anatomical postures with fixed arm and leg positions. However, workers found in accident-related scenarios often assume varied postures. This paper describes the development and application of two phantoms with adjusted postures specified by data acquired from a motion capture system to simulate unique human postures found in a 1999 criticality accident that took place at a JCO facility in Tokai-Mura, Japan. In the course of this accident, two workers were fatally exposed to extremely high levels of radiation. Implementation of the emergent techniques discussed produced more accurate and more detailed dose estimates for the two workers than were reported in previous studies. A total-body dose of 6.43 and 26.38 Gy was estimated for the two workers, who assumed a crouching and a standing posture, respectively. Additionally, organ-specific dose estimates were determined, including a 7.93 Gy dose to the thyroid and 6.11 Gy dose to the stomach for the crouching worker and a 41.71 Gy dose to the liver and a 37.26 Gy dose to the stomach for the standing worker. Implications for the medical prognosis of the workers are discussed, and the results of this study were found to correlate better with the patient outcome than previous estimates, suggesting potential future applications of such methods for improved epidemiological studies involving next-generation computational phantom tools. [ABSTRACT FROM AUTHOR]
AB - Copyright of Physics in Medicine & Biology is the property of IOP Publishing and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - PHANTOMS (Radiology)
KW - COMPUTER simulation
KW - MOTION capture (Medicine)
KW - HUMAN anatomical models (Objects)
KW - RADIATION -- Dosage
KW - NUCLEAR accidents
KW - TOKAI-mura (Japan)
N1 - Accession Number: 97824982; Justin A Vazquez 1,2 Peter F Caracappa 2 X George Xu 2; Email Address: xug2@rpi.edu; Affiliation: 1: Present address: US Nuclear Regulatory Commission, Washington, DC 20555-0001, USA. The opinions, findings, conclusions, and recommendations expressed herein are his own and do not necessarily reflect the views of the employer. 2: Nuclear Engineering Program, Rensselaer Polytechnic Institute, Troy, NY 12180, USA; Source Info: 9/21/2014, Vol. 59 Issue 18, p1; Subject Term: PHANTOMS (Radiology); Subject Term: COMPUTER simulation; Subject Term: MOTION capture (Medicine); Subject Term: HUMAN anatomical models (Objects); Subject Term: RADIATION -- Dosage; Subject Term: NUCLEAR accidents; Subject Term: TOKAI-mura (Japan); Number of Pages: 1p; Document Type: Article
L3 - 10.1088/0031-9155/59/18/5277
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Yadav, Mohan S.
AU - Kim, Seungjin
AU - Tien, Kirk
AU - Bajorek, Stephen M.
T1 - Experiments on geometric effects of 90-degree vertical-upward elbow in air water two-phase flow.
JO - International Journal of Multiphase Flow
JF - International Journal of Multiphase Flow
Y1 - 2014/10//
VL - 65
M3 - Article
SP - 98
EP - 107
SN - 03019322
AB - This study investigates the geometric effects of a 90-degree vertical-upward elbow on local two-phase flow-parameters in an air–water system, and develops an experimental database for interfacial area transport modeling. The experimental facility is constructed from 5.08 cm inner diameter acrylic pipes and includes vertical and horizontal sections interconnected by a 90-degree vertical glass elbow. The elbow has a radius of curvature of 15.24 cm and is installed at L / D = 63 from the inlet. A four-sensor conductivity probe is used to measure time-averaged local two-phase flow parameters including: void fraction, bubble velocity, interfacial area concentration, and bubble frequency at ten axial locations along the test section. It is observed that the bubbles moving through the vertical-upward elbow are entrained by the secondary flow leading to a bimodal distribution in bubbly flow conditions. For the flow conditions investigated within the study, this bimodal distribution occurs regardless of the bubble distribution upstream of the elbow. It is found that the change in bubble distribution downstream of the elbow is strongly correlated to the dissipation of the elbow effects. Furthermore, the dissipation characteristics as well as the length of dissipation region for the vertical-upward elbow are found to be a strong function of the liquid-phase flow rate. [ABSTRACT FROM AUTHOR]
AB - Copyright of International Journal of Multiphase Flow is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - TWO-phase flow
KW - AIR-water interfaces
KW - PHYSICS experiments
KW - AIR flow
KW - GEOMETRIC analysis
KW - GAS flow
KW - BUBBLES
KW - Elbow effect
KW - Interfacial area concentration
KW - Two-phase bubbly flow
KW - Void fraction
N1 - Accession Number: 97410302; Yadav, Mohan S. 1 Kim, Seungjin 1; Email Address: skim@psu.edu Tien, Kirk 2 Bajorek, Stephen M. 2; Affiliation: 1: The Pennsylvania State University, Mechanical and Nuclear Engineering Department, 230 Reber Building, State College, PA 16802, United States 2: The United States Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Oct2014, Vol. 65, p98; Subject Term: TWO-phase flow; Subject Term: AIR-water interfaces; Subject Term: PHYSICS experiments; Subject Term: AIR flow; Subject Term: GEOMETRIC analysis; Subject Term: GAS flow; Subject Term: BUBBLES; Author-Supplied Keyword: Elbow effect; Author-Supplied Keyword: Interfacial area concentration; Author-Supplied Keyword: Two-phase bubbly flow; Author-Supplied Keyword: Void fraction; Number of Pages: 10p; Document Type: Article
L3 - 10.1016/j.ijmultiphaseflow.2014.05.014
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=97410302&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
ID - 109756227
T1 - Civility norms, safety climate, and safety outcomes: A preliminary investigation.
AU - McGonagle, Alyssa K
AU - Walsh, Benjamin M
AU - Kath, Lisa M
AU - Morrow, Stephanie L
Y1 - 2014/10//
N1 - Accession Number: 109756227. Language: English. Entry Date: 20150703. Revision Date: 20150923. Publication Type: Journal Article; research. Journal Subset: Biomedical; Peer Reviewed; USA. Special Interest: Psychiatry/Psychology. NLM UID: 9612485.
KW - Occupational Health
KW - Social Behavior
KW - Work Environment -- Psychosocial Factors
KW - Adult
KW - Female
KW - Human
KW - Male
KW - Wounds and Injuries -- Epidemiology
KW - Wounds and Injuries -- Psychosocial Factors
KW - Organizational Culture
KW - Safety
SP - 437
EP - 452
JO - Journal of Occupational Health Psychology
JF - Journal of Occupational Health Psychology
JA - J OCCUP HEALTH PSYCHOL
VL - 19
IS - 4
CY - Washington, District of Columbia
PB - American Psychological Association
SN - 1076-8998
AD - Department of Psychology, Wayne State University.
AD - Department of Management, University of Illinois at Springfield.
AD - Department of Psychology, San Diego State University.
AD - U.S. Nuclear Regulatory Commission.
U2 - PMID: 24933595.
DO - 10.1037/a0037110
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=rzh&AN=109756227&site=ehost-live&scope=site
DP - EBSCOhost
DB - rzh
ER -
TY - JOUR
ID - 2014-24211-001
AN - 2014-24211-001
AU - McGonagle, Alyssa K.
AU - Walsh, Benjamin M.
AU - Kath, Lisa M.
AU - Morrow, Stephanie L.
T1 - Civility norms, safety climate, and safety outcomes: A preliminary investigation.
JF - Journal of Occupational Health Psychology
JO - Journal of Occupational Health Psychology
JA - J Occup Health Psychol
Y1 - 2014/10//
VL - 19
IS - 4
SP - 437
EP - 452
CY - US
PB - Educational Publishing Foundation
SN - 1076-8998
SN - 1939-1307
AD - McGonagle, Alyssa K., Department of Psychology, Wayne State University, 5057 Woodward Avenue, 7th Floor, Detroit, MI, US, 48202
N1 - Accession Number: 2014-24211-001. PMID: 24933595 Partial author list: First Author & Affiliation: McGonagle, Alyssa K.; Department of Psychology, Wayne State University, Detroit, MI, US. Release Date: 20140616. Correction Date: 20140922. Publication Type: Journal (0100), Peer Reviewed Journal (0110). Format Covered: Electronic. Document Type: Journal Article. Language: English. Major Descriptor: Employee Interaction; Safety; Working Conditions. Minor Descriptor: Injuries; Well Being. Classification: Working Conditions & Industrial Safety (3670). Population: Human (10); Male (30); Female (40). Location: US. Age Group: Adulthood (18 yrs & older) (300). Tests & Measures: Civility Norms Questionnaire. Methodology: Empirical Study; Quantitative Study. Page Count: 16. Issue Publication Date: Oct, 2014. Publication History: First Posted Date: Jun 16, 2014; Accepted Date: Mar 19, 2014; Revised Date: Mar 17, 2014; First Submitted Date: Sep 10, 2012. Copyright Statement: American Psychological Association. 2014.
AB - Working environments that are both civil and safe are good for business and employee well-being. Civility has been empirically linked to such important outcomes as organizational performance and individuals’ positive work-related attitudes, yet research relating civility to safety is lacking. In this study, we link perceptions of civility norms to perceptions of safety climate and safety outcomes. Drawing on social exchange theory, we proposed and tested a model in 2 samples wherein civility norms indirectly relate to safety outcomes through associations with various safety climate facets. Our results supported direct relationships between civility and management safety climate and coworker safety climate. Additionally, indirect effects of civility norms on unsafe behaviors and injuries were observed. Indirect effects of civility norms on unsafe behaviors were observed through coworker safety climate and work-safety tension. Indirect effects of civility norms on injuries were observed through management safety climate and work-safety tension for full-time employees, although these effects did not hold for part-time employees. This study provides initial evidence that researchers and practitioners may want to look beyond safety climate to civility norms to more comprehensively understand the origins of unsafe behaviors and injuries and to develop appropriate preventive interventions. (PsycINFO Database Record (c) 2016 APA, all rights reserved)
KW - injuries
KW - civility norms
KW - safety climate
KW - unsafe behaviors
KW - 2014
KW - Employee Interaction
KW - Safety
KW - Working Conditions
KW - Injuries
KW - Well Being
KW - 2014
U1 - Sponsor: Volpe National Transportation Systems Center. Grant: DTRT57-07-P-80165. Other Details: Contract. Recipients: No recipient indicated
DO - 10.1037/a0037110
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=psyh&AN=2014-24211-001&site=ehost-live&scope=site
UR - alyssa.mcgonagle@wayne.edu
DP - EBSCOhost
DB - psyh
ER -
TY - JOUR
AU - Yadav, Mohan S.
AU - Worosz, Ted
AU - Kim, Seungjin
AU - Tien, Kirk
AU - Bajorek, Stephen M.
T1 - Characterization of the dissipation of elbow effects in bubbly two-phase flows.
JO - International Journal of Multiphase Flow
JF - International Journal of Multiphase Flow
Y1 - 2014/11//
VL - 66
M3 - Article
SP - 101
EP - 109
SN - 03019322
AB - This study develops a method to characterize the elbow-region for vertical-upward-to-horizontal air–water bubbly two-phase flows through a 90° elbow with a non-dimensional centerline radius of curvature, R C / D , of three. The dissipation of the elbow-effects in the horizontal region downstream of the elbow is characterized by the change in the local void fraction distribution. To quantify the dissipation characteristics, the elbow-strength, S , is defined as the inverse of the second moment of the local void fraction distribution. It is found that the elbow-strength decreases exponentially with increasing development length in the elbow-region. The slope of decrease of the elbow-strength in the elbow-region is determined by the dissipation parameter, β . The dissipation parameter determines the development length required for the elbow-effects on the two-phase flow parameters to become negligible. It is found that the dissipation parameter is a linear function of the mixture Reynolds number for the flow conditions investigated in the present study. [ABSTRACT FROM AUTHOR]
AB - Copyright of International Journal of Multiphase Flow is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - ENERGY dissipation
KW - TWO-phase flow
KW - BUBBLE dynamics
KW - RADIUS of curvature (Optics)
KW - AIR-water interfaces
KW - REYNOLDS number
KW - Bubbly flows
KW - Dissipation
KW - Elbow-effects
KW - Void fraction
N1 - Accession Number: 97935108; Yadav, Mohan S. 1 Worosz, Ted 1 Kim, Seungjin 1; Email Address: skim@psu.edu Tien, Kirk 2 Bajorek, Stephen M. 2; Affiliation: 1: The Pennsylvania State University, Department of Mechanical and Nuclear Engineering, 230 Reber Building, University Park, PA 16802, USA 2: The United States Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Nov2014, Vol. 66, p101; Subject Term: ENERGY dissipation; Subject Term: TWO-phase flow; Subject Term: BUBBLE dynamics; Subject Term: RADIUS of curvature (Optics); Subject Term: AIR-water interfaces; Subject Term: REYNOLDS number; Author-Supplied Keyword: Bubbly flows; Author-Supplied Keyword: Dissipation; Author-Supplied Keyword: Elbow-effects; Author-Supplied Keyword: Void fraction; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.ijmultiphaseflow.2014.07.012
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=97935108&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Boyd, Christopher
AU - Skarda, Raymond
T1 - CFD predictions of standby liquid control system mixing in lower plenum of a BWR.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2014/11//
VL - 279
M3 - Article
SP - 109
EP - 115
SN - 00295493
AB - During an anticipated transient without scram (ATWS) scenario in certain boiling water reactor (BWR) systems, a standby liquid control system (SLCS) is used to inject a sodium pentaborate solution into the reactor system in order to quickly shut down (scram) the reactor without the use of the control rods. Some BWR designs utilize a SLCS that injects through a set of nozzles on a vertical pipe in the peripheral region of the lower plenum of the reactor vessel. During the scenario, system water levels are reduced and natural circulation flow rates down through the jet pump nozzles and up into the core are a small fraction of the rated system flow. It is during this period that the SLCS flows are considered. This work outlines some initial scoping studies completed by the staff at the Nuclear Regulatory Commission (NRC). An attempt at benchmarking the computational fluid dynamics (CFD) approach using a set of available test data from a small facility is outlined. Due to our lack of information related to specific details of the facility geometry along with the limited data available from the test, the benchmark exercise produced only a qualitative basis for selecting turbulence models and mesh density. A CFD model simulating a full-scale reactor system is developed for the lower plenum of a representative BWR/4 design and SLCS flows and mixing are studied under a range of flow conditions. The full-scale BWR simulation builds upon the lessons learned from the benchmark exercise. One challenge for this work is the large size of the domain and the relatively small size of the geometric details such as flow passages and gaps. The geometry is simplified to make meshing feasible by eliminating some of the small features. The model includes the lower plenum, control rod drive tubes, basic support structures, and SLCS piping. A series of simulations are completed and modeling choices are discussed in light of best practice guidance. The predictions shed light on the applicability of previous test programs and provide a clearer understanding of the lower plenum flows and mixing. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - COMPUTATIONAL fluid dynamics
KW - BOILING water reactors
KW - PREDICTION models
KW - SIMULATION methods & models
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 99211308; Boyd, Christopher 1; Email Address: christopher.boyd@nrc.gov Skarda, Raymond 1; Email Address: Raymond.skarda@nrc.gov; Affiliation: 1: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Nov2014, Vol. 279, p109; Subject Term: COMPUTATIONAL fluid dynamics; Subject Term: BOILING water reactors; Subject Term: PREDICTION models; Subject Term: SIMULATION methods & models; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 7p; Document Type: Article
L3 - 10.1016/j.nucengdes.2014.02.007
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=99211308&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Morrow, Stephanie L.
AU - Koves, G. Kenneth
AU - Barnes, Valerie E.
T1 - Exploring the relationship between safety culture and safety performance in U.S. nuclear power operations.
JO - Safety Science
JF - Safety Science
Y1 - 2014/11//
VL - 69
M3 - Article
SP - 37
EP - 47
SN - 09257535
AB - How do nuclear power plant workers, within a single national culture, perceive safety culture within their organizations? What is the relationship between safety culture and other indicators of safety? Is the construct of safety culture useful for predicting future plant performance? These questions were addressed in the current study using a survey administered to a sample of personnel at 97% of the nuclear power plants in the United States, resulting in 2876 responses from 63 nuclear power plant sites. Exploratory and confirmatory factor analysis revealed a multi-factor structure to the safety culture survey. For each nuclear power plant, the mean score for the total survey results and the factor means were correlated with organization-level performance indicators both concurrently and one year following the survey administration. Correlations suggested meaningful, statistically significant relationships between safety culture, as measured by the survey, and multiple nuclear power plant performance indicators. This study presents a unique look at safety culture across the United States nuclear power industry and takes a critical step toward establishing that safety culture is empirically related to safety performance. [ABSTRACT FROM AUTHOR]
AB - Copyright of Safety Science is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear power plants
KW - Confirmatory factor analysis
KW - Corporate culture
KW - Social surveys
KW - Social clubs
KW - United States
KW - Human and organizational factors
KW - Nuclear power
KW - Organizational culture
KW - Safety climate
KW - Safety culture
KW - Safety performance
N1 - Accession Number: 96977207; Morrow, Stephanie L. 1; Email Address: Stephanie.Morrow@nrc.gov; Koves, G. Kenneth 2; Barnes, Valerie E. 1; Affiliations: 1: United States Nuclear Regulatory Commission, Washington, DC, USA; 2: Institute of Nuclear Power Operations, Atlanta, GA, USA; Issue Info: Nov2014, Vol. 69, p37; Thesaurus Term: Nuclear power plants; Subject Term: Confirmatory factor analysis; Subject Term: Corporate culture; Subject Term: Social surveys; Subject Term: Social clubs; Subject: United States; Author-Supplied Keyword: Human and organizational factors; Author-Supplied Keyword: Nuclear power; Author-Supplied Keyword: Organizational culture; Author-Supplied Keyword: Safety climate; Author-Supplied Keyword: Safety culture; Author-Supplied Keyword: Safety performance; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 813410 Civic and Social Organizations; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.ssci.2014.02.022
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=96977207&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Morrow, Stephanie L.
AU - Koves, G. Kenneth
AU - Barnes, Valerie E.
T1 - Exploring the relationship between safety culture and safety performance in U.S. nuclear power operations.
JO - Safety Science
JF - Safety Science
Y1 - 2014/11//
VL - 69
M3 - Article
SP - 37
EP - 47
SN - 09257535
AB - How do nuclear power plant workers, within a single national culture, perceive safety culture within their organizations? What is the relationship between safety culture and other indicators of safety? Is the construct of safety culture useful for predicting future plant performance? These questions were addressed in the current study using a survey administered to a sample of personnel at 97% of the nuclear power plants in the United States, resulting in 2876 responses from 63 nuclear power plant sites. Exploratory and confirmatory factor analysis revealed a multi-factor structure to the safety culture survey. For each nuclear power plant, the mean score for the total survey results and the factor means were correlated with organization-level performance indicators both concurrently and one year following the survey administration. Correlations suggested meaningful, statistically significant relationships between safety culture, as measured by the survey, and multiple nuclear power plant performance indicators. This study presents a unique look at safety culture across the United States nuclear power industry and takes a critical step toward establishing that safety culture is empirically related to safety performance. [ABSTRACT FROM AUTHOR]
AB - Copyright of Safety Science is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NUCLEAR power plants
KW - CONFIRMATORY factor analysis
KW - CORPORATE culture
KW - SOCIAL surveys
KW - SOCIAL clubs
KW - UNITED States
KW - Human and organizational factors
KW - Nuclear power
KW - Organizational culture
KW - Safety climate
KW - Safety culture
KW - Safety performance
N1 - Accession Number: 96977207; Morrow, Stephanie L. 1; Email Address: Stephanie.Morrow@nrc.gov Koves, G. Kenneth 2 Barnes, Valerie E. 1; Affiliation: 1: United States Nuclear Regulatory Commission, Washington, DC, USA 2: Institute of Nuclear Power Operations, Atlanta, GA, USA; Source Info: Nov2014, Vol. 69, p37; Subject Term: NUCLEAR power plants; Subject Term: CONFIRMATORY factor analysis; Subject Term: CORPORATE culture; Subject Term: SOCIAL surveys; Subject Term: SOCIAL clubs; Subject Term: UNITED States; Author-Supplied Keyword: Human and organizational factors; Author-Supplied Keyword: Nuclear power; Author-Supplied Keyword: Organizational culture; Author-Supplied Keyword: Safety climate; Author-Supplied Keyword: Safety culture; Author-Supplied Keyword: Safety performance; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; NAICS/Industry Codes: 813410 Civic and Social Organizations; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.ssci.2014.02.022
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=96977207&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
ID - 2014-28700-006
AN - 2014-28700-006
AU - Morrow, Stephanie L.
AU - Koves, G. Kenneth
AU - Barnes, Valerie E.
T1 - Exploring the relationship between safety culture and safety performance in U. S. nuclear power operations.
JF - Safety Science
JO - Safety Science
JA - Saf Sci
Y1 - 2014/11//
VL - 69
SP - 37
EP - 47
CY - Netherlands
PB - Elsevier Science
SN - 0925-7535
AD - Morrow, Stephanie L., Nuclear Regulatory Commission, 11555 Rockville Pike, MailStop O-4A15A, Rockville, MD, US, 20852-2738
N1 - Accession Number: 2014-28700-006. Other Journal Title: Journal of Occupational Accidents. Partial author list: First Author & Affiliation: Morrow, Stephanie L.; United States Nuclear Regulatory Commission, Washington, DC, US. Release Date: 20141117. Correction Date: 20151228. Publication Type: Journal (0100), Peer Reviewed Journal (0110). Format Covered: Electronic. Document Type: Journal Article. Language: English. Major Descriptor: Occupational Safety; Organizational Characteristics; Organizational Climate. Minor Descriptor: Nuclear Technology. Classification: Working Conditions & Industrial Safety (3670). Population: Human (10). Location: US. Age Group: Adulthood (18 yrs & older) (300). Tests & Measures: Chemistry Performance Index; Organizational Safety Culture Measure. Methodology: Empirical Study; Quantitative Study. References Available: Y. Page Count: 11. Issue Publication Date: Nov, 2014. Publication History: First Posted Date: Mar 19, 2014.
AB - How do nuclear power plant workers, within a single national culture, perceive safety culture within their organizations? What is the relationship between safety culture and other indicators of safety? Is the construct of safety culture useful for predicting future plant performance? These questions were addressed in the current study using a survey administered to a sample of personnel at 97% of the nuclear power plants in the United States, resulting in 2876 responses from 63 nuclear power plant sites. Exploratory and confirmatory factor analysis revealed a multi-factor structure to the safety culture survey. For each nuclear power plant, the mean score for the total survey results and the factor means were correlated with organization-level performance indicators both concurrently and one year following the survey administration. Correlations suggested meaningful, statistically significant relationships between safety culture, as measured by the survey, and multiple nuclear power plant performance indicators. This study presents a unique look at safety culture across the United States nuclear power industry and takes a critical step toward establishing that safety culture is empirically related to safety performance. (PsycINFO Database Record (c) 2016 APA, all rights reserved)
KW - human and organizational factors
KW - nuclear power
KW - organizational culture
KW - safety climate
KW - safety culture
KW - safety performance
KW - 2014
KW - Occupational Safety
KW - Organizational Characteristics
KW - Organizational Climate
KW - Nuclear Technology
KW - 2014
DO - 10.1016/j.ssci.2014.02.022
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=psyh&AN=2014-28700-006&site=ehost-live&scope=site
UR - Stephanie.Morrow@nrc.gov
DP - EBSCOhost
DB - psyh
ER -
TY - JOUR
AU - Bosland, L.
AU - Dickinson, S.
AU - Glowa, G.A.
AU - Herranz, L.E.
AU - Kim, H.C.
AU - Powers, D.A.
AU - Salay, M.
AU - Tietze, S.
T1 - Iodine–paint interactions during nuclear reactor severe accidents.
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
Y1 - 2014/12//
VL - 74
M3 - Article
SP - 184
EP - 199
SN - 03064549
AB - To assess the radiological consequences of a severe reactor accident, it is important to be able to predict the behaviour of iodine in containment. Some interactions between iodine and containment paint (e.g., adsorption) have been well known for a long time. However, in recent years, new phenomena have been identified that can affect the gas phase iodine concentration in the longer term (e.g., the release of molecular iodine and organic iodides from irradiated painted surfaces). Several international collaborations and organizations around the world are currently addressing different aspects of this topic, including laboratory experiments and theoretical studies ( ab initio ) designed to improve the mechanistic understanding of the phenomena. Knowledge of the underlying mechanisms will provide explanations for behavioural differences observed between paint types, and will support the extrapolation of laboratory results to the safety analyses of nuclear reactors. The purpose of this paper is to present a selection of recent work performed by Severe Accident Research Network (SARNET) members regarding iodine–paint interactions and paint aging in order to improve the common understanding and better define what has still to be done in this area. The Severe Accident Research Network (SARNET) provides a framework within which members can share and discuss results. [ABSTRACT FROM AUTHOR]
AB - Copyright of Annals of Nuclear Energy is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Nuclear reactor accidents
KW - Iodine
KW - Adsorption
KW - Radiology
KW - Fission reactor containment
KW - Gas phase reactions
KW - Nuclear reactors -- Safety measures
KW - Accident analysis
KW - Containment paint
KW - Iodine behaviour
KW - Severe accident
N1 - Accession Number: 98554357; Bosland, L. 1; Dickinson, S. 2; Glowa, G.A. 3; Email Address: glowag@aecl.ca; Herranz, L.E. 4; Kim, H.C. 5; Powers, D.A. 6; Salay, M. 7; Tietze, S. 8; Affiliations: 1: Institut de Radioprotection et de Sûreté Nucléaire, PSN/SAG/LETR, Centre de Cadarache, 13115 Saint Paul lez Durance Cedex, France; 2: National Nuclear Laboratory, Harwell Oxford Business Centre, Didcot, Oxon OX11 0QT, UK; 3: Atomic Energy of Canada Limited, Chalk River Laboratories, Chalk River, Ontario K0J 1J0, Canada; 4: CIEMAT, Av. Complutense 40, 28040 Madrid, Spain; 5: Korea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon 305-338, Republic of Korea; 6: Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185, USA; 7: U.S. Nuclear Regulatory Commission, MS: C3-A07M, Washington, DC 20555-0001, USA; 8: Chalmers University of Technology, Nuclear Chemistry, Kemivägen 4, SE-41296 Göteborg, Sweden; Issue Info: Dec2014, Vol. 74, p184; Thesaurus Term: Nuclear reactor accidents; Thesaurus Term: Iodine; Thesaurus Term: Adsorption; Subject Term: Radiology; Subject Term: Fission reactor containment; Subject Term: Gas phase reactions; Subject Term: Nuclear reactors -- Safety measures; Author-Supplied Keyword: Accident analysis; Author-Supplied Keyword: Containment paint; Author-Supplied Keyword: Iodine behaviour; Author-Supplied Keyword: Severe accident; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 16p; Document Type: Article
L3 - 10.1016/j.anucene.2014.07.016
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=98554357&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Camper, Larry W.
AU - Cruz, Zahira
T1 - ENVIRONMENTAL REVIEWS AND CASE STUDIES: NEPA Training Is Essential: It Shouldn’t Just Be for Environmental Staff.
JO - Environmental Practice
JF - Environmental Practice
Y1 - 2014/12//
VL - 16
IS - 4
M3 - Article
SP - 287
EP - 289
SN - 14660474
AB - In times of increasing workloads and flat budgets, it is important that the US Nuclear Regulatory Commission (NRC) use available resources and techniques efficiently and effectively to achieve success in environmental reviews throughout the agency. By implementing a contract with Duke University, cosponsored by the Council on Environmental Quality, to present courses near the NRC Headquarters in the Implementation of National Environmental Policy Act (NEPA), the NRC major program offices achieved success in training a large number of staff in NEPA in a timely and cost-effective manner. In addition, this training is positioning NRC staff to complete the Duke University graduate-level professional certificate in NEPA.Environmental Practice 16: 287–289(2014) [ABSTRACT FROM AUTHOR]
AB - Copyright of Environmental Practice is the property of Cambridge University Press and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Environmental impact analysis
KW - Decision making in environmental policy -- United States
KW - Duke University
KW - U.S. Nuclear Regulatory Commission
KW - United States. National Environmental Policy Act of 1969
N1 - Accession Number: 100871420; Camper, Larry W. 1; Cruz, Zahira 1; Affiliations: 1: Larry W. Camper, Director, and Zahira Cruz, Geotechnical Engineer, Division of Decommissioning, Uranium Recovery, and Waste Programs, US Nuclear Regulatory Commission, Washington, DC; Issue Info: Dec2014, Vol. 16 Issue 4, p287; Thesaurus Term: Environmental impact analysis; Subject Term: Decision making in environmental policy -- United States ; Company/Entity: Duke University ; Company/Entity: U.S. Nuclear Regulatory Commission ; Company/Entity: United States. National Environmental Policy Act of 1969; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
L3 - 10.1017/S1466046614000283
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=100871420&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Evans, Robert
T1 - ENVIRONMENTAL REVIEWS AND CASE STUDIES: Decision Making in the Environmental Impact Assessment Process.
JO - Environmental Practice
JF - Environmental Practice
Y1 - 2014/12//
VL - 16
IS - 4
M3 - Article
SP - 290
EP - 301
SN - 14660474
AB - This article analyzes the decision-making processes used by government agencies when trying to decide whether to approve or reject projects that impact the environment. This article examines some of the real-life inputs into the decision, as well as the influences on the decision maker. For example, some academics suggest that decision makers are more influenced by the environmental impact assessment process itself than by the conclusions of the assessment. Three case studies are presented. I provide an overview of each project and the various influences on the respective decision maker. I demonstrate that decision makers tend to elevate social, cultural, and political concerns over the natural environment. I also demonstrate that each decision maker was influenced by a particular social, cultural, or political aspect unique to each situation. I recommend further research in the expanding use of analytical tools and models in environmental decision making. These tools may encourage the decision maker to give more consideration to the results of the environmental impact assessment versus other external influences. Environmental Practice 16: 290–301 (2014) [ABSTRACT FROM AUTHOR]
AB - Copyright of Environmental Practice is the property of Cambridge University Press and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Environmental impact analysis
KW - Government agencies -- United States
KW - Decision making in environmental policy -- United States
KW - Decision making
KW - United States. National Environmental Policy Act of 1969
N1 - Accession Number: 100871421; Evans, Robert 1; Affiliations: 1: Robert Evans, PhD, PE, CHP, Senior Health Physicist, US Nuclear Regulatory Commission, Region IV Office, Arlington, Texas.; Issue Info: Dec2014, Vol. 16 Issue 4, p290; Thesaurus Term: Environmental impact analysis; Subject Term: Government agencies -- United States; Subject Term: Decision making in environmental policy -- United States; Subject Term: Decision making ; Company/Entity: United States. National Environmental Policy Act of 1969; Number of Pages: 12p; Document Type: Article
L3 - 10.1017/S1466046614000295
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=100871421&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Heeszel, David S.
AU - Walter, Fabian
AU - Kilb, Deborah L.
T1 - Humming glaciers.
JO - Geology
JF - Geology
Y1 - 2014/12//
VL - 42
IS - 12
M3 - Article
SP - 1099
EP - 1102
SN - 00917613
AB - Mountain glaciers represent one of the largest repositories of fresh water in alpine regions globally. However, little is known about the processes by which water moves through these systems. Analysis of data from a deployment of seismometers located near an ice marginal lake in the Swiss Alps reveals, for the first time, that harmonic tremor occurs within mountain glaciers and that individual icequakes at the glacier base can exhibit harmonic properties. These observations suggest that there is a complex network of fluid-induced fracture processes at the glacier base. Modeling changes in the observed harmonic frequencies indicates that the spectral characteristics of seismic data can provide important information about hydraulic fracture geometry and fluid pressure at depth, leading to important insights into subglacial hydrologic processes. Future modeling of these processes may lead to improved glacial outburst flood hazard predictions. [ABSTRACT FROM AUTHOR]
AB - Copyright of Geology is the property of Geological Society of America and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - ALPINE glaciers
KW - RESEARCH
KW - SEISMOMETERS
KW - FLOODS
KW - HYDRAULIC fracturing
KW - ALPS, Swiss (Switzerland)
N1 - Accession Number: 99716653; Heeszel, David S. 1,2; Email Address: david.heeszel@nrc.gov Walter, Fabian 3,4 Kilb, Deborah L. 1; Affiliation: 1: Scripps Institution of Oceanography, University of California-San Diego, 9500 Gilman Drive, MC 0225, La Jolla, California 92093, USA 2: U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, USA 3: Institut des Sciences de la Terre, Université de Grenoble I, CNRS, BP 53, F-38041 Grenoble, France 4: Laboratory of Hydraulics, Hydrology and Glaciology (VAW), ETH Zurich, 8093 Zurich, Switzerland; Source Info: Dec2014, Vol. 42 Issue 12, p1099; Subject Term: ALPINE glaciers; Subject Term: RESEARCH; Subject Term: SEISMOMETERS; Subject Term: FLOODS; Subject Term: HYDRAULIC fracturing; Subject Term: ALPS, Swiss (Switzerland); NAICS/Industry Codes: 334519 Other Measuring and Controlling Device Manufacturing; Number of Pages: 4p; Illustrations: 2 Graphs, 1 Map; Document Type: Article
L3 - 10.1130/G35994.1
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=99716653&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - E D Dickson
AU - D M Hamby
T1 - Cloud immersion building shielding factors for US residential structures.
JO - Journal of Radiological Protection
JF - Journal of Radiological Protection
Y1 - 2014/12//
VL - 34
IS - 4
M3 - Article
SP - 1
EP - 1
SN - 09524746
AB - This paper presents validated building shielding factors designed for contemporary US housing-stock under an idealized, yet realistic, exposure scenario within a semi-infinite cloud of radioactive material. The building shielding factors are intended for use in emergency planning and level three probabilistic risk assessments for a variety of postulated radiological events in which a realistic assessment is necessary to better understand the potential risks for accident mitigation and emergency response planning. Factors are calculated from detailed computational housing-units models using the general-purpose Monte Carlo N-Particle computational code, MCNP5, and are benchmarked from a series of narrow- and broad-beam measurements analyzing the shielding effectiveness of ten common general-purpose construction materials and ten shielding models representing the primary weather barriers (walls and roofs) of likely US housing-stock. Each model was designed to scale based on common residential construction practices and include, to the extent practical, all structurally significant components important for shielding against ionizing radiation. Calculations were performed for floor-specific locations as well as for computing a weighted-average representative building shielding factor for single- and multi-story detached homes, both with and without basement, as well for single-wide manufactured housing-units. [ABSTRACT FROM AUTHOR]
AB - Copyright of Journal of Radiological Protection is the property of IOP Publishing and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radioactivity -- Safety measures
KW - Building
KW - Shielding (Radiation)
KW - House construction -- Environmental aspects
KW - Building -- Safety measures
N1 - Accession Number: 99768007; E D Dickson 1; Email Address: elijah.dickson@gmail.com; D M Hamby 2; Email Address: david.hamby@oregonstate.edu; Affiliations: 1: United States Nuclear Regulatory Commission, Rockville, USA; 2: Department of Nuclear Engineering and Radiation Health Physics, Oregon State University, Corvallis, USA; Issue Info: Dec2014, Vol. 34 Issue 4, p1; Thesaurus Term: Radioactivity -- Safety measures; Thesaurus Term: Building; Subject Term: Shielding (Radiation); Subject Term: House construction -- Environmental aspects; Subject Term: Building -- Safety measures; NAICS/Industry Codes: 236117 New Housing For-Sale Builders; NAICS/Industry Codes: 236115 New Single-Family Housing Construction (except For-Sale Builders); NAICS/Industry Codes: 236110 Residential building construction; Number of Pages: 1p; Document Type: Article
L3 - 10.1088/0952-4746/34/4/853
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=99768007&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Pachepsky, Yakov A.
AU - Guber, Andrey K.
AU - Yakirevich, Alexander M.
AU - McKee, Lynn
AU - Cady, Ralph E.
AU - Nicholson, Thomas J.
T1 - Scaling and Pedotransfer in Numerical Simulations of Flow and Transport in Soils.
JO - Vadose Zone Journal
JF - Vadose Zone Journal
Y1 - 2014/12//
VL - 13
IS - 12
M3 - Article
SP - 2
EP - 2
AB - We used hydraulic conductivity pedotransfer functions and power law upscaling in simulations of a tracer transport in soil. Using only pedotransfer functions caused a substantial difference between measured and simulated concentrations. After pedotransfer estimates were upscaled, the accuracy of simulations was the same as that of the calibrated model. Flow and transport parameters of soils in numerical simulations need to be defined at the support scale of computational grid cells. Such support scale can substantially differ from the support scale in laboratory or field measurements of flow and transport parameters. The scale dependence of flow and transport parameters essentially precludes the direct use of measured or pedotransfer-estimated parameter values in numerical simulations. The hypothesis of this work was that a support-based scaling law can be introduced that can convert pedotransfer-estimated saturated hydraulic conductivity values into values to be used over grid cells for finite-element-based simulations of water flow and tracer transport in variably saturated soils. A 4-month-long experiment was conducted at the USDA--ARS experimental site where Cl¯ as a tracer was applied with a pulse of irrigation water and its transport in groundwater and variably saturated shallow coarse-textured soils was monitored in two rows of wells on a daily basis. The HYDRUS-3D software was used to set and calibrate the Richards model for flow simulations and the convective--dispersive equation for transport simulations. Saturated hydraulic conductivity values were estimated with class pedotransfer functions derived from the USDA database containing results of about 1000 measurements in soils of different textures and bulk densities. A power law scaling for the saturated hydraulic conductivity was suggested based on literature data. When only two parameters of the scaling law rather than nine values of hydraulic conductivity from nine soil materials were calibrated, using the scaled saturated hydraulic conductivity values resulted in an accuracy of simulations that was similar to the accuracy of the calibrated model results. Upscaling of pedotransfer-estimated saturated hydraulic conductivities can provide reasonable estimates for numerical flow and transport modeling in variably saturated soils. [ABSTRACT FROM AUTHOR]
AB - Copyright of Vadose Zone Journal is the property of American Society of Agronomy and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RESEARCH
KW - Simulation methods & models
KW - Solifluction
KW - Soil permeability
KW - Soil permeability -- Measurement
KW - Finite element method
N1 - Accession Number: 102021535; Pachepsky, Yakov A. 1; Email Address: yakov.pachepsky@ars.usda.gov; Guber, Andrey K. 2; Yakirevich, Alexander M. 3; McKee, Lynn 1; Cady, Ralph E. 4; Nicholson, Thomas J. 4; Affiliations: 1: USDA-ARS, Beltsville Agricultural Research Center, 10300 Baltimore Ave., Beltsville, MD 20705; 2: Dep. of Plant, Soil and Microbial Sciences, Michigan State Univ., East Lansing, MI 48824; 3: Dep. of Environmental Hydrology and Microbiology, Jacob Blaustein Inst., Desert Research, Ben-Gurion Univ. of the Negev, Israel; 4: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Rockville, MD 20852; Issue Info: Dec2014, Vol. 13 Issue 12, p2; Thesaurus Term: RESEARCH; Thesaurus Term: Simulation methods & models; Subject Term: Solifluction; Subject Term: Soil permeability; Subject Term: Soil permeability -- Measurement; Subject Term: Finite element method; Number of Pages: 1p; Document Type: Article
L3 - 10.2136/vzj2014.02.0020
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=102021535&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Akstulewicz, Frank
T1 - A Global Perspective.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2015/01//Jan/Feb2015
VL - 33
IS - 1
M3 - Opinion
SP - 24
EP - 29
PB - Presidents & Prime Ministers
SN - 08922055
AB - The author comments on nuclear regulations and requirements established by the U.S. Nuclear Regulatory Commission (NRC). Topics discussed include how NRC cooperates with international community, the ITAAC ( Inspections, Tests, Analyses & Acceptance Criteria) related challenges associated with Vogtle and Summer nuclear licensees, and role played by Multinational Design Evaluation Program (MDEP) in the implementation of post-Fukushima, Japan nuclear accident modifications at nuclear plants.
KW - Nuclear power plants
KW - Fukushima Nuclear Accident, Fukushima, Japan, 2011
KW - Nuclear energy -- Government policy -- United States
KW - Nuclear energy -- International cooperation
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 101605368; Akstulewicz, Frank 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: Jan/Feb2015, Vol. 33 Issue 1, p24; Thesaurus Term: Nuclear power plants; Subject Term: Fukushima Nuclear Accident, Fukushima, Japan, 2011; Subject Term: Nuclear energy -- Government policy -- United States; Subject Term: Nuclear energy -- International cooperation ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 2p; Document Type: Opinion
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - KANATAS, CATHERINE E.
AU - SMITH, MAXWELL C.
T1 - Reexamining What We Stand to Lose: A Look at Reinitiated Consultation Under the Endangered Species Act.
JO - Pace Environmental Law Review
JF - Pace Environmental Law Review
Y1 - 2015///Winter2015
VL - 32
IS - 1
M3 - Article
SP - 225
EP - 284
PB - Pace Environmental Law Review
SN - 07386206
AB - The article discusses reinitiation of consultation under the Endangered Species Act (ESA) in the U.S. Topic discussed includes the role of reinitiated consultation in enlisting of a species under the ESA within the U.S. Congress' statutory framework, procedure for listing a species under the ESA, and decisions of different courts related to reinitiated consultation such as those of the U.S. Supreme Court in the case National Ass'n of Home Builders v. Defenders of Wildlife and of a circuit court in the case Strahan v. Coxe.
KW - Endangered species listing
KW - Endangered species -- Law & legislation -- United States
KW - Circuit courts -- United States
KW - National Association of Home Builders v. Defenders of Wildlife (Supreme Court case)
KW - Judgments (Law)
KW - United States. Endangered Species Act of 1973
KW - United States. Supreme Court
N1 - Accession Number: 109268272; KANATAS, CATHERINE E. 1; SMITH, MAXWELL C. 2; Affiliations: 1: Attorney, United States Nuclear Regulatory Commission (NRC); 2: Attorney, NRC; Issue Info: Winter2015, Vol. 32 Issue 1, p225; Thesaurus Term: Endangered species listing; Subject Term: Endangered species -- Law & legislation -- United States; Subject Term: Circuit courts -- United States; Subject Term: National Association of Home Builders v. Defenders of Wildlife (Supreme Court case); Subject Term: Judgments (Law) ; Company/Entity: United States. Endangered Species Act of 1973 ; Company/Entity: United States. Supreme Court; Number of Pages: 60p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Dewji, S.
AU - Bellamy, M.
AU - Hertel, N.
AU - Leggett, R.
AU - Sherbini, S.
AU - Saba, M.
AU - Eckerman, K.
T1 - Estimated dose rates to members of the public from external exposure to patients with 131I thyroid treatment.
JO - Medical Physics
JF - Medical Physics
Y1 - 2015/04//
VL - 42
IS - 4
M3 - Article
SP - 1851
EP - 1857
SN - 00942405
AB - Purpose: Estimated dose rates that may result from exposure to patients who had been administered iodine-131 (131I) as part of medical therapy were calculated. These effective dose rate estimates were compared with simplified assumptions under United States Nuclear Regulatory Commission Regulatory Guide 8.39, which does not consider body tissue attenuation nor time-dependent redistribution and excretion of the administered 131I. Methods: Dose rates were estimated for members of the public potentially exposed to external irradiation from patients recently treated with 131I. Tissue attenuation and iodine biokinetics were considered in the patient in a larger comprehensive effort to improve external dose rate estimates. The external dose rate estimates are based on Monte Carlo simulations using the Phantom with Movable Arms and Legs (PIMAL), previously developed by Oak Ridge National Laboratory and the United States Nuclear Regulatory Commission. PIMAL was employed to model the relative positions of the 131I patient and members of the public in three exposure scenarios: (1) traveling on a bus in a total of six seated or standing permutations, (2) two nursing home cases where a caregiver is seated at 30 cm from the patient's bedside and a nursing home resident seated 250 cm away from the patient in an adjacent bed, and (3) two hotel cases where the patient and a guest are in adjacent rooms with beds on opposite sides of the common wall, with the patient and guest both in bed and either seated back-to-back or lying head to head. The biokinetic model predictions of the retention and distribution of 131I in the patient assumed a single voiding of urinary bladder contents that occurred during the trip at 2, 4, or 8 h after 131I administration for the public transportation cases, continuous first-order voiding for the nursing home cases, and regular periodic voiding at 4, 8, or 12 h after administration for the hotel room cases. Organ specific activities of 131I in the thyroid, bladder, and combined remaining tissues were calculated as a function of time after administration. Exposures to members of the public were considered for 131I patients with normal thyroid uptake (peak thyroid uptake of ~27% of administered 131I), differentiated thyroid cancer (DTC, 5% uptake), and hyperthyroidism (80% uptake). Results: The scenario with the patient seated behind the member of the public yielded the highest dose rate estimate of seated public transportation exposure cases. The dose rate to the adjacent room guest was highest for the exposure scenario in which the hotel guest and patient are seated by a factor of ~4 for the normal and differentiated thyroid cancer uptake cases and by a factor of ~3 for the hyperthyroid case. Conclusions: It was determined that for all modeled cases, the DTC case yielded the lowest external dose rates, whereas the hyperthyroid case yielded the highest dose rates. In estimating external dose to members of the public from patients with 131I therapy, consideration must be given to (patient- and case-specific) administered 131I activities and duration of exposure for a more complete estimate. The method implemented here included a detailed calculation model, which provides a means to determine dose rate estimates for a range of scenarios. The method was demonstrated for variations of three scenarios, showing how dose rates are expected to vary with uptake, voiding pattern, and patient location. [ABSTRACT FROM AUTHOR]
AB - Copyright of Medical Physics is the property of American Association of Physicists in Medicine and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RADIATION dosimetry
KW - THYROID diseases
KW - PATIENTS
KW - IODINE -- Therapeutic use
KW - ADMINISTRATION of drugs
KW - 131I
KW - differentiated thyroid cancer
KW - hyperthyroidism
KW - public risk
KW - thyroid
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 101903541; Dewji, S. 1; Email Address: dewjisa@ornl.gov Bellamy, M. 1,2 Hertel, N. 1 Leggett, R. 1 Sherbini, S. 3 Saba, M. 3 Eckerman, K. 1; Affiliation: 1: Oak Ridge National Laboratory, 1 Bethel Valley Road, MS-6335, Oak Ridge, Tennessee 37831 2: Georgia Institute of Technology, 770 State Street, Atlanta, Georgia 30332-0745 3: United States Nuclear Regulatory Commission, Washington, DC 20555-0001; Source Info: Apr2015, Vol. 42 Issue 4, p1851; Subject Term: RADIATION dosimetry; Subject Term: THYROID diseases; Subject Term: PATIENTS; Subject Term: IODINE -- Therapeutic use; Subject Term: ADMINISTRATION of drugs; Author-Supplied Keyword: 131I; Author-Supplied Keyword: differentiated thyroid cancer; Author-Supplied Keyword: hyperthyroidism; Author-Supplied Keyword: public risk; Author-Supplied Keyword: thyroid; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 541380 Testing Laboratories; Number of Pages: 7p; Document Type: Article
L3 - 10.1118/1.4915084
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DP - EBSCOhost
DB - aph
ER -
TY - GEN
AU - Davis, Jack
AU - Bowen, Jeremy
T1 - Fukushima Lessons-Learned.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2015/05//May/Jun2015
VL - 33
IS - 3
M3 - Interview
SP - 28
EP - 31
PB - Presidents & Prime Ministers
SN - 08922055
AB - An interview is presented with Jack Davis, Director of the Japan Lessons Learned Division (JLLD) in the U.S. Nuclear Regulatory Council's Office of Nuclear Reactor Regulation & Jeremy Bowen, Associate Director for Program Management, Policy, and Support in the Office of Nuclear Reactor Regulation's JLLD. Topics include mitigation strategies for nuclear power plant accidents; strategy to keep the plant staffed in emergency; and lessons learned from the 2011 Fukushima plant accident in Japan.
KW - Nuclear power plants -- Accidents
KW - Fukushima Nuclear Accident, Fukushima, Japan, 2011
KW - U.S. Nuclear Regulatory Commission
KW - Davis, Jack -- Interviews
KW - Bowen, Jeremy -- Interviews
N1 - Accession Number: 103604066; Davis, Jack 1; Bowen, Jeremy; Affiliations: 1: Director, Japan Lessons Learned Division, NRC's Office of Nuclear Reactor Regulation; Issue Info: May/Jun2015, Vol. 33 Issue 3, p28; Thesaurus Term: Nuclear power plants -- Accidents; Subject Term: Fukushima Nuclear Accident, Fukushima, Japan, 2011 ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; People: Davis, Jack -- Interviews; People: Bowen, Jeremy -- Interviews; Number of Pages: 4p; Document Type: Interview
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - E D Dickson
AU - D M Hamby
AU - K F Eckerman
T1 - Contaminant deposition building shielding factors for US residential structures.
JO - Journal of Radiological Protection
JF - Journal of Radiological Protection
Y1 - 2015/06//
VL - 35
IS - 2
M3 - Article
SP - 1
EP - 1
SN - 09524746
AB - This paper presents validated building shielding factors designed for contemporary US housing-stock under an idealized, yet realistic, exposure scenario from contaminant deposition on the roof and surrounding surfaces. The building shielding factors are intended for use in emergency planning and level three probabilistic risk assessments for a variety of postulated radiological events in which a realistic assessment is necessary to better understand the potential risks for accident mitigation and emergency response planning. Factors are calculated from detailed computational housing-units models using the general-purpose Monte Carlo N-Particle computational code, MCNP5, and are benchmarked from a series of narrow- and broad-beam measurements analyzing the shielding effectiveness of ten common general-purpose construction materials and ten shielding models representing the primary weather barriers (walls and roofs) of likely US housing-stock. Each model was designed to scale based on common residential construction practices and include, to the extent practical, all structurally significant components important for shielding against ionizing radiation. Calculations were performed for floor-specific locations from contaminant deposition on the roof and surrounding ground as well as for computing a weighted-average representative building shielding factor for single- and multi-story detached homes, both with and without basement as well for single-wide manufactured housing-unit. [ABSTRACT FROM AUTHOR]
AB - Copyright of Journal of Radiological Protection is the property of IOP Publishing and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Emergency management
KW - Risk assessment
KW - Radioactive contamination
KW - Shielding (Radiation)
KW - Dwellings -- Design & construction
N1 - Accession Number: 103240052; E D Dickson 1; Email Address: elijah.dickson@gmail.com; D M Hamby 2; Email Address: david.hamby@oregonstate.edu; K F Eckerman 3; Affiliations: 1: United States Nuclear Regulatory Commission, Rockville, DC 20555-0001, USA; 2: Department of Nuclear Engineering and Radiation Health Physics, Oregon State University, Corvallis, OR 97331, USA; 3: Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA; Issue Info: Jun2015, Vol. 35 Issue 2, p1; Thesaurus Term: Emergency management; Thesaurus Term: Risk assessment; Subject Term: Radioactive contamination; Subject Term: Shielding (Radiation); Subject Term: Dwellings -- Design & construction; NAICS/Industry Codes: 236110 Residential building construction; NAICS/Industry Codes: 541310 Architectural Services; NAICS/Industry Codes: 238390 Other Building Finishing Contractors; NAICS/Industry Codes: 913190 Other municipal protective services; NAICS/Industry Codes: 922190 Other Justice, Public Order, and Safety Activities; NAICS/Industry Codes: 912190 Other provincial protective services; NAICS/Industry Codes: 911290 Other federal protective services; NAICS/Industry Codes: 624230 Emergency and Other Relief Services; Number of Pages: 1p; Document Type: Article
L3 - 10.1088/0952-4746/35/2/317
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Kaizer, Joshua S.
AU - Heller, A. Kevin
AU - Oberkampf, William L.
T1 - Scientific computer simulation review.
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2015/06//
VL - 138
M3 - Article
SP - 210
EP - 218
SN - 09518320
AB - Before the results of a scientific computer simulation are used for any purpose, it should be determined if those results can be trusted. Answering that question of trust is the domain of scientific computer simulation review. There is limited literature that focuses on simulation review, and most is specific to the review of a particular type of simulation. This work is intended to provide a foundation for a common understanding of simulation review. This is accomplished through three contributions. First, scientific computer simulation review is formally defined. This definition identifies the scope of simulation review and provides the boundaries of the review process. Second, maturity assessment theory is developed. This development clarifies the concepts of maturity criteria, maturity assessment sets, and maturity assessment frameworks, which are essential for performing simulation review. Finally, simulation review is described as the application of a maturity assessment framework. This is illustrated through evaluating a simulation review performed by the U.S. Nuclear Regulatory Commission. In making these contributions, this work provides a means for a more objective assessment of a simulation’s trustworthiness and takes the next step in establishing scientific computer simulation review as its own field. [ABSTRACT FROM AUTHOR]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - COMPUTER simulation
KW - RELIABILITY (Engineering)
KW - PREDICTION models
KW - BAYESIAN analysis
KW - Code review
KW - Maturity assessment
KW - Maturity framework
KW - Measurement of simulation trustworthiness
KW - Requirements for simulation trustworthiness
KW - Scientific computer simulation review
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 101931508; Kaizer, Joshua S. 1; Email Address: Joshua.Kaizer@nrc.gov Heller, A. Kevin 1; Email Address: Kevin.Heller@nrc.gov Oberkampf, William L. 1; Email Address: wloconsulting@gmail.com; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Source Info: Jun2015, Vol. 138, p210; Subject Term: COMPUTER simulation; Subject Term: RELIABILITY (Engineering); Subject Term: PREDICTION models; Subject Term: BAYESIAN analysis; Author-Supplied Keyword: Code review; Author-Supplied Keyword: Maturity assessment; Author-Supplied Keyword: Maturity framework; Author-Supplied Keyword: Measurement of simulation trustworthiness; Author-Supplied Keyword: Requirements for simulation trustworthiness; Author-Supplied Keyword: Scientific computer simulation review; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.ress.2015.01.020
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=101931508&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Cool, D.A.
T1 - Review of the ICRP system of protection: the approach to existing exposure situations.
JO - Annals of the ICRP
JF - Annals of the ICRP
Y1 - 2015/06/02/Jun2015 Supplement 1
VL - 44
M3 - Article
SP - 179
EP - 187
SN - 01466453
AB - The International Commission on Radiological Protection (ICRP) system of protection consists of existing, planned, and emergency exposure situations. With the 2007 Recommendations in ICRP Publication 103, a coherent approach has been established that emphasises the optimisation of protection with appropriate constraints or reference levels in each exposure situation. Existing exposure situations pose unique challenges because the source of exposure already exists, and it may not always be possible to control the source directly. This is the case for naturally occurring sources, which are ubiquitous in the environment and vary widely in the magnitude of exposures that may be received by individuals. Decisions on protection strategies must consider a graded, pragmatic, and flexible approach for dealing with exposure of members of the public, and those that may be occupationally exposed while working with naturally occurring sources. Although limits are not applicable, aspects of the management approach for planned exposure situations may be appropriate, depending upon the magnitude of exposures. [ABSTRACT FROM AUTHOR]
AB - Copyright of Annals of the ICRP is the property of Sage Publications Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RADIATION -- Safety measures
KW - RADIATION exposure
KW - EMERGENCY management
KW - RADIATION -- Environmental aspects
KW - OCCUPATIONAL radiation protection
KW - DECISION making
KW - Existing exposure situations
KW - NORM
KW - System of protection
N1 - Accession Number: 102978134; Cool, D.A. 1; Email Address: Donald.Cool@nrc.gov; Affiliation: 1: US Nuclear Regulatory Commission, Washington DC, VA 20555, USA; Source Info: Jun2015 Supplement 1, Vol. 44, p179; Subject Term: RADIATION -- Safety measures; Subject Term: RADIATION exposure; Subject Term: EMERGENCY management; Subject Term: RADIATION -- Environmental aspects; Subject Term: OCCUPATIONAL radiation protection; Subject Term: DECISION making; Author-Supplied Keyword: Existing exposure situations; Author-Supplied Keyword: NORM; Author-Supplied Keyword: System of protection; NAICS/Industry Codes: 911290 Other federal protective services; NAICS/Industry Codes: 912190 Other provincial protective services; NAICS/Industry Codes: 913190 Other municipal protective services; NAICS/Industry Codes: 624230 Emergency and Other Relief Services; NAICS/Industry Codes: 922190 Other Justice, Public Order, and Safety Activities; Number of Pages: 9p; Document Type: Article
L3 - 10.1177/0146645315572294
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=102978134&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Wellock, Thomas R.
T1 - Downwind: A People's History of the Nuclear West.
JO - Journal of American History
JF - Journal of American History
Y1 - 2015/09//
VL - 102
IS - 2
M3 - Book Review
SP - 603
EP - 604
PB - Oxford University Press / USA
SN - 00218723
KW - NUCLEAR weapons testing -- Environmental aspects
KW - NUCLEAR weapons testing victims
KW - NONFICTION
KW - FOX, Sarah Alisabeth
KW - DOWNWIND: A People's History of the Nuclear West (Book)
N1 - Accession Number: 109519654; Wellock, Thomas R. 1; Affiliation: 1: U.S. Nuclear Regulatory Commission Rockville, Maryland; Source Info: Sep2015, Vol. 102 Issue 2, p603; Subject Term: NUCLEAR weapons testing -- Environmental aspects; Subject Term: NUCLEAR weapons testing victims; Subject Term: NONFICTION; Reviews & Products: DOWNWIND: A People's History of the Nuclear West (Book); People: FOX, Sarah Alisabeth; Number of Pages: 2p; Document Type: Book Review
L3 - 10.1093/jahist/jav470
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Raynaud, Patrick A.C.
AU - Einziger, Robert E.
T1 - Cladding stress during extended storage of high burnup spent nuclear fuel.
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2015/09//
VL - 464
M3 - Article
SP - 304
EP - 312
SN - 00223115
AB - In an effort to assess the potential for low temperature creep and delayed hydride cracking failures in high burnup spent fuel cladding during extended dry storage, the U.S. NRC analytical fuel performance tools were used to predict cladding stress during a 300 year dry storage period for UO 2 fuel burned up to 65 GWd/MTU. Fuel swelling correlations were developed and used along with decay gas production and release fractions to produce circumferential average cladding stress predictions with the FRAPCON-3.5 fuel performance code. The resulting stresses did not result in cladding creep failures. The maximum creep strains accumulated were on the order of 0.54–1.04%, but creep failures are not expected below at least 2% strain. The potential for delayed hydride cracking was assessed by calculating the critical flaw size required to trigger this failure mechanism. The critical flaw size far exceeded any realistic flaw expected in spent fuel at end of reactor life. [ABSTRACT FROM AUTHOR]
AB - Copyright of Journal of Nuclear Materials is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NUCLEAR fuel claddings
KW - BURNUP (Nuclear chemistry)
KW - SPENT reactor fuels
KW - CREEP (Materials)
KW - HYDRIDES
N1 - Accession Number: 108505605; Raynaud, Patrick A.C. 1; Email Address: Patrick.raynaud@nrc.gov Einziger, Robert E. 1; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Sep2015, Vol. 464, p304; Subject Term: NUCLEAR fuel claddings; Subject Term: BURNUP (Nuclear chemistry); Subject Term: SPENT reactor fuels; Subject Term: CREEP (Materials); Subject Term: HYDRIDES; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.jnucmat.2015.05.008
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Ostendorff, William C.
AU - Bloomer, Tamara E.
T1 - U.S. regulatory perspectives on the back end of the fuel cycle: EUROSAFE 2013 proceeding.
JO - Progress in Nuclear Energy
JF - Progress in Nuclear Energy
Y1 - 2015/09//
VL - 84
M3 - Article
SP - 74
EP - 78
SN - 01491970
AB - For the United States Nuclear Regulatory Commission and the reactor licensees it regulates, there are a number of contemporary issues associated with the back end of the fuel cycle including, the agency's revision to its “Waste Confidence” decision and the path-forward for high-level waste disposal. Additionally, the 2012 Blue Ribbon Commission on America's Nuclear Future recommendations, the future of reprocessing, consolidated interim spent fuel storage, and maintaining technical competence within the NRC in challenging budgetary conditions are addressed. I conclude that there is confidence in the feasibility of safe storage of spent nuclear fuel following the licensed operational life of a reactor and any change in high-level waste policy will require Congressional action to amend the Nuclear Waste Policy Act. [ABSTRACT FROM AUTHOR]
AB - Copyright of Progress in Nuclear Energy is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Sewage disposal
KW - Nuclear fuels
KW - Radioactive wastes
KW - Fuel cycle
KW - Decision making
KW - 2012 Blue Ribbon Commission on America's nuclear future
KW - High-level waste disposal
KW - Storage of spent nuclear fuel
KW - Waste confidence
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 109089632; Ostendorff, William C. 1; Email Address: William.Ostenforff@NRC.GOV; Bloomer, Tamara E. 1; Email Address: Tamara.Bloomer@NRC.GOV; Affiliations: 1: United States Nuclear Regulatory Commission, Washington D.C. 20555, USA; Issue Info: Sep2015, Vol. 84, p74; Thesaurus Term: Sewage disposal; Thesaurus Term: Nuclear fuels; Thesaurus Term: Radioactive wastes; Subject Term: Fuel cycle; Subject Term: Decision making; Author-Supplied Keyword: 2012 Blue Ribbon Commission on America's nuclear future; Author-Supplied Keyword: High-level waste disposal; Author-Supplied Keyword: Storage of spent nuclear fuel; Author-Supplied Keyword: Waste confidence ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562212 Solid Waste Landfill; Number of Pages: 5p; Document Type: Article
L3 - 10.1016/j.pnucene.2015.02.001
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=109089632&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Chen, Y.
AU - Alexandreanu, B.
AU - Chen, W.-Y.
AU - Natesan, K.
AU - Li, Z.
AU - Yang, Y.
AU - Rao, A.S.
T1 - Cracking behavior of thermally aged and irradiated CF-8 cast austenitic stainless steel.
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
Y1 - 2015/11//
VL - 466
M3 - Article
SP - 560
EP - 568
SN - 00223115
AB - To assess the combined effect of thermal aging and neutron irradiation on the cracking behavior of CF-8 cast austenitic stainless steel, crack growth rate (CGR) and fracture toughness J-R curve tests were carried out on compact-tension specimens in high-purity water with low dissolved oxygen. Both unaged and thermally aged specimens were irradiated at ∼320 °C to 0.08 dpa. Thermal aging at 400 °C for 10,000 h apparently had no effect on the corrosion fatigue and stress corrosion cracking behavior in the test environment. The cracking susceptibility of CF-8 was not elevated significantly by neutron irradiation at 0.08 dpa. Transgranular cleavage-like cracking was the main fracture mode during the CGR tests, and a brittle morphology of delta ferrite was often seen on the fracture surfaces at the end of CGR tests. The fracture toughness J-R curve tests showed that both thermal aging and neutron irradiation can induce significant embrittlement. The loss of fracture toughness due to neutron irradiation was more pronounced in the unaged than aged specimens. After neutron irradiation, the fracture toughness values of the unaged and aged specimens were reduced to a similar level. G-phase precipitates were observed in the aged and irradiated specimens with or without prior aging. The similar microstructural changes resulting from thermal aging and irradiation suggest a common microstructural mechanism of inducing embrittlement in CF-8. [ABSTRACT FROM AUTHOR]
AB - Copyright of Journal of Nuclear Materials is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - METALS -- Fracture
KW - MATERIALS -- Deterioration
KW - IRRADIATION
KW - CASTING (Manufacturing process)
KW - AUSTENITIC stainless steel
KW - FRACTURE mechanics
KW - FRACTURE toughness
KW - Cast austenitic stainless steel
KW - Environmentally assisted cracking
KW - Irradiation embrittlement
KW - Thermal aging embrittlement
N1 - Accession Number: 110657642; Chen, Y. 1; Email Address: Yiren_Chen@anl.gov Alexandreanu, B. 1 Chen, W.-Y. 1 Natesan, K. 1 Li, Z. 2 Yang, Y. 2 Rao, A.S. 3; Affiliation: 1: Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL 60439, USA 2: University of Florida, Gainesville, FL 32611, USA 3: US Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD 20852, USA; Source Info: Nov2015, Vol. 466, p560; Subject Term: METALS -- Fracture; Subject Term: MATERIALS -- Deterioration; Subject Term: IRRADIATION; Subject Term: CASTING (Manufacturing process); Subject Term: AUSTENITIC stainless steel; Subject Term: FRACTURE mechanics; Subject Term: FRACTURE toughness; Author-Supplied Keyword: Cast austenitic stainless steel; Author-Supplied Keyword: Environmentally assisted cracking; Author-Supplied Keyword: Irradiation embrittlement; Author-Supplied Keyword: Thermal aging embrittlement; NAICS/Industry Codes: 334517 Irradiation Apparatus Manufacturing; Number of Pages: 9p; Document Type: Article
L3 - 10.1016/j.jnucmat.2015.08.047
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=110657642&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Johnson, James J.
AU - Ake, Jon P.
AU - Maslenikov, Oleg R.
AU - Kenneally, Roger M.
T1 - Soil–structure interaction analyses to locate nuclear power plant free-field seismic instrumentation.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2015/12/15/
VL - 295
M3 - Article
SP - 688
EP - 699
SN - 00295493
AB - The recorded earthquake ground motion at the nuclear power plant site is needed for several purposes. US Nuclear Regulatory Commission (NRC) Regulatory Guide 1.12, Nuclear Power Plant Instrumentation for Earthquakes , NRC (1997a), describes acceptable instrumentation to meet the requirements in NRC's regulations pertaining to earthquake engineering criteria for nuclear power plants. The ground motion data recorded by the free-field seismic instrumentation are used to compare the actual earthquake motion at the site with the design input motion. The result of the comparison determines if the Operating Basis Earthquake ground motion (OBE) has been exceeded and plant shutdown is required per the guidance in NRC Regulatory Guide 1.166, Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions , NRC (1979b). The free-field is defined as a location on the ground surface or in the site soil column that is sufficiently distant from the site structures to be essentially unaffected by the vibration of the site structures. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SOIL-structure interaction
KW - SEISMOLOGY
KW - NUCLEAR power plants
KW - EARTHQUAKE engineering
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 111974919; Johnson, James J. 1; Email Address: jasjjoh@aol.com Ake, Jon P. 2 Maslenikov, Oleg R. 1 Kenneally, Roger M. 3; Affiliation: 1: James J. Johnson and Associates, Alamo, CA, USA 2: US Nuclear Regulatory Commission, Washington, DC, USA 3: Consultant, Seminole, FL, USA; Source Info: Dec2015, Vol. 295, p688; Subject Term: SOIL-structure interaction; Subject Term: SEISMOLOGY; Subject Term: NUCLEAR power plants; Subject Term: EARTHQUAKE engineering; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 12p; Document Type: Article
L3 - 10.1016/j.nucengdes.2015.09.003
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Jones, Christopher A.
AU - Dameron, Robert
AU - Sircar, Madhumita
T1 - Improving the state of the art in FEM analysis of PCCVs with bonded and unbonded prestress tendons.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2015/12/15/
VL - 295
M3 - Article
SP - 782
EP - 788
SN - 00295493
AB - In order to assess the structural performance of grouted prestressing systems in nuclear power containment vessels, a full containment vessel was modeled using the finite element program, ABAQUS. Both bonded (grouted) and unbonded (ungrouted) prestressing systems were modeled. Prior to simulation of grouting, both models were identical, with the prestressing stages modeled explicitly, and friction represented along the tendons. The results indicate higher peak stresses and strains in the bonded model since the tendon system is not permitted to slip and redistribute forces as the vessel deforms. Correspondingly, it is noted that the analysis predicts failure of the vessel at a lower internal pressure in the case of the bonded system. This work is an extension of a collaborative study of finite element analysis (FEA) of prestressed concrete containment vessels (PCCVs) sponsored by the United States Nuclear Regulatory Commission (USNRC) and the Atomic Energy Regulatory Board (AERB) of India. Particular emphasis was placed on advancing the state of the art in modeling tendons ( Akin et al., 2013a; Heitman et al., 2014 ). [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - FINITE element method
KW - PRESTRESSED construction
KW - STRUCTURAL engineering
KW - NUCLEAR energy
KW - FISSION reactor containment
N1 - Accession Number: 111974962; Jones, Christopher A. 1; Email Address: cajone@sandia.gov Dameron, Robert 2; Email Address: rdameron@moffattnichol.com Sircar, Madhumita 3; Email Address: Madhumita.sircar@nrc.gov; Affiliation: 1: Sandia National Laboratories, PO Box 5800, MS 0744, Albuquerque, NM 87125-0744, United States 2: Moffatt and Nichol, 1660 Hotel Cir N, San Diego, CA 92108, United States 3: U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, United States; Source Info: Dec2015, Vol. 295, p782; Subject Term: FINITE element method; Subject Term: PRESTRESSED construction; Subject Term: STRUCTURAL engineering; Subject Term: NUCLEAR energy; Subject Term: FISSION reactor containment; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 7p; Document Type: Article
L3 - 10.1016/j.nucengdes.2015.07.023
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=111974962&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Desai, Sachin1
AU - Schroeder, Kathleen2
T1 - U.S. NUCLEAR FOREIGN OWNERSHIP POLICY READY FOR A REFRESHED INTERPRETATION.
JO - Energy Law Journal
JF - Energy Law Journal
J1 - Energy Law Journal
PY - 2016/01//
Y1 - 2016/01//
VL - 37
IS - 1
CP - 1
M3 - Article
SP - 85
EP - 134
SN - 02709163
AB - While the United States remains the global leader in nuclear energy generation and technology, the nuclear energy industry is seeing explosive growth abroad. In the past several years, foreign nuclear companies have expressed interest in purchasing existing reactors and building new ones in the U.S. The Nuclear Regulatory Commission (NRC) is faced with the challenge of balancing competing goals: reducing carbon emissions through new, potentially safer technologies while complying with the Atomic Energy Act (AEA) restriction on foreign ownership of U.S. nuclear reactors. Recent actions have pushed the Commission to reassess this balance. This article proposes a path forward for the Commission to provide clarity in this area of law and to encourage investment in the U.S. nuclear sector. The Atomic Energy Act prohibits foreign "owned, controlled, or dominated" (FOCD) licensees from owning or operating nuclear reactors in the United States. This provision is inherently vague, especially as it applies to the prohibition of foreign ownership. As the Commission has discussed this issue, a split has emerged between those within the Commission interpreting the FOCD provision permissively, as allowing up to 100% foreign indirect ownership of U.S. reactors, and those reading it strictly, who would allow no more than 50% foreign ownership in any form. Besides the obvious deadlock this creates, it results in the Commission adopting a potentially inconsistent approach, which could be reversed by a reviewing court. This uncertainty will lead to future litigation and uncertainty amongst applicants, the public, and Atomic Safety and Licensing Boards tasked with deciding whether to permit foreign companies' purchase or construction of nuclear facilities in the United States. This article reviews recent trends in the global nuclear energy market as well as the legislative history of the AEA's FOCD provision, building off analyses performed by the NRC Staff and the Commission. It critiques the various positions taken by the Commissioners, and challenges each sides' legal arguments. The authors then propose that case law, legislative history, agency practice across the federal government, and a context-driven reading of the text of the FOCD provision under the Chevron doctrine can allow for 100% foreign indirect ownership of U.S. nuclear reactors. This interpretation of the FOCD provision does not conflict with the AEA's goal of ensuring national security. [ABSTRACT FROM AUTHOR]
KW - Foreign investments
KW - Nuclear energy -- Government policy -- United States
KW - Nuclear industry -- United States
KW - Carbon dioxide mitigation
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 115852748; Authors:Desai, Sachin 1; Schroeder, Kathleen 2; Affiliations: 1: Law clerk, Atomic Safety & Licensing Board Panel, U.S. Nuclear Regulatory Commission (NRC); 2: Attorney, Department of Energy General Counsel's Office for Civilian Nuclear Programs; Subject: Nuclear energy -- Government policy -- United States; Subject: Nuclear industry -- United States; Subject: U.S. Nuclear Regulatory Commission; Subject: Carbon dioxide mitigation; Subject: Foreign investments; Number of Pages: 50p; Court Cases: Chevron U.S.A. v. NRDC; Dole Food Co. v. Patrickson; Statute:Atomic Energy Act; Jurisdiction:United States; Record Type: Article
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DP - EBSCOhost
DB - lft
ER -
TY - JOUR
AU - Ekanem, Nsimah J.
AU - Mosleh, Ali
AU - Shen, Song-Hua
T1 - Phoenix – A model-based Human Reliability Analysis methodology: Qualitative Analysis Procedure.
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2016/01//
VL - 145
M3 - Article
SP - 301
EP - 315
SN - 09518320
AB - Phoenix method is an attempt to address various issues in the field of Human Reliability Analysis (HRA). Built on a cognitive human response model, Phoenix incorporates strong elements of current HRA good practices, leverages lessons learned from empirical studies, and takes advantage of the best features of existing and emerging HRA methods. Its original framework was introduced in previous publications. This paper reports on the completed methodology, summarizing the steps and techniques of its qualitative analysis phase. The methodology introduces the “Crew Response Tree” which provides a structure for capturing the context associated with Human Failure Events (HFEs), including errors of omission and commission. It also uses a team-centered version of the Information, Decision and Action cognitive model and “macro-cognitive” abstractions of crew behavior, as well as relevant findings from cognitive psychology literature and operating experience, to identify potential causes of failures and influencing factors during procedure-driven and knowledge-supported crew-plant interactions. The result is the set of identified HFEs and likely scenarios leading to each. The methodology itself is generic in the sense that it is compatible with various quantification methods, and can be adapted for use across different environments including nuclear, oil and gas, aerospace, aviation, and healthcare. [ABSTRACT FROM AUTHOR]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RELIABILITY (Engineering)
KW - ERGONOMICS
KW - QUALITATIVE research
KW - COGNITIVE ability
KW - EMPIRICAL research
KW - ERROR analysis (Mathematics)
KW - COGNITIVE psychology
KW - Crew Failure Mode (CFM)
KW - Crew Response Tree (CRT)
KW - Human Failure Event (HFE)
KW - Human Reliability Analysis (HRA)
KW - Performance Influencing Factor (PIF)
KW - Probabilistic Risk Assessment (PRA)
N1 - Accession Number: 110822897; Ekanem, Nsimah J. 1; Email Address: njekanem@gmail.com Mosleh, Ali 1 Shen, Song-Hua 2; Affiliation: 1: Center for Risk and Reliability, University of Maryland, College Park, USA 2: US Nuclear Regulatory Commission, Washington, DC, USA; Source Info: Jan2016, Vol. 145, p301; Subject Term: RELIABILITY (Engineering); Subject Term: ERGONOMICS; Subject Term: QUALITATIVE research; Subject Term: COGNITIVE ability; Subject Term: EMPIRICAL research; Subject Term: ERROR analysis (Mathematics); Subject Term: COGNITIVE psychology; Author-Supplied Keyword: Crew Failure Mode (CFM); Author-Supplied Keyword: Crew Response Tree (CRT); Author-Supplied Keyword: Human Failure Event (HFE); Author-Supplied Keyword: Human Reliability Analysis (HRA); Author-Supplied Keyword: Performance Influencing Factor (PIF); Author-Supplied Keyword: Probabilistic Risk Assessment (PRA); Number of Pages: 15p; Document Type: Article
L3 - 10.1016/j.ress.2015.07.009
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=110822897&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Pachepsky, Yakov A.
AU - Martinez, Gonzalo
AU - Pan, Feng
AU - Wagener, Thorsten
AU - Nicholson, Thomas
T1 - Evaluating Hydrological Model Performance using Information Theory-based Metrics.
JO - Hydrology & Earth System Sciences Discussions
JF - Hydrology & Earth System Sciences Discussions
Y1 - 2016/02//
VL - 13
IS - 2
M3 - Article
SP - 1
EP - 24
SN - 18122108
AB - The accuracy-based model performance metrics not necessarily reflect the qualitative correspondence between simulated and measured streamflow time series. The objective of this work was to use the information theory-based metrics to see whether they can be used as complementary tool for hydrologic model evaluation and selection. We simulated 10-year streamflow time series in five watersheds located in Texas, North Carolina, Mississippi, and West Virginia. Eight model of different complexity were applied. The information theory based metrics were obtained after representing the time series as strings of symbols where different symbols corresponded to different quantiles of the probability distribution of streamflow. The symbol alphabet was used. Three metrics were computed for those strings - mean information gain that measures the randomness of the signal, effective measure complexity that characterizes predictability and fluctuation complexity that characterizes the presence of a pattern in the signal. The observed streamflow time series has smaller information content and larger complexity metrics than the precipitation time series. Watersheds served as information filters and and streamflow time series were less random and more complex than the ones of precipitation. This is reflected by the fact that the watershed acts as the information filter in the hydrologic conversion process from precipitation to streamflow. The Nash Sutcliffe efficiency metric increased as the complexity of models increased, but in many cases several model had this efficiency values not statistically significant from each other. In such cases, ranking models by the closeness of the information theory based parameters in simulated and measured streamflow time series can provide an additional criterion for the evaluation of hydrologic model performance. [ABSTRACT FROM AUTHOR]
AB - Copyright of Hydrology & Earth System Sciences Discussions is the property of Copernicus Gesellschaft mbH and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Streamflow
KW - Watersheds -- Models
KW - Information theory
KW - Distribution (Probability theory)
KW - Key performance indicators (Management)
KW - Time series analysis
N1 - Accession Number: 115484060; Pachepsky, Yakov A. 1; Email Address: yakov.pachepsky@ars.usda.gov; Martinez, Gonzalo 2; Email Address: z42magag@uco.es; Pan, Feng 3,4; Email Address: fpan@egi.utah.edu; Wagener, Thorsten 5; Email Address: cextw@bristol.ac.uk; Nicholson, Thomas 6; Email Address: Thomas.Nicholson@nrc.gov; Affiliations: 1: USDA - ARS Environmental Microbial and Food Safety Laboratory, Beltsville, MD 20705, USA; 2: Department of Agronomy, University of Cordoba, 14071, Cordoba, Spain; 3: Department of Civil & Environmental Engineering, the University of Utah, Salt Lake City, UT 84112, USA; 4: Energy & Geoscience Institu te, the University of Utah, Salt Lake City, UT 84108, USA; 5: Department of Civil Engineering, University of Bristol, Bristol, UK; 6: Office of Regulatory Research, US Nuclear Regulatory Commission, Rockville, MD 20852, USA; Issue Info: 2016, Vol. 13 Issue 2, p1; Thesaurus Term: Streamflow; Subject Term: Watersheds -- Models; Subject Term: Information theory; Subject Term: Distribution (Probability theory); Subject Term: Key performance indicators (Management); Subject Term: Time series analysis; Number of Pages: 24p; Document Type: Article
L3 - 10.5194/hess-2016-46
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=115484060&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Mohanta, Lokanath
AU - Cheung, Fan-Bill
AU - Bajorek, Stephen M.
T1 - Stability of coaxial jets confined in a tube with heat and mass transfer.
JO - Physica A
JF - Physica A
Y1 - 2016/02//
VL - 443
M3 - Article
SP - 333
EP - 346
SN - 03784371
AB - A linear temporal stability of coaxial confined jets in a vertical tube involving heat and mass transfer at the interface is presented in this paper. A potential flow analysis that includes the effect of viscosity at the interface is performed in analyzing the stability of the system. Film boiling in a vertical tube gives rise to the flow configuration explored in this work. The effects of various non-dimensional parameters on the growth rate and the neutral curve are discussed. The heat transfer at the interface has been characterized by introducing a heat flux ratio between the conduction heat flux and the evaporation heat flux. Viscous forces and the heat and mass transfer at the interface are found to stabilize the flow both in the capillary instability region and Kelvin–Helmholtz instability region. Increasing heat and mass transfer at the interface stabilizes the flow to small as well as very large wave numbers. [ABSTRACT FROM AUTHOR]
AB - Copyright of Physica A is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - COAXIAL cables
KW - JETS (Fluid dynamics)
KW - HEAT transfer
KW - MASS transfer
KW - FILM boiling
KW - HEAT conduction
KW - Capillary instability
KW - Interface heat and mass transfer
KW - Kelvin–Helmholtz instability
KW - Stability of confined co-axial jets
KW - Viscous potential flow
N1 - Accession Number: 110631854; Mohanta, Lokanath 1; Email Address: lxm971@psu.edu Cheung, Fan-Bill 1 Bajorek, Stephen M. 2; Affiliation: 1: The Pennsylvania State University, Department of Mechanical and Nuclear Engineering, University Park, PA 16802, United States 2: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC 20555-0001, United States; Source Info: Feb2016, Vol. 443, p333; Subject Term: COAXIAL cables; Subject Term: JETS (Fluid dynamics); Subject Term: HEAT transfer; Subject Term: MASS transfer; Subject Term: FILM boiling; Subject Term: HEAT conduction; Author-Supplied Keyword: Capillary instability; Author-Supplied Keyword: Interface heat and mass transfer; Author-Supplied Keyword: Kelvin–Helmholtz instability; Author-Supplied Keyword: Stability of confined co-axial jets; Author-Supplied Keyword: Viscous potential flow; NAICS/Industry Codes: 335920 Communication and energy wire and cable manufacturing; NAICS/Industry Codes: 335929 Other Communication and Energy Wire Manufacturing; NAICS/Industry Codes: 416110 Electrical wiring and construction supplies merchant wholesalers; NAICS/Industry Codes: 423610 Electrical Apparatus and Equipment, Wiring Supplies, and Related Equipment Merchant Wholesalers; Number of Pages: 14p; Document Type: Article
L3 - 10.1016/j.physa.2015.09.088
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Cumblidge, Stephen
AU - D'Agostino, Amy
T1 - Calculating Inspector Probability of Detection Using Performance Demonstration Program Pass Rates.
JO - AIP Conference Proceedings
JF - AIP Conference Proceedings
Y1 - 2016/02/05/
VL - 1706
IS - 1
M3 - Article
SP - 1
EP - 9
PB - American Institute of Physics
SN - 0094243X
AB - The United States Nuclear Regulatory Commission (NRC) staff has been working since the 1970's to ensure that nondestructive testing performed on nuclear power plants in the United States will provide reasonable assurance of structural integrity of the nuclear power plant components. One tool used by the NRC has been the development and implementation of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI Appendix VIII[1] (Appendix VIII) blind testing requirements for ultrasonic procedures, equipment, and personnel. Some concerns have been raised, over the years, by the relatively low pass rates for the Appendix VIII qualification testing. The NRC staff has applied statistical tools and simulations to determine the expected probability of detection (POD) for ultrasonic examinations under ideal conditions based on the pass rates for the Appendix VIII qualification tests for the ultrasonic testing personnel. This work was primarily performed to answer three questions. First, given a test design and pass rate, what is the expected overall POD for inspectors? Second, can we calculate the probability of detection for flaws of different sizes using this information? Finally, if a previously qualified inspector fails a requalification test, does this call their earlier inspections into question? The calculations have shown that one can expect good performance from inspectors who have passed appendix VIII testing in a laboratory-like environment, and the requalification pass rates show that the inspectors have maintained their skills between tests. While these calculations showed that the PODs for the ultrasonic inspections are very good under laboratory conditions, the field inspections are conducted in a very different environment. The NRC staff has initiated a project to systematically analyze the human factors differences between qualification testing and field examinations. This work will be used to evaluate and prioritize potential human factors issues that may degrade performance in the field. [ABSTRACT FROM AUTHOR]
AB - Copyright of AIP Conference Proceedings is the property of American Institute of Physics and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NUCLEAR power plants
KW - NONDESTRUCTIVE testing
KW - ULTRASONIC testing
KW - PRESSURE vessels
KW - PROBABILITY theory
KW - UNITED States
KW - AMERICAN Society of Mechanical Engineers
N1 - Accession Number: 113073679; Cumblidge, Stephen 1; Email Address: Stephen.Cumblidge@nrc.gov D'Agostino, Amy 1; Email Address: Amy.DAgostino@nrc.gov; Affiliation: 1: United States Nuclear Regulatory Commission, Washington, DC 20555-0001; Source Info: 2016, Vol. 1706 Issue 1, p1; Subject Term: NUCLEAR power plants; Subject Term: NONDESTRUCTIVE testing; Subject Term: ULTRASONIC testing; Subject Term: PRESSURE vessels; Subject Term: PROBABILITY theory; Subject Term: UNITED States; Company/Entity: AMERICAN Society of Mechanical Engineers; NAICS/Industry Codes: 541380 Testing Laboratories; Number of Pages: 9p; Illustrations: 2 Charts, 7 Graphs; Document Type: Article
L3 - 10.1063/1.4940657
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=113073679&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Banerjee, Dilip
AU - Nguyen, Tinh
AU - Chuang, Tze-Jer
T1 - Mechanical properties of single-walled carbon nanotube reinforced polymer composites with varied interphase’s modulus and thickness: A finite element analysis study.
JO - Computational Materials Science
JF - Computational Materials Science
Y1 - 2016/03//
VL - 114
M3 - Article
SP - 209
EP - 218
SN - 09270256
AB - The role of the interphase on mechanical performance of glassy polymer/single-walled carbon nanotube composites has been investigated by finite element (FE) method. The matrix and the interphase are modeled using continuum elements and the nanotube is analyzed by Timoshenko beam elements. Stress distribution and mechanical property of the nanocomposites are quantified as a function of the interphase’s modulus and thickness. For composites that include an interphase, the predicted moduli are comparable to the values calculated by the rule of mixtures, but are much lower than those of an interphase-free composite. For composites consisting of only the CNT and the matrix, the predicted modulus values are in good agreement with those computed by the rule of mixtures and with theoretical data reported in the literature, although the predicted values are considerably higher than those of real polymer/CNT composites. Using Griffin’s fracture analysis for dissimilar materials, we have proved that fracture stress of the weak boundary layer in the CNT/polymer interphase is lower than that of the CNT/polymer interface or of the matrix. The weak boundary layer , which is always existing in a CNT/polymer’s three dimensional interphase, is proposed as the main reason for the large discrepancy between Young’s moduli predicted by the model observed in this study and reported in the literature and those measured experimentally from real-world polymer/SWCNT composites. [ABSTRACT FROM AUTHOR]
AB - Copyright of Computational Materials Science is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SINGLE walled carbon nanotubes
KW - MATERIALS -- Mechanical properties
KW - POLYMERIC composites
KW - INTERFACES (Physical sciences)
KW - FINITE element method
KW - TIMOSHENKO beam theory
KW - MIXTURES
KW - CNT
KW - Composite
KW - Finite element
KW - Interphase
KW - Modeling
KW - Multiscale
KW - Polymer
N1 - Accession Number: 112674317; Banerjee, Dilip 1 Nguyen, Tinh 1 Chuang, Tze-Jer 2; Affiliation: 1: National Institute of Standards and Technology, Gaithersburg, MD 20899, United States 2: United States Nuclear Regulatory Commission, Rockville, MD 20852, United States; Source Info: Mar2016, Vol. 114, p209; Subject Term: SINGLE walled carbon nanotubes; Subject Term: MATERIALS -- Mechanical properties; Subject Term: POLYMERIC composites; Subject Term: INTERFACES (Physical sciences); Subject Term: FINITE element method; Subject Term: TIMOSHENKO beam theory; Subject Term: MIXTURES; Author-Supplied Keyword: CNT; Author-Supplied Keyword: Composite; Author-Supplied Keyword: Finite element; Author-Supplied Keyword: Interphase; Author-Supplied Keyword: Modeling; Author-Supplied Keyword: Multiscale; Author-Supplied Keyword: Polymer; Number of Pages: 10p; Document Type: Article
L3 - 10.1016/j.commatsci.2015.12.026
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=112674317&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - KANATAS, CATHERINE E.
AU - SMITH, MAXWELL C.
T1 - THE HEART OF THE MATTER: ALTERNATIVES, MITIGATION MEASURES, AND THE CLOUDED HEART OF NEPA.
JO - Journal of Land Use & Environmental Law
JF - Journal of Land Use & Environmental Law
Y1 - 2016///Spring2016
VL - 31
IS - 2
M3 - Article
SP - 197
EP - 232
PB - Florida State University College of Law
SN - 08924880
AB - The article focuses on mitigation measures for environmental impact statements affecting the quality of the human environment, and mentions National Environmental Policy Act; Council on Environmental Quality issuing regulations governing NEPA; and mitigation measures in environmental assessments.
KW - Environmental impact statements
KW - Human ecology
KW - Extenuating circumstances
N1 - Accession Number: 121219129; KANATAS, CATHERINE E. 1; SMITH, MAXWELL C. 2; Affiliations: 1: Senior Attorney at the United States Nuclear Regulatory Commission (NRC); 2: Attorney at the NRC; Issue Info: Spring2016, Vol. 31 Issue 2, p197; Thesaurus Term: Environmental impact statements; Thesaurus Term: Human ecology; Subject Term: Extenuating circumstances; Number of Pages: 36p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Burns, Stephen G.
T1 - Maintaining Public Trust.
JO - Nuclear Plant Journal
JF - Nuclear Plant Journal
Y1 - 2016/03//Mar/Apr2016
VL - 34
IS - 2
M3 - Article
SP - 20
EP - 23
PB - Presidents & Prime Ministers
SN - 08922055
AB - The article offers the author's insights on the significance of maintaining public trust to the U.S. Nuclear Regulatory Commission (NRC). Topics discussed include the significant role played by trust on how people accept and respond to risk, the need for the NRC to look even more closely in the past on how trust is achieved, and the need for the agency to remain vigilant on explaining its role.
KW - Risk assessment
KW - Government agencies -- United States
KW - Trust
KW - Vigilance (Psychology)
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 114935002; Burns, Stephen G. 1; Affiliations: 1: U.S. Nuclear Regulatory Commission; Issue Info: Mar/Apr2016, Vol. 34 Issue 2, p20; Thesaurus Term: Risk assessment; Subject Term: Government agencies -- United States; Subject Term: Trust; Subject Term: Vigilance (Psychology) ; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; Number of Pages: 3p; Document Type: Article
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DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Yang, Yaguang
T1 - Controllability of spacecraft using only magnetic torques.
JO - IEEE Transactions on Aerospace & Electronic Systems
JF - IEEE Transactions on Aerospace & Electronic Systems
Y1 - 2016/04//
VL - 52
IS - 2
M3 - Article
SP - 954
EP - 961
SN - 00189251
AB - Spacecraft attitude control using only magnetic torques is a time-varying system. Many designs have been proposed using linear quadratic regulator (LQR) and H∞ formulations. The existence of the solutions depends on the controllability of the linear time-varying systems, which has not been established. In this paper, the conditions of controllability for this linear time-varying system is derived. [ABSTRACT FROM AUTHOR]
AB - Copyright of IEEE Transactions on Aerospace & Electronic Systems is the property of IEEE and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SPACE vehicles
KW - MAGNETIC torque
KW - TIME-varying systems
KW - ELECTROMAGNETS
KW - ARTIFICIAL satellites -- Attitude control systems
KW - Attitude control
KW - Controllability
KW - Earth
KW - Magnetosphere
KW - Space vehicles
KW - Time-varying systems
KW - Torque
N1 - Accession Number: 115795745; Yang, Yaguang 1; Affiliation: 1: US Nuclear Regulatory Commission Rockville, MD, USA; Source Info: Apr2016, Vol. 52 Issue 2, p954; Subject Term: SPACE vehicles; Subject Term: MAGNETIC torque; Subject Term: TIME-varying systems; Subject Term: ELECTROMAGNETS; Subject Term: ARTIFICIAL satellites -- Attitude control systems; Author-Supplied Keyword: Attitude control; Author-Supplied Keyword: Controllability; Author-Supplied Keyword: Earth; Author-Supplied Keyword: Magnetosphere; Author-Supplied Keyword: Space vehicles; Author-Supplied Keyword: Time-varying systems; Author-Supplied Keyword: Torque; NAICS/Industry Codes: 927110 Space Research and Technology; NAICS/Industry Codes: 335315 Switchgear and switchboard, and relay and industrial control apparatus manufacturing; NAICS/Industry Codes: 336410 Aerospace product and parts manufacturing; NAICS/Industry Codes: 336414 Guided Missile and Space Vehicle Manufacturing; NAICS/Industry Codes: 423860 Transportation Equipment and Supplies (except Motor Vehicle) Merchant Wholesalers; Number of Pages: 8p; Document Type: Article
L3 - 10.1109/TAES.2015.150520
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=115795745&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Boyd, Christopher
T1 - Perspectives on CFD analysis in nuclear reactor regulation.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2016/04//
VL - 299
M3 - Article
SP - 12
EP - 17
SN - 00295493
AB - The U.S. Nuclear Regulatory Commission is tasked with ensuring that the commercial use of nuclear materials in the United States is safe. This includes the review and evaluation of submitted analyses that support the safety justification for specific reactor-system components or scenarios. Typically these analyses involve the use of codes that have a proven history of validation and acceptance for the specific application of interest. The use of computational fluid dynamics (CFD) has not been as widespread in regulatory activities and the experience level with acceptance is more limited. The ever-increasing capacity of computers, along with the growing number of capable analysts, ensures us that CFD applications will continue to grow in usage for nuclear safety analysis. The challenge ahead is to ensure that these tools are properly validated and applied in order to build up the necessary evidence for more common acceptance in regulatory processes. The challenges include a continuation of the development and maintenance of best-practice guidance, development of problem-specific CFD-grade benchmark studies, the application of verification and validation techniques, and the development of practical treatments for uncertainties and scaling. Through these efforts, it is anticipated that CFD methods will continue to gain acceptance for use in nuclear reactor safety applications. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - COMPUTATIONAL fluid dynamics
KW - RADIOACTIVE substances
KW - NUCLEAR reactors -- Safety measures
KW - FLUID dynamics
KW - U.S. Nuclear Regulatory Commission
N1 - Accession Number: 113897081; Boyd, Christopher 1; Email Address: christopher.boyd@nrc.gov; Affiliation: 1: U.S. Nuclear Regulatory Commission, Washington, DC 20555, United States; Source Info: Apr2016, Vol. 299, p12; Subject Term: COMPUTATIONAL fluid dynamics; Subject Term: RADIOACTIVE substances; Subject Term: NUCLEAR reactors -- Safety measures; Subject Term: FLUID dynamics; Company/Entity: U.S. Nuclear Regulatory Commission; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 6p; Document Type: Article
L3 - 10.1016/j.nucengdes.2015.08.001
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=113897081&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Gallucci, Raymond H.V.
T1 - Development of default uncertainties for the value/benefit attributes in the regulatory analysis technical evaluation handbook.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2016/08/15/
VL - 305
M3 - Article
SP - 260
EP - 269
SN - 00295493
AB - NUREG/BR-0184, Regulatory Analysis Technical Evaluation (RATE) Handbook , was produced in 1997 as an update to the original NUREG/CR-3568, A Handbook for Value-Impact Assessment (1983). Both documents, especially the later RATE Handbook, have been used extensively by the USNRC and its contractors not only for regulatory analyses to support backfit considerations but also for similar applications, such as Severe Accident Management Alternative (SAMA) analyses as part of license renewals. While both provided high-level guidance on the performance of uncertainty analyses for the various value/benefit attributes, detailed quantification was not of prime interest at the times of the Handbooks’ development, defaulting only to best estimates with low and high bounds on these attributes. As the USNRC examines the possibility of updating the RATE Handbook, renewed interest in a more quantitative approach to uncertainty analyses for the attributes has surfaced. As the result of an effort to enhance the RATE Handbook to permit at least default uncertainty analyses for the value/benefit attributes, it has proven feasible to assign default uncertainties in terms of 95th %ile upper bounds (and absolute lower bounds) on the five dominant value/benefit attributes, and their sum, when performing a regulatory analysis via the RATE Handbook. Appropriate default lower bounds of zero (no value/benefit) and an upper bound (95th %ile) that is four times higher than the mean (for individual value/benefit attributes) or three times higher (for their summation) can be recommended. Distributions in the form of histograms on the summed value/benefit attributes are also provided which could be combined, after appropriate scaling and most likely via simulation, with their counterpart(s) from the impact/cost analysis to yield a final distribution on the net overall value/impact (benefit/cost). [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - HISTOGRAMS
KW - NUCLEAR reactor accidents
KW - NUCLEAR reactors -- Licenses
KW - NUCLEAR reactors -- Safety measures
KW - NUCLEAR engineering
KW - L. Safety and risk analysis
N1 - Accession Number: 117645346; Gallucci, Raymond H.V. 1; Email Address: Ray.Gallucci@nrc.gov; Affiliation: 1: U.S. Nuclear Regulatory Commission (USNRC), MS O-10C15, Washington, D.C. 20555, United States; Source Info: Aug2016, Vol. 305, p260; Subject Term: HISTOGRAMS; Subject Term: NUCLEAR reactor accidents; Subject Term: NUCLEAR reactors -- Licenses; Subject Term: NUCLEAR reactors -- Safety measures; Subject Term: NUCLEAR engineering; Author-Supplied Keyword: L. Safety and risk analysis; NAICS/Industry Codes: 332410 Power Boiler and Heat Exchanger Manufacturing; Number of Pages: 10p; Document Type: Article
L3 - 10.1016/j.nucengdes.2016.05.016
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=117645346&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Foster, Norah A.
AU - Moore, Bria
AU - IIWomack, Kenneth R.
AU - Blizzard, Daniel J.
AU - Karikari, Isaac O.
AU - Erickson, Melissa
AU - Richardson, William J.
T1 - 195 - Evaluation of Patient and Operating Room Personnel Radiation Exposure and Effect of Body Habitus Utilizing Current Intraoperative Imaging Systems in Spine Surgery.
JO - Spine Journal
JF - Spine Journal
Y1 - 2016/10/02/Oct2016 Supplement
VL - 16
M3 - Article
SP - S300
EP - S301
SN - 15299430
KW - OPERATING rooms
KW - SPINE -- Surgery
KW - INTRAOPERATIVE radiotherapy
KW - RADIATION -- Dosage
KW - SPINE -- Diseases
KW - TREATMENT
N1 - Accession Number: 118698855; Foster, Norah A. 1 Moore, Bria 1 IIWomack, Kenneth R. 2 Blizzard, Daniel J. 3 Karikari, Isaac O. 4 Erickson, Melissa 4 Richardson, William J. 4; Affiliation: 1: Hospital for Joint Diseases, NYU Langone Medical Center, New York, NY, USA 2: U.S. Nuclear Regulatory Commission, Atlanta, GA, USA 3: Duke University, Durham, NC, USA 4: Duke University Medical Center, Durham, NC, USA; Source Info: Oct2016 Supplement, Vol. 16, pS300; Subject Term: OPERATING rooms; Subject Term: SPINE -- Surgery; Subject Term: INTRAOPERATIVE radiotherapy; Subject Term: RADIATION -- Dosage; Subject Term: SPINE -- Diseases; Subject Term: TREATMENT; Number of Pages: 1p; Document Type: Article
L3 - 10.1016/j.spinee.2016.07.222
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=118698855&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
ID - 118698855
T1 - 195 - Evaluation of Patient and Operating Room Personnel Radiation Exposure and Effect of Body Habitus Utilizing Current Intraoperative Imaging Systems in Spine Surgery.
AU - Foster, Norah A.
AU - Moore, Bria
AU - IIWomack, Kenneth R.
AU - Blizzard, Daniel J.
AU - Karikari, Isaac O.
AU - Erickson, Melissa
AU - Richardson, William J.
Y1 - 2016/10/02/Oct2016 Supplement
N1 - Accession Number: 118698855. Language: English. Entry Date: In Process. Revision Date: 20161014. Publication Type: Article. Supplement Title: Oct2016 Supplement. Journal Subset: Biomedical; USA. NLM UID: 101130732.
SP - S300
EP - S301
JO - Spine Journal
JF - Spine Journal
JA - SPINE J
VL - 16
CY - New York, New York
PB - Elsevier Science
SN - 1529-9430
AD - Hospital for Joint Diseases, NYU Langone Medical Center, New York, NY, USA
AD - U.S. Nuclear Regulatory Commission, Atlanta, GA, USA
AD - Duke University, Durham, NC, USA
AD - Duke University Medical Center, Durham, NC, USA
DO - 10.1016/j.spinee.2016.07.222
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=rzh&AN=118698855&site=ehost-live&scope=site
DP - EBSCOhost
DB - rzh
ER -
TY - JOUR
AU - Gallucci, Raymond H.V.
T1 - The “incredible” difficulty of proving “incredibility” – Example of fire-induced multiple spurious operations.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2016/11//
VL - 308
M3 - Article
SP - 96
EP - 102
SN - 00295493
AB - “Risk-informed” regulation is often an alternative to “deterministically-based” regulation that offers relaxation in criteria for acceptability while possibly requiring greater analytical effort. “Risk-informed determinism” is an attempt to meld the best of both worlds by using risk information to set deterministic acceptance criteria a priori . A recent joint effort by the US Nuclear Regulatory Commission’s Office of Nuclear Regulatory Research (RES) and Electric Power Research Institute (EPRI) originally endeavored to do this for several examples involving fire-induced multiple spurious operations (MSOs) in electrical circuits at nuclear power plants. While a noble effort, this did not consider the actual distributions involved in the events, originally limiting the analysis to mean values and, in some cases, qualitative considerations. A much more comprehensive and defensible approach is performed here where the probabilistic distributions for all the factors are considered via simulation to meet quantitative acceptance criteria related to the concept of “incredibility” that is often the figure of merit that must be met in a deterministic world. The effort demonstrates that it can be “incredibly” difficult to prove “incredibility” in this context. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - RISK assessment
KW - ELECTRIC circuits
KW - NUCLEAR power plants -- Safety measures
KW - L. Safety and Risk Analysis
KW - U.S. Nuclear Regulatory Commission
KW - ELECTRIC Power Research Institute
N1 - Accession Number: 118401762; Gallucci, Raymond H.V. 1; Email Address: Ray.Gallucci@nrc.gov; Affiliation: 1: U.S. Nuclear Regulatory Commission (USNRC), MS O-10C15, Washington, D.C. 20555, United States; Source Info: Nov2016, Vol. 308, p96; Subject Term: RISK assessment; Subject Term: ELECTRIC circuits; Subject Term: NUCLEAR power plants -- Safety measures; Author-Supplied Keyword: L. Safety and Risk Analysis; Company/Entity: U.S. Nuclear Regulatory Commission DUNS Number: Company/Entity: ELECTRIC Power Research Institute DUNS Number: 062511126; NAICS/Industry Codes: 926130 Regulation and Administration of Communications, Electric, Gas, and Other Utilities; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 7p; Document Type: Article
L3 - 10.1016/j.nucengdes.2016.08.013
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=118401762&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Ahn, Tae M.
T1 - Multiple lines of evidence for performance of the canister and waste form in long-term nuclear waste disposal: Reviews.
JO - Progress in Nuclear Energy
JF - Progress in Nuclear Energy
Y1 - 2016/11//
VL - 93
M3 - Article
SP - 343
EP - 350
SN - 01491970
AB - The time scales required for nuclear waste disposal are very large compared with those for other engineering endeavors. Because of this, there are many uncertainties associated with the quantitative performance assessment of canisters containing high-level radioactive waste in a waste form. Multiple lines of evidence can be helpful in building confidence in the long-term behavior (corrosion and dissolution) of the canister and waste form. These lines of evidence are derived from long-term supports and probabilistic models and developed based on shorter term tests, bounding and conservative approaches, and available observations on natural analogs. This paper presents the progress made for important lines of evidence considered in quantitatively assessing radionuclide release behavior from canisters and waste forms. This paper considers risk-significant issues for canisters and waste forms (i.e., risk informed approach) in the probabilistic performance assessment of the disposal system which has also other components such as geology and hydrology. [ABSTRACT FROM AUTHOR]
AB - Copyright of Progress in Nuclear Energy is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radioactive waste disposal
KW - Radioisotopes
KW - Corrosion & anti-corrosives
KW - Hydrology
KW - Radioactive waste canisters
KW - Corrosion
KW - Long-term behavior
KW - Nuclear waste
KW - Radionuclide release
N1 - Accession Number: 118698388; Ahn, Tae M. 1; Email Address: tae.ahn@nrc.gov; Affiliations: 1: Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, MS 2WFN 4A12, Washington, DC, 20555-0001, USA; Issue Info: Nov2016, Vol. 93, p343; Thesaurus Term: Radioactive waste disposal; Thesaurus Term: Radioisotopes; Thesaurus Term: Corrosion & anti-corrosives; Thesaurus Term: Hydrology; Subject Term: Radioactive waste canisters; Author-Supplied Keyword: Corrosion; Author-Supplied Keyword: Long-term behavior; Author-Supplied Keyword: Nuclear waste; Author-Supplied Keyword: Radionuclide release; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 8p; Document Type: Article
L3 - 10.1016/j.pnucene.2016.08.020
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=118698388&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Worosz, Ted
AU - Bernard, Matt
AU - Kong, Ran
AU - Toptan, Aysenur
AU - Kim, Seungjin
AU - Hoxie, Chris
T1 - Sensitivity studies on the multi-sensor conductivity probe measurement technique for two-phase flows.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2016/12/15/
VL - 310
M3 - Article
SP - 552
EP - 563
SN - 00295493
AB - The objective of this study is to advance the local multi-sensor conductivity probe measurement technique through systematic investigation into several practical aspects of a conductivity probe measurement system. Firstly, signal “ghosting” among probe sensors is found to cause artificially high bubble velocity measurements and low interfacial area concentration ( a i ) measurements that depend on sampling frequency and sensor impedance. A revised electrical circuit is suggested to eliminate this artificial variability. Secondly, the sensitivity of the probe measurements to sampling frequency is investigated in 13 two-phase flow conditions with superficial liquid and gas velocities ranging from 1.00–5.00 m/s and 0.17–2.0 m/s, respectively. With increasing gas flow rate, higher sampling frequencies, greater than 100 kHz in some cases, are required to adequately capture the bubble number frequency and a i measurements. This trend is due to the increase in gas velocity and the transition to the slug flow regime. Thirdly, the sensitivity of the probe measurements to the measurement duration as well as the sample number is investigated for the same flow conditions. Measurements of both group-I (spherical/distorted) and group-II (cap/slug/churn-turbulent) bubbles are found to be relatively insensitive to both the measurement duration and the number of bubbles, as long as the measurements are made for a duration long enough to capture a collection of samples characteristic to a given two-phase flow system (or a statistical ensemble). Fourthly, investigation into the orientation of a double-sensor probe in the pipe indicates that the sensors should be oriented parallel to the pipe wall to ensure symmetric bubble velocity measurements. Lastly, Monte Carlo simulations are performed to study the effects of the axial ( s ) and lateral ( d ) probe sensor separation distances. In addition to previous criteria on the ratio of s to the bubble diameter, it is found that s / d should be greater than four to minimize errors in the measured bubble velocity. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - TWO-phase flow
KW - SENSITIVITY analysis
KW - MULTISENSOR data fusion
KW - PHYSICAL measurements
KW - INTERFACES (Physical sciences)
KW - Bubble velocity
KW - Conductivity probe
KW - Interfacial area concentration
KW - Sensitivity
KW - Two-phase flow
N1 - Accession Number: 120143241; Worosz, Ted 1 Bernard, Matt 2 Kong, Ran 1 Toptan, Aysenur 1 Kim, Seungjin 1; Email Address: skim@psu.edu Hoxie, Chris 2; Affiliation: 1: Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, 230 Reber Building, University Park, PA 16802, USA 2: The United States Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD 20852, USA; Source Info: Dec2016, Vol. 310, p552; Subject Term: TWO-phase flow; Subject Term: SENSITIVITY analysis; Subject Term: MULTISENSOR data fusion; Subject Term: PHYSICAL measurements; Subject Term: INTERFACES (Physical sciences); Author-Supplied Keyword: Bubble velocity; Author-Supplied Keyword: Conductivity probe; Author-Supplied Keyword: Interfacial area concentration; Author-Supplied Keyword: Sensitivity; Author-Supplied Keyword: Two-phase flow; Number of Pages: 12p; Document Type: Article
L3 - 10.1016/j.nucengdes.2016.10.046
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=120143241&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Yang, X.
AU - Schlegel, J.P.
AU - Liu, Y.
AU - Paranjape, S.
AU - Hibiki, T.
AU - Ishii, M.
AU - Bajorek, S.
AU - Ireland, A.
T1 - Prediction of interfacial area transport in a scaled 8×8 BWR rod bundle.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2016/12/15/
VL - 310
M3 - Article
SP - 638
EP - 647
SN - 00295493
AB - In the two-fluid model, it is important to give an accurate prediction for the interfacial area concentration. In order to achieve this goal, the interfacial area transport equation has been developed. This study focuses on the benchmark of IATE performance in a rod bundle geometry. A set of interfacial area concentration source and sink term models are proposed for a rod bundle geometry based on the confined channel IATE model. This model was selected as a basis because of the relative similarity of the two geometries. Benchmarking of the new model with interfacial area concentration data in an 8×8 rod bundle test section which has been scaled from an actual BWR fuel bundle is performed. The model shows good agreement in bubbly and cap-bubbly flows, which are similar in many types of geometries, while it shows some discrepancy in churn-turbulent flow regime. This discrepancy may be due to the geometrical differences between the actual rod bundle test facility and the facility used to collect the data which benchmarked the original source and sink models. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - BOILING water reactors
KW - INTERFACES (Physical sciences)
KW - PREDICTION (Logic)
KW - NUCLEAR fuel rods
KW - GEOMETRIC analysis
KW - Interfacial area concentration
KW - Interfacial area transport equation
KW - Rod bundle
KW - Two-phase flow
N1 - Accession Number: 120143216; Yang, X. 1 Schlegel, J.P. 1 Liu, Y. 1 Paranjape, S. 1 Hibiki, T. 1 Ishii, M. 1 Bajorek, S. 2 Ireland, A. 2; Affiliation: 1: School of Nuclear Engineering, Purdue University, 400 Central Dr., West Lafayette, IN 47907-2017, United States 2: U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, United States; Source Info: Dec2016, Vol. 310, p638; Subject Term: BOILING water reactors; Subject Term: INTERFACES (Physical sciences); Subject Term: PREDICTION (Logic); Subject Term: NUCLEAR fuel rods; Subject Term: GEOMETRIC analysis; Author-Supplied Keyword: Interfacial area concentration; Author-Supplied Keyword: Interfacial area transport equation; Author-Supplied Keyword: Rod bundle; Author-Supplied Keyword: Two-phase flow; Number of Pages: 10p; Document Type: Article
L3 - 10.1016/j.nucengdes.2016.10.037
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=120143216&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Bond, Alexander
AU - Bruský, Ivan
AU - Cao, Tianqing
AU - Chittenden, Neil
AU - Fedors, Randall
AU - Feng, Xia-Ting
AU - Gwo, Jin-Ping
AU - Kolditz, Olaf
AU - Lang, Philipp
AU - McDermott, Christopher
AU - Neretnieks, Ivars
AU - Pan, Peng-Zhi
AU - Šembera, Jan
AU - Shao, Hua
AU - Watanabe, Nori
AU - Yasuhara, Hide
AU - Zheng, Hong
T1 - A synthesis of approaches for modelling coupled thermal-hydraulic-mechanical-chemical processes in a single novaculite fracture experiment.
JO - Environmental Earth Sciences
JF - Environmental Earth Sciences
Y1 - 2017/01//
VL - 76
IS - 1
M3 - Article
SP - 1
EP - 19
SN - 18666280
AB - The geological formation immediately surrounding a nuclear waste disposal facility has the potential to undergo a complex set of physical and chemical processes starting from construction and continuing many years after closure. The DECOVALEX project (DEvelopment of COupled models and their VALidation against EXperiments) was established and maintained by a variety of waste management organisations, regulators and research organisations to help improve capabilities in experimental interpretation, numerical modelling and blind prediction of complex coupled systems. In the present round of DECOVALEX (D-2015), one component of Task C1 has considered the detailed experimental work of Yasuhara et al. (Earth Planet Sci Lett 244:186-200, 2006), wherein a single artificial fracture in novaculite (micro- or crypto-crystalline quartz) is subject to variable fluid flows, mechanical confining pressure and different applied temperatures. This paper presents a synthesis of the completed work of six separate research teams. A range of approaches are presented including 2D and 3D high-resolution coupled thermo-hydro-mechanical-chemical models. The results of the work show that while good, physically plausible representations of the experiment can be obtained using a range of approaches, there is considerable uncertainty in the relative importance of the various processes, and that the parameterisation of these processes can be closely linked to the interpretation of the fracture surface topography at different spatial scales. [ABSTRACT FROM AUTHOR]
AB - Copyright of Environmental Earth Sciences is the property of Springer Science & Business Media B.V. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radioactive wastes
KW - Formations (Geology)
KW - Thermal hydraulics
KW - Novaculite
KW - Chemical processes
KW - Experiment
KW - Fracture
KW - Modelling
KW - Radioactive waste
KW - THMC
N1 - Accession Number: 120771019; Bond, Alexander 1; Email Address: alexbond@quintessa.org; Bruský, Ivan 2; Cao, Tianqing 3; Chittenden, Neil 1; Fedors, Randall 3; Feng, Xia-Ting 4; Gwo, Jin-Ping 3; Kolditz, Olaf 5; Lang, Philipp 6; McDermott, Christopher 7; Neretnieks, Ivars 8; Pan, Peng-Zhi 4; Email Address: pzpan@whrsm.ac.cn; Šembera, Jan 2; Shao, Hua 9; Watanabe, Nori 5; Yasuhara, Hide 10; Zheng, Hong 4; Affiliations: 1: Quintessa Ltd , Henley-on-Thames UK; 2: Technical University of Liberec , Liberec Czech Republic; 3: U.S. Nuclear Regulatory Commission , North Bethesda USA; 4: Institute of Rock and Soil Mechanics , Chinese Academy of Sciences , Wuhan China; 5: Department Environmental Informatics , Helmholtz Centre for Environmental Research - UFZ , Leipzig Germany; 6: Imperial College , London UK; 7: School of Geosciences , University of Edinburgh , Edinburgh UK; 8: Department of Chemical Engineering , Royal Institute of Technology , Stockholm Sweden; 9: Federal Institute for Geosciences and Natural Resources (BGR) , Hannover Germany; 10: Ehime University , Matsuyama Japan; Issue Info: Jan2017, Vol. 76 Issue 1, p1; Thesaurus Term: Radioactive wastes; Subject Term: Formations (Geology); Subject Term: Thermal hydraulics; Subject Term: Novaculite; Subject Term: Chemical processes; Author-Supplied Keyword: Experiment; Author-Supplied Keyword: Fracture; Author-Supplied Keyword: Modelling; Author-Supplied Keyword: Radioactive waste; Author-Supplied Keyword: THMC; NAICS/Industry Codes: 562210 Waste treatment and disposal; NAICS/Industry Codes: 562211 Hazardous Waste Treatment and Disposal; Number of Pages: 19p; Document Type: Article
L3 - 10.1007/s12665-016-6326-6
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=eih&AN=120771019&site=ehost-live&scope=site
DP - EBSCOhost
DB - eih
ER -
TY - JOUR
AU - Gallucci, Raymond
T1 - Statistical Characterization of Cable Electrical Failure Temperatures Due to Fire for Nuclear Power Plant Risk Applications.
JO - Fire Technology
JF - Fire Technology
Y1 - 2017/01//
VL - 53
IS - 1
M3 - Article
SP - 401
EP - 412
SN - 00152684
AB - Single-value failure temperatures for fire loss of electrical cable functionality have been the norm for Fire Probabilistic Risk Assessments since the publication in 2005 of NUREG/CR-6850. If the calculated exposure temperature matches or exceeds the cable failure temperature, electrical failure is always assumed; if not, no failure is assumed. While this can be relaxed somewhat if a distribution for the exposure temperature is estimated, use of a distribution on the cable failure temperature itself more readily enables such relaxation and, therefore, a more realistic assessment. This paper develops probability distributions for different generic cable types (based on insulation) using data from the US Nuclear Regulatory Commission tests. Results indicate mean failure temperatures considerably higher than those used deterministically, 252°C, 421°C and 383°C, respectively for thermoplastic, thermoset and Kerite-FR. This suggests considerable relaxation from the conservatism inherent using the deterministic failure temperatures could be achieved. The paper then postulates two hypothetical distributions on the exposure temperature from applying a fire phenomenological model in a statistical way to estimate the possible relaxation using the distributed cable failure temperatures to enhance the realism of the assessment. Examples show that use of probabilistically-distributed cable failure temperatures (in conjunction with similar for exposure temperatures) can reduce the probability of electrical failure for a normally-distributed exposure temperature with a mean of 350°C and standard deviation of 58.3°C by factors of approximately three and eight for Kerite-FR and thermoset cables, respectively. The reduction would be less pronounced for thermoplastic cables, although larger reductions would be possible here as well for lower exposure temperatures (e.g., a factor of two). [ABSTRACT FROM AUTHOR]
AB - Copyright of Fire Technology is the property of Springer Science & Business Media B.V. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - NUCLEAR power plants -- Risk assessment
KW - ELECTRIC power failures
KW - THERMOPLASTIC composites
KW - PHENOMENOLOGICAL theory (Physics)
KW - FIRE prevention
KW - Cable fires
KW - Damage temperatures
KW - Electrical failures
KW - Probabilities
KW - Statistics
N1 - Accession Number: 120737880; Gallucci, Raymond 1; Email Address: Ray.gallucci@nrc.gov; Affiliation: 1: US Nuclear Regulatory Commission (NRC) , 11555 Rockville Pike Rockville 20852 USA; Source Info: Jan2017, Vol. 53 Issue 1, p401; Subject Term: NUCLEAR power plants -- Risk assessment; Subject Term: ELECTRIC power failures; Subject Term: THERMOPLASTIC composites; Subject Term: PHENOMENOLOGICAL theory (Physics); Subject Term: FIRE prevention; Author-Supplied Keyword: Cable fires; Author-Supplied Keyword: Damage temperatures; Author-Supplied Keyword: Electrical failures; Author-Supplied Keyword: Probabilities; Author-Supplied Keyword: Statistics; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; Number of Pages: 12p; Document Type: Article
L3 - 10.1007/s10694-016-0616-0
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=120737880&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Mohanta, Lokanath
AU - Cheung, Fan-Bill
AU - Bajorek, Stephen M.
AU - Tien, Kirk
AU - Hoxie, Chris L.
T1 - Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer grids.
JO - Nuclear Engineering & Design
JF - Nuclear Engineering & Design
Y1 - 2017/02//
VL - 312
M3 - Article
SP - 99
EP - 105
SN - 00295493
AB - Heat transfer by mixed convection in a rod bundle occurs when convection is affected by both the buoyancy and inertial forces. Mixed convection can be assumed when the Richardson number ( Ri = Gr / Re 2 ) is on the order of unity, indicating that both forced and natural convection are important contributors to heat transfer. In the present study, data obtained from the Rod Bundle Heat Transfer (RBHT) facility was used to determine the heat transfer coefficient in the mixed convection regime, which was found to be significantly larger than those expected assuming purely forced convection based on the inlet flow rate. The inlet Reynolds ( Re ) number for the tests ranged from 500 to 1300, while the Grashof ( Gr ) number varied from 1.5 × 10 5 to 3.8 × 10 6 yielding 0.25 < Ri < 4.3. Using results from RBHT test along with the correlation from the FLECHT-SEASET test program for laminar forced convection, a new correlation is proposed for mixed convection in a rod bundle. The new correlation accounts for the enhancement of heat transfer relative to laminar forced convection. [ABSTRACT FROM AUTHOR]
AB - Copyright of Nuclear Engineering & Design is the property of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - LAMINAR flow
KW - HEAT transfer coefficient
KW - REYNOLDS number
KW - FORCED convection
KW - NUCLEAR fuel rods
KW - RICHARDSON number
N1 - Accession Number: 121376732; Mohanta, Lokanath 1; Email Address: lxm971@psu.edu Cheung, Fan-Bill 1 Bajorek, Stephen M. 2 Tien, Kirk 2 Hoxie, Chris L. 2; Affiliation: 1: Department of Mechanical and Nuclear Engineering, Pennsylvania State University, University Park, PA 16802, USA 2: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, USA; Source Info: Feb2017, Vol. 312, p99; Subject Term: LAMINAR flow; Subject Term: HEAT transfer coefficient; Subject Term: REYNOLDS number; Subject Term: FORCED convection; Subject Term: NUCLEAR fuel rods; Subject Term: RICHARDSON number; Number of Pages: 7p; Document Type: Article
L3 - 10.1016/j.nucengdes.2016.07.023
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=121376732&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Wang, Guanyi
AU - Dang, Zhuoran
AU - Ju, Peng
AU - Yang, Xiaohong
AU - Ishii, Mamoru
AU - Ireland, Andrew
AU - Bajorek, Stephen
AU - Bernard, Matthew
T1 - Experimental study on interfacial structure and interfacial area transport in downward two-phase flow.
JO - International Journal of Heat & Mass Transfer
JF - International Journal of Heat & Mass Transfer
Y1 - 2017/03//
VL - 106
M3 - Article
SP - 1303
EP - 1317
SN - 00179310
AB - In view of the importance of two-group interfacial area transport equation and lack of corresponding accurate downward flow database that can reveal two-group interfacial area transport, a systematic database for adiabatic, air-water, vertical downward two-phase flow in a round pipe with inner diameter of 25.4 mm was collected to gain an insight of interfacial structure and provide benchmarking data for two-group interfacial area transport model. Four-sensor conductivity probes were used to measure the local two phase flow parameters at high data sampling frequency to ensure the accuracy. Axial development of local flow parameter profiles including void fraction, interfacial area concentration, and Sauter mean diameter were presented. Drastic inter-group transfer of void fraction and interfacial area as well as the wall peaked interfacial area concentration profiles were observed and discussed. [ABSTRACT FROM AUTHOR]
AB - Copyright of International Journal of Heat & Mass Transfer is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - AIR-water interfaces
KW - THERMAL conductivity
KW - CONVECTION-diffusion equations
KW - ADIABATIC processes
KW - VOIDS (Crystallography)
KW - HEAT transfer
KW - Downward two-phase flow
KW - Four-sensor conductivity probe
KW - Interfacial area concentration
KW - Interfacial area transport equation
N1 - Accession Number: 120146234; Wang, Guanyi 1 Dang, Zhuoran 1 Ju, Peng 1,2 Yang, Xiaohong 1 Ishii, Mamoru 1; Email Address: ishii@purdue.edu Ireland, Andrew 3 Bajorek, Stephen 3 Bernard, Matthew 3; Affiliation: 1: School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA 2: China Nuclear Power Technology Research Institute Co., Ltd, Shenzhen 518000, China 3: United States Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Mar2017, Vol. 106, p1303; Subject Term: AIR-water interfaces; Subject Term: THERMAL conductivity; Subject Term: CONVECTION-diffusion equations; Subject Term: ADIABATIC processes; Subject Term: VOIDS (Crystallography); Subject Term: HEAT transfer; Author-Supplied Keyword: Downward two-phase flow; Author-Supplied Keyword: Four-sensor conductivity probe; Author-Supplied Keyword: Interfacial area concentration; Author-Supplied Keyword: Interfacial area transport equation; Number of Pages: 15p; Document Type: Article
L3 - 10.1016/j.ijheatmasstransfer.2016.10.112
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Park, J.
AU - Chang, Y.J.
AU - Kim, Y.
AU - Choi, S.
AU - Kim, S.
AU - Jung, W.
T1 - The use of the SACADA taxonomy to analyze simulation records: Insights and suggestions.
JO - Reliability Engineering & System Safety
JF - Reliability Engineering & System Safety
Y1 - 2017/03//
VL - 159
M3 - Article
SP - 174
EP - 183
SN - 09518320
AB - It is evident that diverse human reliability analysis (HRA) methods are effective for enhancing the safety of socio-technical systems through identifying the most vulnerable tasks to human errors with the associated human error probabilities. This means that reliable human performance data is an important factor affecting HRA quality. Therefore, many researchers have developed technical underpinnings (such as guidelines and taxonomies) that specify what and how HRA data can be collected from simulator experiments. Here, SACADA (Scenario Authoring, Characterization, and Debriefing Application) taxonomy recently developed by US NRC (Nuclear Regulatory Commission) is worth emphasizing, because it is constructed on the basis of a cognitive model (i.e., a top-down approach) while most of the technical underpinnings are developed by a bottom-up approach (i.e., the intensive review of existing literature). For this reason, in this study, the SACADA taxonomy is used to analyze several audio-visual records collected from the full scope simulators of nuclear power plants in the Republic of Korea. The results indicate that the SACADA taxonomy is useful to collect operator performance data in simulator training for HRA. Certain human performance information that can be provided by SACADA data provided are difficult to be covered by the bottom-up approach. [ABSTRACT FROM AUTHOR]
AB - Copyright of Reliability Engineering & System Safety is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - SOCIOTECHNICAL systems
KW - RELIABILITY (Engineering)
KW - HUMAN error
KW - SIMULATION methods & models
KW - NUCLEAR power plants
KW - Data collection framework
KW - Human reliability analysis
KW - Nuclear power plant
KW - SACADA taxonomy
KW - Simulator experiment
N1 - Accession Number: 120321881; Park, J. 1; Email Address: kshpjk@kaeri.re.kr Chang, Y.J. 2 Kim, Y. 1 Choi, S. 1 Kim, S. 1 Jung, W. 1; Affiliation: 1: Korea Atomic Energy Research Institute (KAERI), South Korea 2: U.S. Nuclear Regulatory Commission (NRC), South Korea; Source Info: Mar2017, Vol. 159, p174; Subject Term: SOCIOTECHNICAL systems; Subject Term: RELIABILITY (Engineering); Subject Term: HUMAN error; Subject Term: SIMULATION methods & models; Subject Term: NUCLEAR power plants; Author-Supplied Keyword: Data collection framework; Author-Supplied Keyword: Human reliability analysis; Author-Supplied Keyword: Nuclear power plant; Author-Supplied Keyword: SACADA taxonomy; Author-Supplied Keyword: Simulator experiment; NAICS/Industry Codes: 221113 Nuclear Electric Power Generation; NAICS/Industry Codes: 237130 Power and Communication Line and Related Structures Construction; Number of Pages: 10p; Document Type: Article
L3 - 10.1016/j.ress.2016.11.002
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=120321881&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Mohanta, Lokanath
AU - Sohag, Faruk A.
AU - Cheung, Fan-Bill
AU - Bajorek, Stephen M.
AU - Kelly, Joseph M.
AU - Tien, Kirk
AU - Hoxie, Chris L.
T1 - Heat transfer correlation for film boiling in vertical upward flow.
JO - International Journal of Heat & Mass Transfer
JF - International Journal of Heat & Mass Transfer
Y1 - 2017/04//
VL - 107
M3 - Article
SP - 112
EP - 122
SN - 00179310
AB - There is no heat transfer correlation available in the Inverted Slug Film Boiling (ISFB) regime. In this study, a new correlation for film boiling in a vertical channel is proposed using a semi-empirical model. This correlation is applicable in the Inverted Annular Film Boiling (IAFB) heat transfer regime as well as ISFB heat transfer regime. A semi-empirical model is developed to establish the functional dependence of the Nusselt number on various controlling parameters. Test data obtained from the transient reflood tests carried out in a full length 7 × 7 vertical Rod Bundle Heat Transfer (RBHT) facility are used to develop the correlation. The predicted Nusselt number agrees within 15% with the RBHT data set and other data set available in the literature. This heat transfer correlation is applicable up to a void fraction of 90%, i.e., both in the IAFB and ISFB regimes. The proposed correlation is also applicable to a tube geometry using a modified coefficient in the correlation with an error less than 10%. [ABSTRACT FROM AUTHOR]
AB - Copyright of International Journal of Heat & Mass Transfer is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - HEAT transfer
KW - FILM boiling
KW - NUSSELT number
KW - VERTICAL flow (Fluid dynamics)
KW - CORRELATION (Statistics)
KW - Inverted Annular Film Boiling
KW - Inverted Slug Film Boiling
KW - Rod bundle
KW - Subcooled film boiling
N1 - Accession Number: 120242689; Mohanta, Lokanath 1; Email Address: lokanath.mohanta@gmail.com Sohag, Faruk A. 1 Cheung, Fan-Bill 1 Bajorek, Stephen M. 2 Kelly, Joseph M. 2 Tien, Kirk 2 Hoxie, Chris L. 2; Affiliation: 1: The Pennsylvania State University, Department of Mechanical and Nuclear Engineering, University Park, PA 16802, United States 2: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, D.C. 20555-0001, United States; Source Info: Apr2017, Vol. 107, p112; Subject Term: HEAT transfer; Subject Term: FILM boiling; Subject Term: NUSSELT number; Subject Term: VERTICAL flow (Fluid dynamics); Subject Term: CORRELATION (Statistics); Author-Supplied Keyword: Inverted Annular Film Boiling; Author-Supplied Keyword: Inverted Slug Film Boiling; Author-Supplied Keyword: Rod bundle; Author-Supplied Keyword: Subcooled film boiling; Number of Pages: 11p; Document Type: Article
L3 - 10.1016/j.ijheatmasstransfer.2016.11.018
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=120242689&site=ehost-live&scope=site
DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Yang, Jiann C.
AU - Hnetkovsky, Edward
AU - Rinehart, Doris
AU - Fernandez, Marco
AU - Gonzalez, Felix
AU - Borowsky, Joseph
T1 - Performance of metal and polymeric O-ring seals during beyond-design-basis thermal conditions.
JO - Polymer Testing
JF - Polymer Testing
Y1 - 2017/04//
VL - 58
M3 - Article
SP - 135
EP - 141
SN - 01429418
AB - This paper summarizes the small scale thermal exposure test results of the performance of metallic and polymeric O-ring seals typically used in radioactive material transportation packages. Five different O-ring materials were evaluated: Inconel/silver, ethylene-propylene diene monomer (EPDM), polytetrafluoroethylene (PTFE), silicone, butyl, and Viton. The overall objective of this study is to provide test data and insights to the performance of these O-ring seals when exposed to beyond-design-basis temperature conditions due to a severe fire. Tests were conducted using a small-scale stainless steel pressure vessel pressurized with helium to 2 bar or 5 bar at room temperature. The vessel was then heated in an electric furnace to temperatures up to 900 °C for a pre-determined period (typically 8 h–9 h). The pressure drop technique was used to determine if leakage occurred during thermal exposure. Out of a total of 46 tests performed, leakage (loss of vessel pressure) was detected in 13 tests. [ABSTRACT FROM AUTHOR]
AB - Copyright of Polymer Testing is the property of Elsevier Science Publishing Company, Inc. and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - POLYMERS -- Thermal properties
KW - O-rings
KW - POLYTEF
KW - POLYMERIC composites
KW - TEMPERATURE effect
KW - Beyond-design-basis conditions
KW - Cask
KW - Fires
KW - Seals
KW - Shipping package
KW - Spent fuels
N1 - Accession Number: 121296741; Yang, Jiann C. 1; Email Address: jiann.yang@nist.gov Hnetkovsky, Edward 1 Rinehart, Doris 1 Fernandez, Marco 1 Gonzalez, Felix 2 Borowsky, Joseph 2; Affiliation: 1: Fire Research Division, Engineering Laboratory, National Institute of Standards and Technology, Gaithersburg, MD 20899, USA 2: U.S. Nuclear Regulatory Commission, Rockville, MD 20852, USA; Source Info: Apr2017, Vol. 58, p135; Subject Term: POLYMERS -- Thermal properties; Subject Term: O-rings; Subject Term: POLYTEF; Subject Term: POLYMERIC composites; Subject Term: TEMPERATURE effect; Author-Supplied Keyword: Beyond-design-basis conditions; Author-Supplied Keyword: Cask; Author-Supplied Keyword: Fires; Author-Supplied Keyword: Seals; Author-Supplied Keyword: Shipping package; Author-Supplied Keyword: Spent fuels; Number of Pages: 7p; Document Type: Article
L3 - 10.1016/j.polymertesting.2016.12.011
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DP - EBSCOhost
DB - aph
ER -
TY - JOUR
AU - Dave, Akshay J.
AU - Manera, Annalisa
AU - Beyer, Matthias
AU - Lucas, Dirk
AU - Bernard, Matthew
T1 - Evaluation of two-group interfacial area transport equation model for vertical small diameter pipes against high-resolution experimental data.
JO - Chemical Engineering Science
JF - Chemical Engineering Science
Y1 - 2017/04/27/
VL - 162
M3 - Article
SP - 175
EP - 191
SN - 00092509
AB - Two-phase flow is ubiquitous in industrial, chemical and thermal plants alike. The current state-of-the-art system-code model for predicting fluid transport in two-phase flows is the two-fluid model. In the two-fluid transport model, the coupling of mass, momentum and energy transfer between phases is highly dependent on interfacial area transfer terms. Several research efforts in the past have been focused on the development of an interfacial area transport equation model (IATE) in order to eliminate the drawbacks of static regime flow maps currently used in best-estimate thermal-hydraulic system codes. The IATE attempts to model the dynamic evolution of the vapor/liquid interface by accounting for the different interaction mechanisms affecting gaseous phase transport. The further development and validation of IATE models has been hindered by the lack of adequate experimental data in regions beyond the bubbly flow regime. At the Helmoltz-Zentrum Dresden-Rossendorf (HZDR) experiments utilizing wire-mesh sensors have been performed over all flow regimes, establishing a database of high-resolution (in space and time) data. A 52.3 mm diameter pipe with a 16 by 16 wire-mesh sensor operating at 2.5 kHz is utilized in the air-water experimental database used in this work. There are a total of 37 tests (with varying superficial gas and liquid velocities, at approximately 0.25 MPa). Analysis of IATE performance in the bubbly flow and slug flow regimes is presented. The performance of the Fu-Ishii two-group IATE model is evaluated. In all regions, the interfacial area concentration for small bubbles is predicted well. The model performs poorly in high void fraction regimes, in which large irregularly shaped bubbles are present. The interaction mechanisms that support and deter performance of the IATE model are highlighted. A sensitivity analysis indicates modification of the group-2 wake entrainment coefficient may extend the validity of the Fu-Ishii model. An optimization study is presented to further explore improving IATE performance. It is concluded that the availability of accurate data at high void fractions from the HZDR facility provides a path to improve IATE performance. [ABSTRACT FROM AUTHOR]
AB - Copyright of Chemical Engineering Science is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - CONVECTION-diffusion equations
KW - TWO-phase flow
KW - GENETIC algorithms
KW - SENSITIVITY analysis
KW - VAPOR-liquid equilibrium
KW - Genetic algorithm
KW - Interfacial area transport
KW - Small-diameter
KW - Wire-mesh sensor
N1 - Accession Number: 121378550; Dave, Akshay J. 1; Email Address: akshayjd@umich.edu Manera, Annalisa 1 Beyer, Matthias 2 Lucas, Dirk 2 Bernard, Matthew 3; Affiliation: 1: Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48105, USA 2: Helmholtz-Zentrum Dresden-Rossendorf, Institute of Fluid Dynamics, 01314 Dresden, Germany 3: U.S. Nuclear Regulatory Commission, Washington, DC 20555, USA; Source Info: Apr2017, Vol. 162, p175; Subject Term: CONVECTION-diffusion equations; Subject Term: TWO-phase flow; Subject Term: GENETIC algorithms; Subject Term: SENSITIVITY analysis; Subject Term: VAPOR-liquid equilibrium; Author-Supplied Keyword: Genetic algorithm; Author-Supplied Keyword: Interfacial area transport; Author-Supplied Keyword: Small-diameter; Author-Supplied Keyword: Wire-mesh sensor; Number of Pages: 17p; Document Type: Article
L3 - 10.1016/j.ces.2017.01.001
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=121378550&site=ehost-live&scope=site
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DB - aph
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TY - JOUR
AU - Dang, Zhuoran
AU - Wang, Guanyi
AU - Ju, Peng
AU - Yang, Xiaohong
AU - Bean, Robert
AU - Ishii, Mamoru
AU - Bajorek, Stephen
AU - Bernard, Matthew
T1 - Experimental study of interfacial characteristics of vertical upward air-water two-phase flow in 25.4 mm ID round pipe.
JO - International Journal of Heat & Mass Transfer
JF - International Journal of Heat & Mass Transfer
Y1 - 2017/05/02/May2017 Part B
VL - 108
M3 - Article
SP - 1825
EP - 1838
SN - 00179310
AB - An adiabatic upward air-water flow experiment was performed on a vertical pipe with 25.4 mm inner diameter to investigate the interface structure and characteristics. Local experiment parameters, including time-averaged void fraction, interfacial area concentration, bubble interfacial velocity and Sauter mean diameter were measured using a four-sensor conductivity probe with a data acquisition frequency of 100 kHz. Experiment data for 19 flow conditions was collected at 3 axial locations ( z/D = 15, 78, and 141) and 13 radial positions from r/R = −0.84 to 0.7. In the experimental study, the measuring range of superficial liquid and gas velocity were from 0.3 to 1.0 m/s and 0.03 to 11.0 m/s, respectively. The flow regimes ranged from bubbly flow to the transition of churn-turbulent to annular flow. The local measurement result agreed well with the drift flux model by Ishii (1977) and Kataoka (1987). The different interfacial structures in different flow regimes and two group bubble interfacial transfer were observed from the experiment result. This data will be used for the evaluation and extension of the current interfacial area transport equation. [ABSTRACT FROM AUTHOR]
AB - Copyright of International Journal of Heat & Mass Transfer is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - TWO-phase flow
KW - AIR-water interfaces
KW - ACQUISITION of data
KW - FLOW (Fluid dynamics)
KW - ANNULAR flow (Fluid dynamics)
KW - Four-sensor conductivity probe
KW - Interfacial characteristics
KW - Local measurement
KW - Pipe flow
KW - Two-phase flow
N1 - Accession Number: 121275578; Dang, Zhuoran 1 Wang, Guanyi 1 Ju, Peng 1 Yang, Xiaohong 1 Bean, Robert 1 Ishii, Mamoru 1; Email Address: ishii@purdue.edu Bajorek, Stephen 2 Bernard, Matthew 2; Affiliation: 1: School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907, USA 2: U.S. Nuclear Regulatory Commission, Rockville, MD 20852, USA; Source Info: May2017 Part B, Vol. 108, p1825; Subject Term: TWO-phase flow; Subject Term: AIR-water interfaces; Subject Term: ACQUISITION of data; Subject Term: FLOW (Fluid dynamics); Subject Term: ANNULAR flow (Fluid dynamics); Author-Supplied Keyword: Four-sensor conductivity probe; Author-Supplied Keyword: Interfacial characteristics; Author-Supplied Keyword: Local measurement; Author-Supplied Keyword: Pipe flow; Author-Supplied Keyword: Two-phase flow; Number of Pages: 14p; Document Type: Article
L3 - 10.1016/j.ijheatmasstransfer.2017.01.040
UR - https://auth.lib.unc.edu/ezproxy_auth.php?url=http://search.ebscohost.com/login.aspx?direct=true&db=aph&AN=121275578&site=ehost-live&scope=site
DP - EBSCOhost
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ER -
TY - JOUR
AU - E D Dickson
AU - D M Hamby
T1 - Building protection- and building shielding-factors for environmental exposure to radionuclides and monoenergetic photon emissions.
JO - Journal of Radiological Protection
JF - Journal of Radiological Protection
Y1 - 2019/09//
VL - 36
IS - 3
M3 - Article
SP - 1
EP - 1
SN - 09524746
AB - We describe a simplified method for calculating both building protection- and shielding-factors for generic one- and two-story housing-unit models that are source-term dependent. Typically, radionuclide-independent factors are applied generically to external dose coefficients to account for the radiation shielding effects of indoor residences. In reality, the shielding effectiveness of each housing-unit would change over time as the radionuclide mixture and gamma-ray energy spectrum change due to physical effects such as deposition, radioactive decay, weathering effects, and decontamination efforts. Thus, it is necessary to develop factors designed for multiple photon energy spectrums to generate a more realistic estimate of the shielding effectiveness of a particular building. It is impractical to develop factors specific to a spectrum of photons emitted by each radionuclide of interest. Therefore, Monte Carlo simulations have been performed for sixteen monoenergetic photon energies from 0.10 to 3.0 MeV to characterize the 3D radiation fluence through each housing-unit produced by two idealized, yet realistic, environmental exposure scenarios. Results of these simulations were then used to develop fitted logarithmic functions (extrapolated to 0.0 MeV) to correlate an estimated factor to any monoenergetic photon energy up to 3.0 MeV. To verify these functions, another series of Monte Carlo simulations were performed for a select set of radionuclides to develop radionuclide-specific building protection- and shielding-factors. Good agreement is achieved between factors estimated using the presented functions and those calculated directly using Monte Carlo methods. Factors predicted by these functions are found to be in general agreement with other study results reported on similar structures which applied various computational methods and source-terms. This study only focuses on generic one- and two-story homes to provide a practical application that can contribute to improve the preparedness for and the response to a nuclear or radiological emergency. [ABSTRACT FROM AUTHOR]
AB - Copyright of Journal of Radiological Protection is the property of IOP Publishing and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
KW - Radioisotopes
KW - Monoenergetic radiation
KW - Photon emission
KW - Radiation -- Dosage
KW - Building protection
N1 - Accession Number: 119568581; E D Dickson 1; Email Address: elijah.dickson@gmail.com; D M Hamby 2; Email Address: david.hamby@oregonstate.edu; Affiliations: 1: United States Nuclear Regulatory Commission, Rockville, DC 20555-0001, USA; 2: Department of Nuclear Engineering and Radiation Health Physics, Oregon State University, Corvallis, OR 97331, USA; Issue Info: Sep2016, Vol. 36 Issue 3, p1; Thesaurus Term: Radioisotopes; Subject Term: Monoenergetic radiation; Subject Term: Photon emission; Subject Term: Radiation -- Dosage; Subject Term: Building protection; NAICS/Industry Codes: 325180 Other Basic Inorganic Chemical Manufacturing; NAICS/Industry Codes: 325189 All other basic inorganic chemical manufacturing; Number of Pages: 1p; Document Type: Article
L3 - 10.1088/0952-4746/36/3/579
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DP - EBSCOhost
DB - eih
ER -