TY - JOUR T1 - Instrument response and self-noise analysis of dataloggers at the Idaho National Laboratory AN - 1855315993; 2017-001304 AB - This article describes the performance tests of three different digitizers that are currently in use by the Idaho National Laboratory seismic network and other seismic networks worldwide. The three digitizers are the PAR4CH from Symmetric Research, and the DAQ24USB-5V and DAQ24USB-XR from DAQSystems Inc. The theoretical response of each digitizer is discussed, followed by a description of how the filter coefficients were calculated. The empirically determined sensitivities are compared with the sensitivities reported by the manufacturers. Noise measurements were conducted to better understand the limitations of these digitizers. The digital filters used by all three digitizers are a combination of various sinc N filters; therefore, the filter coefficients were calculated by the convolution of N unit rectangle functions. The sensitivity as a function of the gain was measured and compared with the reported manufacturer's sensitivities. The DAQ24USB-5V and DAQ24USB-XR boards are highly accurate (1%) for the higher gain settings of 32 and 64. The PAR4CH board is the least accurate ( approximately 5%) of the three boards in this study. Noise measurements indicate that at lower sampling rates, 100 samples per second, the DAQ24USB-5V shows the lowest self-noise and is flat from 1 to 20 Hz, whereas the DAQ24USB-XR has higher self-noise at lower frequencies but is flat after 10 Hz. The PAR4CH has the flattest noise model, but the self-noise is about 30 dB greater than that of the DAQ24USB-5V. At higher sample rates, around 500 samples per second, the DAQ24USB is very flat up to about 200 Hz, after which it begins to drop, whereas the DAQ24USB-XR is relatively flat from 10 Hz till Nyquist, thus indicating that the DAQ24USB-XR is more suitable for applications that require higher sampling rates. JF - Seismological Research Letters AU - Bockholt, Blaine M Y1 - 2016/11/16/ PY - 2016 DA - 2016 Nov 16 SP - 104 EP - 112 PB - Seismological Society of America, El Cerrito, CA VL - 88 IS - 1 SN - 0895-0695, 0895-0695 KW - United States KW - Idaho KW - digital data KW - PAR4CH KW - seismographs KW - noise KW - Idaho National Laboratory KW - seismicity KW - DAQ24USB-5V KW - DAQ24USB-XR KW - seismic networks KW - Snake River plain KW - earthquakes KW - accuracy KW - instruments KW - filters KW - 19:Seismology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1855315993?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Seismological+Research+Letters&rft.atitle=Instrument+response+and+self-noise+analysis+of+dataloggers+at+the+Idaho+National+Laboratory&rft.au=Bockholt%2C+Blaine+M&rft.aulast=Bockholt&rft.aufirst=Blaine&rft.date=2016-11-16&rft.volume=88&rft.issue=1&rft.spage=104&rft.isbn=&rft.btitle=&rft.title=Seismological+Research+Letters&rft.issn=08950695&rft_id=info:doi/10.1785%2F0220160092 L2 - http://srl.geoscienceworld.org/ LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2017, American Geosciences Institute. Abstract, Copyright, Seismological Society of America | Reference includes data from GeoScienceWorld, Alexandria, VA, United States N1 - Date revised - 2017-01-01 N1 - Number of references - 25 N1 - PubXState - CA N1 - Document feature - illus. incl. 2 tables, sketch map N1 - Last updated - 2017-01-19 N1 - SubjectsTermNotLitGenreText - accuracy; DAQ24USB-5V; DAQ24USB-XR; digital data; earthquakes; filters; Idaho; Idaho National Laboratory; instruments; noise; PAR4CH; seismic networks; seismicity; seismographs; Snake River plain; United States DO - http://dx.doi.org/10.1785/0220160092 ER - TY - JOUR T1 - Physics-based simulation of multiple interacting crack growth in brittle rocks driven by thermal cooling AN - 1827897154; PQ0003724377 AB - Crack growth in hot brittle rocks, driven by thermal cooling, was simulated using a coupled two-dimensional discrete element and heat transport model that explicitly includes the random initiation and subsequent propagation of interacting cracks. The model clearly predicts that a quasi-hierarchical array of subparallel cracks, oriented along the direction of the temperature gradient, is formed under small to moderately large thermally generated strain load conditions. The simulation results also demonstrate that, after an initial transient, thermal cracks propagate in a stable fashion with a velocity that scales with ~ t super(-1/2). However, under large thermal strain loads, a more complicated geometry composed of cracks that curve and coalesce develops during the later stages of crack growth. JF - International Journal for Numerical and Analytical Methods in Geomechanics AU - Huang, Hai AU - Meakin, Paul AU - Malthe-Sorenssen, Anders AD - Idaho National Laboratory, Idaho Falls, ID, U.S.A. Y1 - 2016/11// PY - 2016 DA - November 2016 SP - 2163 EP - 2177 PB - Wiley-Blackwell, 111 River Street Hoboken NJ 07030-5774 United States VL - 40 IS - 16 SN - 0363-9061, 0363-9061 KW - ASFA 2: Ocean Technology Policy & Non-Living Resources; Water Resources Abstracts KW - Growth rate KW - Simulation Analysis KW - Velocity KW - Simulation KW - Strains KW - Temperature gradients KW - Strain KW - Cooling KW - Temperature Gradient KW - Growth KW - Rocks KW - Analytical Methods KW - Cracks KW - Modelling KW - Heat transport KW - Q2 09262:Methods and instruments KW - SW 0810:General UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1827897154?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Awaterresources&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=International+Journal+for+Numerical+and+Analytical+Methods+in+Geomechanics&rft.atitle=Physics-based+simulation+of+multiple+interacting+crack+growth+in+brittle+rocks+driven+by+thermal+cooling&rft.au=Huang%2C+Hai%3BMeakin%2C+Paul%3BMalthe-Sorenssen%2C+Anders&rft.aulast=Huang&rft.aufirst=Hai&rft.date=2016-11-01&rft.volume=40&rft.issue=16&rft.spage=2163&rft.isbn=&rft.btitle=&rft.title=International+Journal+for+Numerical+and+Analytical+Methods+in+Geomechanics&rft.issn=03639061&rft_id=info:doi/10.1002%2Fnag.2523 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-10-01 N1 - Last updated - 2016-12-22 N1 - SubjectsTermNotLitGenreText - Growth rate; Growth; Simulation; Temperature gradients; Strains; Heat transport; Modelling; Rocks; Analytical Methods; Simulation Analysis; Velocity; Cracks; Temperature Gradient; Cooling; Strain DO - http://dx.doi.org/10.1002/nag.2523 ER - TY - GEN T1 - Armor For The Grid AN - 1823285493 JF - Breaking Energy AU - Karen Bass | Idaho National Laboratory Y1 - 2016/09/26/ PY - 2016 DA - 2016 Sep 26 CY - New York PB - SyndiGate Media Inc KW - Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1823285493?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aabitrade&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=unknown&rft.jtitle=Breaking+Energy&rft.atitle=Armor+For+The+Grid&rft.au=Karen+Bass+%3B+Idaho+National+Laboratory&rft.aulast=Karen+Bass+%7C+Idaho+National+Laboratory&rft.aufirst=&rft.date=2016-09-26&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Breaking+Energy&rft.issn=&rft_id=info:doi/ LA - English DB - ProQuest Central N1 - Copyright - Copyright © 2016 Breaking Media, Inc. All rights reserved. Provided by SyndiGate Media Inc. (Syndigate.info). N1 - Last updated - 2016-09-27 ER - TY - GEN T1 - Students Designed A Robot To Handle Nuclear Fuel AN - 1805170397 JF - Breaking Energy AU - Nora Heikkinen | Idaho National Laboratory Y1 - 2016/07/18/ PY - 2016 DA - 2016 Jul 18 CY - New York PB - SyndiGate Media Inc KW - Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1805170397?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aabitrade&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=unknown&rft.jtitle=Breaking+Energy&rft.atitle=Students+Designed+A+Robot+To+Handle+Nuclear+Fuel&rft.au=Nora+Heikkinen+%3B+Idaho+National+Laboratory&rft.aulast=Nora+Heikkinen+%7C+Idaho+National+Laboratory&rft.aufirst=&rft.date=2016-07-18&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Breaking+Energy&rft.issn=&rft_id=info:doi/ LA - English DB - ProQuest Central N1 - Copyright - Copyright © 2016 Breaking Media, Inc. All rights reserved. Provided by SyndiGate Media Inc. (Syndigate.info). N1 - Last updated - 2016-07-19 ER - TY - JOUR T1 - Wellbore and groundwater temperature distribution eastern Snake River plain, Idaho; implications for groundwater flow and geothermal potential AN - 1824216041; 2016-085176 AB - A map of groundwater temperatures from the Eastern Snake River Plain (ESRP) regional aquifer can be used to identify and interpret important features of the aquifer, including aquifer flow direction, aquifer thickness, and potential geothermal anomalies. The ESRP is an area of high heat flow, yet most of this thermal energy fails to reach the surface, due to the heat being swept downgradient by the aquifer to the major spring complexes near Thousand Springs, ID, a distance of 300 km. Nine deep boreholes that fully penetrate the regional aquifer display three common features: (1) high thermal gradients beneath the aquifer, corresponding to high conductive heat flow in low-permeability hydrothermally-altered rocks; (2) isothermal temperature profiles within the aquifer, characteristic of an actively flowing groundwater; and (3) moderate thermal gradients in the vadose zone with values that indicate that over half of the geothermal heat flow is removed by advective transport in the regional aquifer system. This study utilized temperature data from 250 ESRP aquifer wells to evaluate regional aquifer flow direction, aquifer thickness, and potential geothermal anomalies. Because the thermal gradients are typically low in the aquifer, any measurement of groundwater temperature is a reasonable estimate of temperature throughout the aquifer thickness, allowing the construction of a regional aquifer temperature map for the ESRP. Mapped temperatures are used to identify cold thermal plumes associated with recharge from tributary valleys and adjacent uplands, and warm zones associated with geothermal input to the aquifer. Warm zones in the aquifer can have various causes, including local circulation of groundwater through the deep conductively dominated region, slow groundwater movement in low-permeability regions, or localized heat flow from deeper thermal features. JF - Journal of Volcanology and Geothermal Research AU - McLing, Travis L AU - Smith, Richard P AU - Smith, Robert W AU - Blackwell, David D AU - Roback, Robert C AU - Sondrup, Andrus J Y1 - 2016/06/15/ PY - 2016 DA - 2016 Jun 15 SP - 144 EP - 155 PB - Elsevier, Amsterdam VL - 320 SN - 0377-0273, 0377-0273 KW - United States KW - plumes KW - thermal alteration KW - unsaturated zone KW - preferential flow KW - metasomatism KW - temperature KW - ground water KW - geothermal systems KW - thermal anomalies KW - transport KW - heat flow KW - tracers KW - hydrothermal alteration KW - geothermal gradient KW - Idaho KW - fluid flow KW - advection KW - distribution KW - aquifers KW - geothermal energy KW - water table KW - geothermal exploration KW - boreholes KW - water wells KW - Snake River plain KW - permeability KW - 29A:Economic geology, geology of energy sources KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1824216041?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Volcanology+and+Geothermal+Research&rft.atitle=Wellbore+and+groundwater+temperature+distribution+eastern+Snake+River+plain%2C+Idaho%3B+implications+for+groundwater+flow+and+geothermal+potential&rft.au=McLing%2C+Travis+L%3BSmith%2C+Richard+P%3BSmith%2C+Robert+W%3BBlackwell%2C+David+D%3BRoback%2C+Robert+C%3BSondrup%2C+Andrus+J&rft.aulast=McLing&rft.aufirst=Travis&rft.date=2016-06-15&rft.volume=320&rft.issue=&rft.spage=144&rft.isbn=&rft.btitle=&rft.title=Journal+of+Volcanology+and+Geothermal+Research&rft.issn=03770273&rft_id=info:doi/10.1016%2Fj.jvolgeores.2016.04.006 L2 - http://www.sciencedirect.com/science/journal/03770273 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2016-01-01 N1 - Number of references - 110 N1 - Document feature - illus. incl. sect., 1 table, sketch maps N1 - Last updated - 2016-09-29 N1 - CODEN - JVGRDQ N1 - SubjectsTermNotLitGenreText - advection; aquifers; boreholes; distribution; fluid flow; geothermal energy; geothermal exploration; geothermal gradient; geothermal systems; ground water; heat flow; hydrothermal alteration; Idaho; metasomatism; permeability; plumes; preferential flow; Snake River plain; temperature; thermal alteration; thermal anomalies; tracers; transport; United States; unsaturated zone; water table; water wells DO - http://dx.doi.org/10.1016/j.jvolgeores.2016.04.006 ER - TY - GEN T1 - The Future Of Bioenergy Is In This Book-Less Library AN - 1789109477 JF - Breaking Energy AU - Cory Hatch | Idaho National Laboratory Y1 - 2016/05/16/ PY - 2016 DA - 2016 May 16 CY - New York PB - SyndiGate Media Inc KW - Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1789109477?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aabitrade&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=unknown&rft.jtitle=Breaking+Energy&rft.atitle=The+Future+Of+Bioenergy+Is+In+This+Book-Less+Library&rft.au=Cory+Hatch+%3B+Idaho+National+Laboratory&rft.aulast=Cory+Hatch+%7C+Idaho+National+Laboratory&rft.aufirst=&rft.date=2016-05-16&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Breaking+Energy&rft.issn=&rft_id=info:doi/ LA - English DB - ProQuest Central N1 - Copyright - Copyright © 2016 Breaking Media, Inc. All rights reserved. Provided by SyndiGate Media Inc. (Syndigate.info). N1 - Last updated - 2016-05-17 ER - TY - JOUR T1 - Selective Extraction of Heavy and Light Lanthanides from Aqueous Solution by Advanced Magnetic Nanosorbents. AN - 1781153606; 27018913 AB - Rare earth elements (REEs) make unique and vital contributions to our current world of technology. Separating and recycling REEs is of great importance to diversify the sources of REEs and advance the efficient use of REE resources when the supply is limited. In light of separation nanotechnology, diethylenetriamine-pentaacetic acid (DTPA) functionalized magnetic nanosorbents have been synthesized and investigated for the highly selective extraction of heavy (Sm-Ho) and light (La-Nd) lanthanides (Ln) from aqueous solutions. The results demonstrated that the separation factor (SF) between heavy-Ln and light-Ln groups reached the maximal value of 11.5 at low pH value of 2.0 in 30 min. For example, the SFs of Gd/La and Dy/La pairs were up to 10 times higher than that reported by other studies. Besides the excellent selectivity, our double-coated magnetic nanoparticles coupled with diethylenetriaminepentaacetic acid (dMNP-DTPA) nanosorbents are more advantageous in that the Ln(III) sorption was effectively and quickly (in 30 min) achieved in acid solutions with pH values as low as 2.0. Such attributes ensure a stronger adaptability to the harsh environments of REE recycling processes. Displacement phenomena were subsequently observed between the heavy-Ln and light-Ln ions that were coexisting in solution and competing for the same sorption sites, causing the increase in sorption capacity of heavy Ln on the surface of nanosorbents with time. The order of affinity of Ln(III) to DTPA-functionalized magnetic nanosorbents perfectly followed the corresponding stability constants between Ln(III) and nonimmobilized DTPA. Displacement phenomena and lanthanide contraction, as well as the surface nanostructures of DTPA-functionalized nanosorbents, significantly improved the separation factors of heavy-Ln/light-Ln pairs. The Ln(III) interaction with DTPA-functionalized magnetic nanosorbents followed the pseudo-second-order kinetics with a correlation coefficient extremely high and close to unity. JF - ACS applied materials & interfaces AU - Zhang, Huijin AU - McDowell, Rocklan G AU - Martin, Leigh R AU - Qiang, You AD - Aqueous Separations and Radiochemistry Department, Idaho National Laboratory , Idaho Falls, Idaho 83415, United States. Y1 - 2016/04/13/ PY - 2016 DA - 2016 Apr 13 SP - 9523 EP - 9531 VL - 8 IS - 14 KW - magnetic nanoparticles KW - rare earth elements KW - trivalent lanthanides KW - selective sorption KW - nanosorbents KW - magnetic separation UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1781153606?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Atoxline&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=ACS+applied+materials+%26+interfaces&rft.atitle=Selective+Extraction+of+Heavy+and+Light+Lanthanides+from+Aqueous+Solution+by+Advanced+Magnetic+Nanosorbents.&rft.au=Zhang%2C+Huijin%3BMcDowell%2C+Rocklan+G%3BMartin%2C+Leigh+R%3BQiang%2C+You&rft.aulast=Zhang&rft.aufirst=Huijin&rft.date=2016-04-13&rft.volume=8&rft.issue=14&rft.spage=9523&rft.isbn=&rft.btitle=&rft.title=ACS+applied+materials+%26+interfaces&rft.issn=1944-8252&rft_id=info:doi/10.1021%2Facsami.6b01550 LA - English DB - ProQuest Environmental Science Collection N1 - Date completed - 2016-08-23 N1 - Date created - 2016-04-13 N1 - Date revised - 2017-02-17 N1 - Last updated - 2017-02-23 DO - http://dx.doi.org/10.1021/acsami.6b01550 ER - TY - JOUR T1 - Sources of Biomass Feedstock Variability and the Potential Impact on Biofuels Production AN - 1776656746; PQ0002817137 AB - Terrestrial lignocellulosic biomass has the potential to be a carbon neutral and domestic source of fuels and chemicals. However, the innate variability of biomass resources, such as herbaceous and woody materials, and the inconsistency within a single resource due to disparate growth and harvesting conditions, presents challenges for downstream processes which often require materials that are physically and chemically consistent. Intrinsic biomass characteristics, including moisture content, carbohydrate and ash compositions, bulk density, and particle size/shape distributions are highly variable and can impact the economics of transforming biomass into value-added products. For instance, ash content increases by an order of magnitude between woody and herbaceous feedstocks (from 0.5 to 5 %, respectively) while lignin content drops by a factor of two (from 30 to 15 %, respectively). This increase in ash and reduction in lignin leads to biofuel conversion consequences, such as reduced pyrolysis oil yields for herbaceous products as compared to woody material. In this review, the sources of variability for key biomass characteristics are presented for multiple types of biomass. Additionally, this review investigates the major impacts of the variability in biomass composition on four conversion processes: fermentation, hydrothermal liquefaction, pyrolysis, and direct combustion. Finally, future research processes aimed at reducing the detrimental impacts of biomass variability on conversion to fuels and chemicals are proposed. [copy 2015 Battelle Energy Alliance, LLC, contract manager for Idaho National Laboratory. JF - BioEnergy Research AU - Williams, CLuke AU - Westover, Tyler L AU - Emerson, Rachel M AU - Tumuluru, Jaya Shankar AU - Li, Chenlin AD - Biofuels and Renewable Energy Technology Department, Idaho National Laboratory, Idaho Falls, ID, USA, luke.williams@inl.gov Y1 - 2016/03// PY - 2016 DA - March 2016 SP - 1 EP - 14 PB - Springer Science+Business Media, Van Godewijckstraat 30 Dordrecht 3311 GX Netherlands VL - 9 IS - 1 SN - 1939-1234, 1939-1234 KW - Environment Abstracts; Sustainability Science Abstracts UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1776656746?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Assamodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=BioEnergy+Research&rft.atitle=Sources+of+Biomass+Feedstock+Variability+and+the+Potential+Impact+on+Biofuels+Production&rft.au=Williams%2C+CLuke%3BWestover%2C+Tyler+L%3BEmerson%2C+Rachel+M%3BTumuluru%2C+Jaya+Shankar%3BLi%2C+Chenlin&rft.aulast=Williams&rft.aufirst=CLuke&rft.date=2016-03-01&rft.volume=9&rft.issue=1&rft.spage=1&rft.isbn=&rft.btitle=&rft.title=BioEnergy+Research&rft.issn=19391234&rft_id=info:doi/10.1007%2Fs12155-015-9694-y LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 121 N1 - Last updated - 2016-03-30 DO - http://dx.doi.org/10.1007/s12155-015-9694-y ER - TY - JOUR T1 - Experimental and numerical analysis of parallel reactant flow and transverse mixing with mineral precipitation in homogeneous and heterogeneous porous media AN - 1832603426; 772369-4 AB - Formation of mineral precipitates in the mixing interface between two reactant solutions flowing in parallel in porous media is governed by reactant mixing by diffusion and dispersion and is coupled to changes in porosity/permeability due to precipitation. The spatial and temporal distribution of mixing-dependent precipitation of barium sulfate in porous media was investigated with side-by-side injection of barium chloride and sodium sulfate solutions in thin rectangular flow cells packed with quartz sand. The results for homogeneous sand beds were compared to beds with higher or lower permeability inclusions positioned in the path of the mixing zone. In the homogeneous and high permeability inclusion experiments, BaSO (sub 4) precipitate (barite) formed in a narrow deposit along the length and in the center of the solution-solution mixing zone even though dispersion was enhanced within, and downstream of, the high permeability inclusion. In the low permeability inclusion experiment, the deflected BaSO (sub 4) precipitation zone broadened around one side and downstream of the inclusion and was observed to migrate laterally toward the sulfate solution. A continuum-scale fully coupled reactive transport model that simultaneously solves the nonlinear governing equations for fluid flow, transport of reactants and geochemical reactions was used to simulate the experiments and provide insight into mechanisms underlying the experimental observations. Migration of the precipitation zone in the low permeability inclusion experiment could be explained by the coupling effects among fluid flow, reactant transport and localized mineral precipitation reaction. Copyright 2016 Springer Science+Business Media Dordrecht and 2015 The Author(s) JF - Transport in Porous Media AU - Fox, Don T AU - Guo, Luanjing AU - Fujita, Yoshiko AU - Huang, Hai AU - Redden, George Y1 - 2016/02// PY - 2016 DA - February 2016 SP - 605 EP - 626 PB - Springer, Dordrecht VL - 111 IS - 3 SN - 0169-3913, 0169-3913 KW - solutions KW - simulation KW - barium chloride KW - parallel reactant flow KW - spatial distribution KW - laboratory studies KW - chemical reactions KW - transport KW - mixing KW - reactive transport KW - experimental studies KW - diffusion KW - sulfates KW - numerical analysis KW - fluid flow KW - porous materials KW - sodium sulfate KW - porosity KW - heterogeneous materials KW - precipitation KW - temporal distribution KW - barite KW - permeability KW - homogeneous materials KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1832603426?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefinprocess&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transport+in+Porous+Media&rft.atitle=Experimental+and+numerical+analysis+of+parallel+reactant+flow+and+transverse+mixing+with+mineral+precipitation+in+homogeneous+and+heterogeneous+porous+media&rft.au=Fox%2C+Don+T%3BGuo%2C+Luanjing%3BFujita%2C+Yoshiko%3BHuang%2C+Hai%3BRedden%2C+George&rft.aulast=Fox&rft.aufirst=Don&rft.date=2016-02-01&rft.volume=111&rft.issue=3&rft.spage=605&rft.isbn=&rft.btitle=&rft.title=Transport+in+Porous+Media&rft.issn=01693913&rft_id=info:doi/10.1007%2Fs11242-015-0614-6 L2 - http://springerlink.metapress.com/(l4tqdq55jga2hgb0achos1qm)/app/home/journal.asp?referrer=parent&backto=linkingpublicationresults,1:100342,1 LA - English DB - GeoRef N1 - Copyright - GeoRef in Process, Copyright 2017, American Geosciences Institute. After editing and indexing, this record will be added to Georef. Reference includes data supplied by Springer Verlag, Berlin, Federal Republic of Germany N1 - Number of references - 30 N1 - Document feature - illus. incl. 2 tables N1 - Last updated - 2017-01-24 N1 - SubjectsTermNotLitGenreText - barite; barium chloride; chemical reactions; diffusion; experimental studies; fluid flow; heterogeneous materials; homogeneous materials; laboratory studies; mixing; numerical analysis; parallel reactant flow; permeability; porosity; porous materials; precipitation; reactive transport; simulation; sodium sulfate; solutions; spatial distribution; sulfates; temporal distribution; transport DO - http://dx.doi.org/10.1007/s11242-015-0614-6 ER - TY - JOUR T1 - Aqueous rare earth element patterns and concentration in co-produced brines and industrial ponds, Wyoming AN - 1873351131; 2017-013922 AB - Aqueous Rare Earth Elements (REEs), stable isotopes, and geochemistry where quantified in 29 Wyoming samples spanning two basins and four industrial sites. Measurement of REEs at the ppt level in oily brines was possible thanks to the methods developed by INL co-authors. Isotope, geochemical, and trace analyses were performed at UW and by commercial laboratories. Basin samples contain elevated Eu and industrial sites contain elevated HREEs (Tb-Lu). In the sampled oil and gas co-produced waters Eu averages 18 ppt and can exceed 70 ppt. Respectively, these concentrations are 80 and 300 times greater than found in ocean waters (North Pacific Deep Water). In industrial power station ponds, total HREEs average 58 ppt and can exceed 190 ppt. The HREE enrichment at station ponds is also evident from their YbNASC:LaNASC ratio, which averages 16:1 for the sampled station ponds. In contrast, the ocean's YbNASC:LaNASC ratio is 1:2. Isotopic ratios range from -16.8 to 9.8 ppm for delta (super 13) C, -119 to -33 ppm for delta D, and -14 to +2 ppm for delta (super 18) O. To a first order approximation, aqueous REEs combine signatures for the geologic basin they sample, and also the field, but show little variation between formations within the same field. The basin signature for the Powder River Basin (PRB) is a Gd anomaly nearly as large as Eu after normalization, which distinguishes them from the Wind River Basin (WRB) where a similar Gd anomaly is absent. Fields also have a signature: In the PRB, field H has slight HREE enrichment over NPDW, but field P has HREE contents far greater than the NPDW. In the WRB, field M has slight HREE depletion, but field L has HREE enrichment. Although the PRB samples include common formations between fields H and P there is no detectable formation signature in the REEs independent of field signature. A formation signature is available in isotope and trace geochemistry. delta (super 13) C isotopes in some formations show evidence of biogenic natural gas, and industrial site isotopes conform to the superficial water delta (super 13) C range. All water samples are displaced to the right of the delta D-delta (super 18) O GMWL. Although all waters were sodium-chloride to sodium-sulfate type, trace geochemistry also includes information on source formation. REEs, isotopes, and trace elements offer enough information to identify the basin, field, and formation a water came from. JF - Abstracts with Programs - Geological Society of America AU - Nye, Charles AU - Quillinan, Scott AU - McLing, Travis L AU - Neupane, Ghanashyam AU - McLaughlin, J Fred AU - Bagdonas, Davin A AU - Anonymous Y1 - 2016 PY - 2016 DA - 2016 SP - Abstract no. 181 EP - 4 PB - Geological Society of America (GSA), Boulder, CO VL - 48 IS - 7 SN - 0016-7592, 0016-7592 KW - 02C:Geochemistry of rocks, soils, and sediments UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1873351131?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Aqueous+rare+earth+element+patterns+and+concentration+in+co-produced+brines+and+industrial+ponds%2C+Wyoming&rft.au=Nye%2C+Charles%3BQuillinan%2C+Scott%3BMcLing%2C+Travis+L%3BNeupane%2C+Ghanashyam%3BMcLaughlin%2C+J+Fred%3BBagdonas%2C+Davin+A%3BAnonymous&rft.aulast=Nye&rft.aufirst=Charles&rft.date=2016-01-01&rft.volume=48&rft.issue=7&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2016 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2017, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2017-01-01 N1 - PubXState - CO N1 - Last updated - 2017-03-02 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - The kISMET (permeability (K) and induced seismicity management for energy technologies) project; an underground field laboratory for investigating the relations between natural and induced fractures, stress field, and rock fabric AN - 1869032103; 2017-011506 AB - kISMET is part of the US Department of Energy's Subsurface Technology & Engineering Research (SubTER) crosscutting initiative for adaptive control of fractures, reactions, and flow in the subsurface. The project is located at the Sanford Underground Research Facility (SURF) in the former Homestake gold mine in Lead, SD. The kISMET site consists of five closely spaced near-vertical boreholes on the 4850 level that are designed for a series of hydraulic fracturing stress measurements and induced-fracture stimulation experiments. Four of the boreholes are HQ-sized holes that are 50 m in depth and will host monitoring sensors; in conjunction with a central NQ borehole they form a five-spot pattern at depth. The monitoring boreholes are located nearly equal 3 m away from the central borehole, allowing for very precise monitoring of fracture initiation and growth. The host rock is the Poorman Formation, a highly foliated phyllite that is steeply dipping at the kISMET site. Initial characterization of the site is being conducted using core samples, televiewer logs, and extensive preexisting geologic data. A straddle packer assembly will be installed at several depths in the central borehole to conduct stress measurements, and later to perform a series of hydrofracture stimulations. Preliminary analytical and numerical fracture initiation and growth model simulations conducted using existing geomechanical data for the Poorman phyllite suggest rock breakdown pressures in the range of 35-50 MPa. Two primary methods will be employed to monitor the experiments: continuous active-source seismic monitoring (CASSM) and electrical resistivity tomography (ERT); these will be complemented by passive microseismic (MEQ), pore pressure and injection rate monitoring. These experiments are aimed at understanding the effects of stress state, rock fabric, existing fractures, and stimulation approach on the character of the fracture(s) created (e.g., permeability enhancement, size, orientation, aperture), the fracturing process, and the associated induced microseismicity. Results of this research will be directly applicable to fracture stimulation and reservoir creation in Enhanced Geothermal Systems (EGS). JF - Abstracts with Programs - Geological Society of America AU - Dobson, Patrick F AU - Oldenburg, Curtis M AU - Daley, Thomas M AU - Birkholzer, Jens T AU - Cook, Paul J AU - Ajo-Franklin, Jonathan AU - Rutqvist, Jonny AU - Siler, Drew L AU - Kneafsey, Timothy J AU - Nakagawa, Seiji AU - Wu, Yuxin AU - Guglielmi, Yves AU - Ulrich, Craig AU - Wang, Herb F AU - Haimson, Bezalel C AU - Sone, Hiroki AU - Vigilante, Peter AU - Roggenthen, William M AU - Doe, Thomas W AU - Lee, Moo Y AU - Mattson, Earl D AU - Huang, Hai AU - Johnson, Timothy J AU - Morris, Joseph P AU - White, Joshua A AU - Johnson, Paul A AU - Coblentz, David D AU - Heise, Jaret AU - Anonymous Y1 - 2016 PY - 2016 DA - 2016 SP - Abstract no. 4 EP - 9 PB - Geological Society of America (GSA), Boulder, CO VL - 48 IS - 7 SN - 0016-7592, 0016-7592 KW - 27A:Economic geology, geology of ore deposits UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1869032103?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=The+kISMET+%28permeability+%28K%29+and+induced+seismicity+management+for+energy+technologies%29+project%3B+an+underground+field+laboratory+for+investigating+the+relations+between+natural+and+induced+fractures%2C+stress+field%2C+and+rock+fabric&rft.au=Dobson%2C+Patrick+F%3BOldenburg%2C+Curtis+M%3BDaley%2C+Thomas+M%3BBirkholzer%2C+Jens+T%3BCook%2C+Paul+J%3BAjo-Franklin%2C+Jonathan%3BRutqvist%2C+Jonny%3BSiler%2C+Drew+L%3BKneafsey%2C+Timothy+J%3BNakagawa%2C+Seiji%3BWu%2C+Yuxin%3BGuglielmi%2C+Yves%3BUlrich%2C+Craig%3BWang%2C+Herb+F%3BHaimson%2C+Bezalel+C%3BSone%2C+Hiroki%3BVigilante%2C+Peter%3BRoggenthen%2C+William+M%3BDoe%2C+Thomas+W%3BLee%2C+Moo+Y%3BMattson%2C+Earl+D%3BHuang%2C+Hai%3BJohnson%2C+Timothy+J%3BMorris%2C+Joseph+P%3BWhite%2C+Joshua+A%3BJohnson%2C+Paul+A%3BCoblentz%2C+David+D%3BHeise%2C+Jaret%3BAnonymous&rft.aulast=Dobson&rft.aufirst=Patrick&rft.date=2016-01-01&rft.volume=48&rft.issue=7&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2016 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2017, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2017-01-01 N1 - PubXState - CO N1 - Last updated - 2017-02-17 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Controlling the distribution of microbially induced calcite precipitation in the subsurface AN - 1869030201; 2017-009895 JF - V.M. Goldschmidt Conference - Program and Abstracts AU - Fujita, Yoshiko AU - Smith, Robert W AU - Ginn, Timothy R AU - Weathers, Tess AU - Anonymous Y1 - 2016 PY - 2016 DA - 2016 SP - 867 PB - Goldschmidt Conference, [varies] VL - 26 SN - 1042-7287, 1042-7287 KW - limestone KW - calcium KW - alkaline earth metals KW - experimental studies KW - calcite KW - sedimentary rocks KW - precipitation KW - metals KW - microbialite KW - carbonate rocks KW - carbonates KW - microorganisms KW - 01C:Mineralogy of non-silicates UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1869030201?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=V.M.+Goldschmidt+Conference+-+Program+and+Abstracts&rft.atitle=Controlling+the+distribution+of+microbially+induced+calcite+precipitation+in+the+subsurface&rft.au=Fujita%2C+Yoshiko%3BSmith%2C+Robert+W%3BGinn%2C+Timothy+R%3BWeathers%2C+Tess%3BAnonymous&rft.aulast=Fujita&rft.aufirst=Yoshiko&rft.date=2016-01-01&rft.volume=26&rft.issue=&rft.spage=867&rft.isbn=&rft.btitle=&rft.title=V.M.+Goldschmidt+Conference+-+Program+and+Abstracts&rft.issn=10427287&rft_id=info:doi/ L2 - http://goldschmidt.info/2016/uploads/abstracts/finalPDFs/867.pdf LA - English DB - GeoRef N1 - Conference title - Goldschmidt 2016 N1 - Copyright - GeoRef, Copyright 2017, American Geosciences Institute. N1 - Date revised - 2017-01-01 N1 - Last updated - 2017-02-17 N1 - SubjectsTermNotLitGenreText - alkaline earth metals; calcite; calcium; carbonate rocks; carbonates; experimental studies; limestone; metals; microbialite; microorganisms; precipitation; sedimentary rocks ER - TY - JOUR T1 - Stochastic exploration and the geologic context of enhanced geothermal system viability on the Snake River plain, Idaho AN - 1828846080; 2016-087140 AB - Geothermal energy depends on high subsurface temperature, adequate permeability and fracture volume, and accessible groundwater supply to support heat exchange with surrounding rock. Some regions may have adequate thermal resources but lack the necessary permeability or deep circulating water. Exploitation of such areas for geothermal energy could occur if permeability can be enhanced enough to provide the necessary heat exchange. These improvements to the geothermal reservoir would produce what is termed an "enhanced geothermal system" (EGS). The Snake River Plain (SRP) in southern Idaho is a geological region with high heat flux ( approximately 110 mW/m (super 2) ) that has been recommended as an EGS target. In this study, we consider how the geologic and thermal history of the SRP might influence its EGS potential. We describe the fracture distribution (mean = 28.63 fractures/10 m) in a welded tuff core recovered from one of the few deep boreholes located on the SRP and provide a preliminary discussion of the likely geomechanical behavior under in situ stress. Spatial autocorrelation of fracture features is defined with geostatistical techniques and used in a stochastic simulation of possible structures in other welded tuff reservoirs. Autocorrelation scales for the continuous date are on the order of 70 meters with high subsample scale variability (56 m). Results should aid in designing criteria for a hydraulic fracturing plan that would augment the permeability and connectivity of an SRP reservoir's preexisting fracture network. JF - Special Paper - Geological Society of America AU - Moody, Alex AU - Fairley, Jerry AU - Plummer, Mitchell Y1 - 2016 PY - 2016 DA - 2016 SP - 115 EP - 136 PB - Geological Society of America (GSA), Boulder, CO VL - 519 SN - 0072-1077, 0072-1077 KW - United States KW - hydraulic fracturing KW - Idaho KW - Global Positioning System KW - heat flux KW - geothermal engineering KW - enhanced recovery KW - porosity KW - thermal waters KW - geothermal energy KW - stochastic processes KW - heat transfer KW - reservoir properties KW - hydraulic conductivity KW - Snake River plain KW - permeability KW - 29A:Economic geology, geology of energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1828846080?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Special+Paper+-+Geological+Society+of+America&rft.atitle=Stochastic+exploration+and+the+geologic+context+of+enhanced+geothermal+system+viability+on+the+Snake+River+plain%2C+Idaho&rft.au=Moody%2C+Alex%3BFairley%2C+Jerry%3BPlummer%2C+Mitchell&rft.aulast=Moody&rft.aufirst=Alex&rft.date=2016-01-01&rft.volume=519&rft.issue=&rft.spage=115&rft.isbn=&rft.btitle=&rft.title=Special+Paper+-+Geological+Society+of+America&rft.issn=00721077&rft_id=info:doi/10.1130%2F2016.2519%2808%29 L2 - http://specialpapers.gsapubs.org/ LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2016-01-01 N1 - Number of references - 62 N1 - PubXState - CO N1 - Document feature - illus. incl. 3 tables N1 - Last updated - 2016-10-25 N1 - CODEN - GSAPAZ N1 - SubjectsTermNotLitGenreText - enhanced recovery; geothermal energy; geothermal engineering; Global Positioning System; heat flux; heat transfer; hydraulic conductivity; hydraulic fracturing; Idaho; permeability; porosity; reservoir properties; Snake River plain; stochastic processes; thermal waters; United States DO - http://dx.doi.org/10.1130/2016.2519(08) ER - TY - JOUR T1 - A three-dimensional geologic conceptual model beneath the Idaho National Lab's geothermal resource research area AN - 1812220455; 2016-072713 AB - The U.S. Department of Energy has initiated a research and development program to make a step change in Geothermal Resource Development called the Frontier Observatory for Research in Geothermal Energy (FORGE). The Snake River Geothermal Consortium (SRGC) and its partners, including the University of Idaho, have won a Phase I grant under the competition, proposing to host FORGE at the Idaho National Laboratory (INL). INL has established a Geothermal Resource Research Area (GRRA) for that purpose that is an approximately 100-km2 area along the northern margin of the eastern Snake River Plain (SRP). The initial phase of the FORGE initiative called for the development of a conceptual geologic model that demonstrates the suitability of the site for EGS development. The key features of a suitable EGS site are 1) temperatures of 175 -225 degrees C within 1.5 to 4 km of the surface and 2) low permeability ( approximately 1e-16 m (super 2) ). A 3-dimensional conceptual model is presented that integrates all of the available geologic, hydrogeologic, geophysical, and temperature data for this area. The conceptual model shows a system of four nested calderas within the Picabo volcanic field filled with thick, dense flows of rhyolite tuff. Temperature estimates are based on observations from nearby deep boreholes, which suggest that the 175 degrees C isotherm may be encountered between 2.4 and 3.8 km below the land surface. The variability of heat fluxes across the plain, wide distribution of recent volcanic activity, and areas of apparent low seismic activity in the shallow crust suggest a relatively shallow, magmatic heat source that persists, distinct from the time-progressive caldera eruptions associated with development of the plain. JF - Abstracts with Programs - Geological Society of America AU - St Clair, James T AU - Janis, Michael AU - Podgorney, Robert K AU - McCurry, Michael AU - Plummer, Mitchell A AU - Wood, Thomas R AU - Anonymous Y1 - 2016 PY - 2016 DA - 2016 SP - Abstract no. 15 EP - 3 PB - Geological Society of America (GSA), Boulder, CO VL - 48 IS - 6 SN - 0016-7592, 0016-7592 KW - 29A:Economic geology, geology of energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1812220455?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=A+three-dimensional+geologic+conceptual+model+beneath+the+Idaho+National+Lab%27s+geothermal+resource+research+area&rft.au=St+Clair%2C+James+T%3BJanis%2C+Michael%3BPodgorney%2C+Robert+K%3BMcCurry%2C+Michael%3BPlummer%2C+Mitchell+A%3BWood%2C+Thomas+R%3BAnonymous&rft.aulast=St+Clair&rft.aufirst=James&rft.date=2016-01-01&rft.volume=48&rft.issue=6&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/10.1130%2Fabs%2F2016RM-276197 LA - English DB - GeoRef N1 - Conference title - Geological Society of America, Rocky Mountain Section, 68th annual meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2016-01-01 N1 - PubXState - CO N1 - Last updated - 2016-08-18 N1 - CODEN - GAAPBC DO - http://dx.doi.org/10.1130/abs/2016RM-276197 ER - TY - JOUR T1 - Chronology and paleoclimate of late Pleistocene glaciation in the Trinity Alps, California, from cosmogenic (super 10) Be and numerical modelling AN - 1812219188; 2016-070669 AB - Glaciers are sensitive indicators of climate variation, especially to changes in precipitation and temperature over sub-millennial timescales. The western United States exhibits an excellent record of glaciation, but ongoing work across the region shows complex and yet-unexplained variation in timing of deglaciation at the end of the Last Glacial Maximum (LGM). The Trinity Alps of the southern Klamath Mountains in Northern California contain an excellent record of Pleistocene glaciation which can be used to fill a significant spatial gap in published glacial chronologies. Glacial deposits in the Trinity Alps were located using Google Earth and previously published maps, and were confirmed in the field. This study focuses on the Long Gulch and Trail Gulch Valleys at the northern margin of the Trinity Alps Wilderness Area. 24 samples from 5 moraines were taken for (super 10) Be dating, as well as 3 samples from striated bedrock. Of the 24, 10 samples were selected for exposure age analysis: 3 from bedrock, 5 from an LGM moraine and 2 from an older moraine. These ages should provide at least 2 ages of glacial abandonment within the valleys. Our new ages will be combined with 26 (super 10) Be ages collected between 2004-2012 to provide a detailed chronology of late Pleistocene glacial advances and retreat in the Klamath Mts. Our new ages will be combined with numerical modelling of glacial extent in Trail Gulch and Long Gulch using a coupled ice-flow model and mass and energy balance model. This will allow us to interpret the specific climate conditions for each glacial the two valleys. Initial dating results suggest that at least 2 pulses occurred during the LGM at approximately 15 and 19 ka. When paired with the final chronology, results from the paleoclimate modelling should provide new insights into the latitudinal variation in timing and character of paleoclimate change in the western US. JF - Abstracts with Programs - Geological Society of America AU - Dickey, Nathan W AU - Heermance, Richard V AU - Plummer, Mitchell A AU - Anonymous Y1 - 2016 PY - 2016 DA - 2016 SP - Abstract no. 3 EP - 3 PB - Geological Society of America (GSA), Boulder, CO VL - 48 IS - 4 SN - 0016-7592, 0016-7592 KW - 24:Quaternary geology KW - 03:Geochronology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1812219188?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Chronology+and+paleoclimate+of+late+Pleistocene+glaciation+in+the+Trinity+Alps%2C+California%2C+from+cosmogenic+%28super+10%29+Be+and+numerical+modelling&rft.au=Dickey%2C+Nathan+W%3BHeermance%2C+Richard+V%3BPlummer%2C+Mitchell+A%3BAnonymous&rft.aulast=Dickey&rft.aufirst=Nathan&rft.date=2016-01-01&rft.volume=48&rft.issue=4&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/10.1130%2Fabs%2F2016CD-274545 LA - English DB - GeoRef N1 - Conference title - Geological Society of America, Cordilleran Section, 112th annual meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2016-01-01 N1 - PubXState - CO N1 - Last updated - 2016-08-18 N1 - CODEN - GAAPBC DO - http://dx.doi.org/10.1130/abs/2016CD-274545 ER - TY - JOUR T1 - Structural controls of a geothermal system and effects on local groundwater aquifer, northern Cache Valley, Idaho AN - 1803776474; 2016-063162 AB - The Northern Cache Valley (NCV) of southeastern Idaho is a north-south trending Basin and Range graben that is receiving renewed interest for its geothermal potential. In the 1970s and 80s, geophysical and hydrological studies were undertaken, motivated by the presence of thermal wells and springs in the area. Geothermal exploration in this era culminated with the drilling of geothermal exploration wells by Sunedco Energy Development in 1979 and 1980. The test borehole temperatures were deemed too low (< 120 degrees C) for power production using technology available at the time. In January of 2014, a water well drilled to 79 meters, encountered Na-Cl-HCO (sub 3) water with a measured bottom hole temperature of 104 degrees C. Traditional magnesium corrected Na-K-Ca geothermometry of water from that well estimated the temperature of the thermal reservoir to be 204 degrees C. Due to this revived interest, new studies utilizing updated geochemical and geophysical techniques were undertaken. Present understanding of the NCV geothermal system suggests that fluid flow is associated with a fault(s) adjacent to Clifton Hill (aka Little Mountain) - a secondary horst complex rising from the floor of the Cache Valley graben. The existing data from the area is relatively sparse and is not suitable for pinpointing the location of faults thought to be acting as conduits for thermal water to travel from depth to the shallow subsurface. To investigate the locations of these faults and accurately characterize the plumbing of the geothermal system, high resolution potential field (gravity and magnetic) data was collected along lines made across the suspected location of the Clifton Hill bounding faults. Geophysical models of the subsurface using these data in conjunction with existing hydrogeological and geochemical data have aided in better determining fault locations. Groundwater level and aquifer temperature mapping in the area adjacent to the fault system has also been undertaken to explore the behavior of the shallow ground water aquifer in response to the discharge of thermal water through the system's faults. JF - Abstracts with Programs - Geological Society of America AU - Worthing, Wade AU - Wood, Thomas R AU - Glen, Jonathan AU - McLing, Travis L AU - Dobson, Patrick F AU - Ritzinger, Brent AU - Neupane, Ghanashyam AU - Thorne, Michael S AU - Anonymous Y1 - 2016 PY - 2016 DA - 2016 SP - Abstract no. 33 EP - 1 PB - Geological Society of America (GSA), Boulder, CO VL - 48 IS - 6 SN - 0016-7592, 0016-7592 KW - 29A:Economic geology, geology of energy sources KW - 16:Structural geology KW - 20:Applied geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1803776474?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Structural+controls+of+a+geothermal+system+and+effects+on+local+groundwater+aquifer%2C+northern+Cache+Valley%2C+Idaho&rft.au=Worthing%2C+Wade%3BWood%2C+Thomas+R%3BGlen%2C+Jonathan%3BMcLing%2C+Travis+L%3BDobson%2C+Patrick+F%3BRitzinger%2C+Brent%3BNeupane%2C+Ghanashyam%3BThorne%2C+Michael+S%3BAnonymous&rft.aulast=Worthing&rft.aufirst=Wade&rft.date=2016-01-01&rft.volume=48&rft.issue=6&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/10.1130%2Fabs%2F2016RM-276186 LA - English DB - GeoRef N1 - Conference title - Geological Society of America, Rocky Mountain Section, 68th annual meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2016-01-01 N1 - PubXState - CO N1 - Last updated - 2016-07-14 N1 - CODEN - GAAPBC DO - http://dx.doi.org/10.1130/abs/2016RM-276186 ER - TY - JOUR T1 - (super 135) Cs/ (super 137) Cs isotopic composition of environmental samples across Europe; environmental transport and source term emission applications AN - 1800393984; 2016-057502 AB - (super 135) Cs/ (super 137) Cs isotopic analyses represent an important tool for studying the fate and transport of radiocesium in the environment; in this work the (super 135) Cs/ (super 137) Cs isotopic composition in environmental samples taken from across Europe is reported. Surface soil and vegetation samples from western Russia, Ukraine, Austria, and Hungary show consistent aged thermal fission product (super 135) Cs/ (super 137) Cs isotope ratios of 0.58 + or - 0.01 (age corrected to 1/1/15), with the exception of one sample of soil-moss from Hungary which shows an elevated (super 135) Cs/ (super 137) Cs ratio of 1.78 + or - 0.12. With the exception of the outlier sample from Hungary, surface soil/vegetation data are in quantitative agreement with values previously reported for soils within the Chernobyl exclusion zone, suggesting that radiocesium at these locations is primarily composed of homogenous airborne deposition from Chernobyl. Seawater samples taken from the Irish Sea show (super 135) Cs/ (super 137) Cs isotope ratios of 1.22 + or - 0.11 (age corrected to 1/1/15), suggesting aged thermal fission product Cs discharged from Sellafield. The differences in (super 135) Cs/ (super 137) Cs isotope ratios between Sellafield, Chernobyl, and global nuclear weapons testing fallout indicate that (super 135) Cs/ (super 137) Cs isotope ratios can be utilized to discriminate between and track radiocesium transport from different nuclear production source terms, including major emission sources in Europe. Abstract Copyright (2016) Elsevier, B.V. JF - Journal of Environmental Radioactivity AU - Snow, Mathew S AU - Snyder, Darin C Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 258 EP - 263 PB - Elsevier, Oxford VL - 151 IS - Part 1 SN - 0265-931X, 0265-931X KW - solute transport KW - isotopes KW - England KW - Europe KW - ecosystems KW - vegetation KW - Great Britain KW - air pollution KW - radioactive isotopes KW - cesium KW - transport KW - Cumbria England KW - fallout KW - Sellafield England KW - Western Europe KW - pollutants KW - isotope ratios KW - alkali metals KW - solutes KW - pollution KW - United Kingdom KW - Cs-137 KW - Chernobyl nuclear accident KW - soil pollution KW - metals KW - nuclear facilities KW - Cs-135 KW - 22:Environmental geology KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1800393984?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Environmental+Radioactivity&rft.atitle=%28super+135%29+Cs%2F+%28super+137%29+Cs+isotopic+composition+of+environmental+samples+across+Europe%3B+environmental+transport+and+source+term+emission+applications&rft.au=Snow%2C+Mathew+S%3BSnyder%2C+Darin+C&rft.aulast=Snow&rft.aufirst=Mathew&rft.date=2016-01-01&rft.volume=151&rft.issue=Part+1&rft.spage=258&rft.isbn=&rft.btitle=&rft.title=Journal+of+Environmental+Radioactivity&rft.issn=0265931X&rft_id=info:doi/10.1016%2Fj.jenvrad.2015.10.025 L2 - http://www.sciencedirect.com/science/journal/0265931X LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2016-01-01 N1 - Document feature - illus. incl. 2 tables, sketch map N1 - Last updated - 2016-06-30 N1 - SubjectsTermNotLitGenreText - air pollution; alkali metals; cesium; Chernobyl nuclear accident; Cs-135; Cs-137; Cumbria England; ecosystems; England; Europe; fallout; Great Britain; isotope ratios; isotopes; metals; nuclear facilities; pollutants; pollution; radioactive isotopes; Sellafield England; soil pollution; solute transport; solutes; transport; United Kingdom; vegetation; Western Europe DO - http://dx.doi.org/10.1016/j.jenvrad.2015.10.025 ER - TY - JOUR T1 - New Simulation Schemes and Capabilities for the PHISICS/RELAP5-3D Coupled Suite AN - 1793275999; PQ0002706786 AB - PHISICS (Parallel and Highly Innovative Simulation for INL Code System) is a reactor physics package developed at the Idaho National Laboratory. It is composed of several modules: a nodal and semi-structured transport core solver (INSTANT), a depletion module (MRTAU), a time-dependent solver (Time Inte-grator), a cross-section interpolation and manipulation framework (MIXER), a criticality search module (CRITICALITY), and a fuel management and shuffling component (SHUFFLE). The PHISICS code has been coupled to the RELAP5-3D thermal-hydraulics code. Flexibility in the coupling among the different modules and with RELAP5-3D allows for several new integrated computational schemes and improvements with respect to current available options using NESTLE/RELAP5-3D. These schemes will be described in this paper. Moreover, the whole PHISICS package is fully parallelized, using the Message Passing Interface protocol. This allows for reduced computational times, while providing the capability to solve very detailed problems. JF - Nuclear Science and Engineering AU - Rabiti, C AU - Alfonsi, A AU - Epiney, A AD - Idaho National Laboratory, Idaho Falls, Idaho cristian.rabiti@inl.gov Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 104 EP - 118 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 182 IS - 1 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - RELAP5-3D KW - PHISICS KW - depletion KW - Joining KW - Computation KW - Packages KW - Computer simulation KW - Modules KW - Solvers KW - Searching KW - Mixers UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1793275999?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=New+Simulation+Schemes+and+Capabilities+for+the+PHISICS%2FRELAP5-3D+Coupled+Suite&rft.au=Rabiti%2C+C%3BAlfonsi%2C+A%3BEpiney%2C+A&rft.aulast=Rabiti&rft.aufirst=C&rft.date=2016-01-01&rft.volume=182&rft.issue=1&rft.spage=104&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-143 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-06-01 N1 - Number of references - 11 N1 - Last updated - 2016-06-02 DO - http://dx.doi.org/10.13182/NSE14-143 ER - TY - JOUR T1 - Modeling Moving Systems with RELAP5-3D AN - 1793275903; PQ0002706784 AB - The RELAP5-3D code is typically used to model stationary, land-based, thermal-hydraulic systems and contains specialized physics for the modeling of nuclear power plants. It can also model thermal-hydraulic systems in other inertial and accelerating frames of reference. By changing the magnitude of the gravitational vector through user input, RELAP5-3D can model thermal-hydraulic systems on planets, moons, and space stations. Additionally, the field equations were modified to model thermal-hydraulic systems in a noninertial frame, such as occur onboard moving craft or during earthquakes for land-based systems. Transient body forces affect fluid flow in thermal-fluid machinery aboard accelerating crafts during rotational and translational accelerations. It is useful to express the equations of fluid motion in the accelerating frame of reference attached to the moving craft. However, careful treatment of the rotational and translational kinematics is required to accurately capture the physics of fluid motion. Correlations for flow at angles between horizontal and vertical are generated via interpolation because limited experimental data exist. Equations for three-dimensional fluid motion in a noninertial frame of reference are developed. Two different systems for describing rotational motion are presented, user input is discussed, and examples of a modeled simple thermal-hydraulic system undergoing both rotational and translational motion are provided. JF - Nuclear Science and Engineering AU - Mesina, G L AU - Aumiller, D L AU - Buschman, F X AU - Kyle, M R AD - Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, Idaho 83402 george.mesina@inl.gov Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 83 EP - 95 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 182 IS - 1 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - RELAP5-3D KW - noninertial frame KW - Euler angles KW - Computational fluid dynamics KW - Mathematical models KW - Three dimensional motion KW - Fluids KW - Fluid flow KW - Crafts KW - Rotational KW - Mathematical analysis UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1793275903?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Modeling+Moving+Systems+with+RELAP5-3D&rft.au=Mesina%2C+G+L%3BAumiller%2C+D+L%3BBuschman%2C+F+X%3BKyle%2C+M+R&rft.aulast=Mesina&rft.aufirst=G&rft.date=2016-01-01&rft.volume=182&rft.issue=1&rft.spage=83&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE15-3 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-06-01 N1 - Number of references - 7 N1 - Last updated - 2016-06-02 DO - http://dx.doi.org/10.13182/NSE15-3 ER - TY - JOUR T1 - Development of Governing Equations Based on Six Fields for the RELAP Code AN - 1793273920; PQ0002706783 AB - The RELAP5-3D code is used to analyze nuclear reactor systems during steady-state and transient operations. Reactor transients that result in significant two-phase flow conditions and phase change, such as reflood scenarios, loss-of-coolant accidents, and others, can tax the current capabilities of the code to model the flow fields. Current codes, such as RELAP5-3D, RELAP-7, and TRACE, have mass, momentum, and energy governing equations for only two fields (liquid and vapor). The representation of two-phase flow phenomena is improved by increasing the number of fields. Therefore, governing equations based on six fields (liquid, vapor, small bubble, large bubble, small droplet, and large droplet) are derived in this paper for implementation in RELAP5-3D. JF - Nuclear Science and Engineering AU - Roth, Glenn A AU - Aydogan, Fatih AD - University of Idaho, Center for Advanced Energy Studies, 995 University Boulevard, Idaho Falls, Idaho 83401 roth1581@vandals.uidaho.edu Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 71 EP - 82 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 182 IS - 1 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - RELAP KW - two-phase flow KW - new fields KW - Nuclear reactors KW - Mathematical models KW - Droplets KW - Phase change KW - Liquids KW - Bubbles KW - Nuclear engineering KW - Mathematical analysis UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1793273920?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Development+of+Governing+Equations+Based+on+Six+Fields+for+the+RELAP+Code&rft.au=Roth%2C+Glenn+A%3BAydogan%2C+Fatih&rft.aulast=Roth&rft.aufirst=Glenn&rft.date=2016-01-01&rft.volume=182&rft.issue=1&rft.spage=71&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-149 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-06-01 N1 - Number of references - 9 N1 - Last updated - 2016-06-02 DO - http://dx.doi.org/10.13182/NSE14-149 ER - TY - JOUR T1 - A History of RELAP Computer Codes AN - 1793273874; PQ0002706779 AB - The RELAP5-3D (Reactor Excursion and Leak Analysis Program-Three Dimensional) code is the state-of-the art member of a series of computer programs developed at Idaho National Laboratory (INL) for modeling nuclear power plants. Originally funded by the U.S. Atomic Energy Commission [today's U.S. Nuclear Regulatory Commission (NRC)] to model small-break loss-of-coolant accidents (SBLOCAs) for pressurized water reactors (PWRs), the modeling capability and fidelity have grown with each successive release of the software. JF - Nuclear Science and Engineering AU - Mesina, G L AD - Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, Idaho 83402 Y1 - 2016/01// PY - 2016 DA - January 2016 SP - v EP - ix PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 182 IS - 1 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Software KW - Nuclear power plants KW - Nuclear power generation KW - Computer programs KW - Regulatory agencies KW - Pressurized water reactors KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1793273874?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=A+History+of+RELAP+Computer+Codes&rft.au=Mesina%2C+G+L&rft.aulast=Mesina&rft.aufirst=G&rft.date=2016-01-01&rft.volume=182&rft.issue=1&rft.spage=v&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-06-01 N1 - Last updated - 2016-06-02 ER - TY - JOUR T1 - Extremely Accurate Sequential Verification of RELAP5-3D AN - 1793272939; PQ0002706780 AB - Large computer programs like RELAP5-3D solve complex systems of governing, closure, and special process equations to model the underlying physics of thermal-hydraulic systems and include specialized physics for the modeling of nuclear power plants. Further, these programs incorporate other mechanisms for selecting optional code physics, input, output, data management, user interaction, and post-processing. Before being released to users, software quality assurance requires verification and validation. RELAP5-3D verification and validation are focused toward nuclear power plant applications. Verification ensures that the program is built right by checking that it meets its design specifications, comparing coding algorithms to equations, comparing calculations against analytical solutions, and the method of manufactured solutions. Sequential verification performs these comparisons initially, but thereafter only compares code calculations between consecutive code versions to demonstrate that no unintended changes have been introduced. An automated, highly accurate sequential verification method, based on previous work by Aumiller, has been developed for RELAP5-3D. It provides the ability to test that no unintended consequences result from code development. Moreover, it provides the means to test the following code capabilities: repeated time-step advancement, runs continued from a restart file, and performance of coupled analyses using the R5EXEC executive program. Analyses of the adequacy of the checks used in these comparisons are provided. JF - Nuclear Science and Engineering AU - Mesina, G L AU - Aumiller, D L AU - Buschman, F X AD - Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, Idaho 83402 george.mesina@inl.gov Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 1 EP - 12 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 182 IS - 1 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - RELAP5-3D KW - verification KW - governing equations KW - Nuclear power plants KW - Nuclear power generation KW - Computer programs KW - Mathematical models KW - Algorithms KW - Automation KW - Design analysis KW - Mathematical analysis UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1793272939?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Extremely+Accurate+Sequential+Verification+of+RELAP5-3D&rft.au=Mesina%2C+G+L%3BAumiller%2C+D+L%3BBuschman%2C+F+X&rft.aulast=Mesina&rft.aufirst=G&rft.date=2016-01-01&rft.volume=182&rft.issue=1&rft.spage=1&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-151 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-06-01 N1 - Number of references - 14 N1 - Last updated - 2016-08-08 DO - http://dx.doi.org/10.13182/NSE14-151 ER - TY - JOUR T1 - Qualitative and Quantitative Evaluation of Coupling Approaches for Coupling of RELAP5 and LabVIEW AN - 1793266684; PQ0002706787 AB - In the study and design of a nuclear power plant, extensive system modeling is necessary to determine how the reactor will perform in any given situation, not only in the normal performance of the reactor, but also in transients including unanticipated transients without scram and hypothetical accidents. One type of nuclear power plant under study is the hybrid energy system, which uses nuclear power to generate both electricity and heat for facilities. Obviously, the second steam cycle in the nuclear power plant requires several design updates and experiments. Unfortunately, the current versions of the Reactor Excursion and Leak Analysis Program (RELAP) do not allow online data streams from experimental facilities to the computational model of the secondary steam loop. Therefore, this study develops a coupling between RELAP5 and Laboratory Virtual Instrument Engineering Workbench (LabVIEW) to model primary and secondary coolant loops. In this way, the LabVIEW model can easily be connected to an experimental apparatus to provide an online data stream and the online transient behavior of an entire nuclear power plant system. This study shows two different coupling approaches and makes qualitative and quantitative comparisons between these approaches. This paper demonstrates the results of different couplings between the primary and secondary systems of a typical pressurized water reactor (PWR). The primary loop model is a four-loop PWR. The model has been executed with steady state and transients (in this case, a loss-of-coolant accident). The results of both coupling methods have been compared with the typical RELAP5 results. JF - Nuclear Science and Engineering AU - Fu, Zheng AU - Pack, Joshua AU - Aydogan, Fatih AD - University of Idaho, Center for Advanced Energy Studies, 995 University Boulevard, Idaho Falls, Idaho 83401 Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 119 EP - 134 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 182 IS - 1 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - LabVIEW KW - RELAP5 KW - coupling KW - Nuclear power plants KW - Nuclear power generation KW - Joining KW - Nuclear reactors KW - Pressurized water reactors KW - Online KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1793266684?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Qualitative+and+Quantitative+Evaluation+of+Coupling+Approaches+for+Coupling+of+RELAP5+and+LabVIEW&rft.au=Fu%2C+Zheng%3BPack%2C+Joshua%3BAydogan%2C+Fatih&rft.aulast=Fu&rft.aufirst=Zheng&rft.date=2016-01-01&rft.volume=182&rft.issue=1&rft.spage=119&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE15-4 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-06-01 N1 - Number of references - 7 N1 - Last updated - 2016-06-02 DO - http://dx.doi.org/10.13182/NSE15-4 ER - TY - JOUR T1 - RELAP5-3D User Tools AN - 1773917290; PQ0002706798 AB - To support the functionality of RELAP5-3D for best-estimate reactor simulation code, a variety of utility programs were developed at Idaho National Laboratory. Conversion and upgrades of RELAP5-3D to FORTRAN 95 required the upgrades of these utility programs as well. Pygmalion (Pygi) and the RELAP5-3D Graphical User Interface (RGUI) are two of the utility programs that were upgraded and enhanced. Pygi creates a copy of a RELAP5-3D input file with updated initial condition information. From the restart/plot file of the RELAP5-3D run of an input deck, Pygi obtains the final conditions for each component. It creates a new input file that replaces the original input file values with updated conditions. This provides an accurate and efficient means of creating new input decks with steady-state input conditions. RGUI is an alternative to the command line interface for performing RELAP5-3D-related work. RGUI provides single-interface access to other RELAP5-3D tools such as Pygi. It is highly configurable, allowing the user to customize the environment. The interface runs on both Linux and Windows. This suite of utility programs is continually being enhanced to provide better support for RELAP5-3D users. This technical note provides details of Pygi and RGUI functionality. Future plans for enhancements are also included. JF - Nuclear Technology AU - Forsmann, J Hope AD - Idaho National Laboratory, RELAP5-3D Development Team, 2525 Fremont Avenue, Idaho Falls, Idaho 83402, Hope.forsmann@inl.gov Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 213 EP - 217 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 193 IS - 1 SN - 0029-5450, 0029-5450 KW - Environment Abstracts KW - RELAP5-3D KW - RGUI KW - Pygmalion KW - USA, Idaho KW - Nuclear reactors KW - Simulation KW - ENA 07:General UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1773917290?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Technology&rft.atitle=RELAP5-3D+User+Tools&rft.au=Forsmann%2C+J+Hope&rft.aulast=Forsmann&rft.aufirst=J&rft.date=2016-01-01&rft.volume=193&rft.issue=1&rft.spage=213&rft.isbn=&rft.btitle=&rft.title=Nuclear+Technology&rft.issn=00295450&rft_id=info:doi/10.13182%2FNT14-141 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 9 N1 - Last updated - 2016-03-17 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Simulation; USA, Idaho DO - http://dx.doi.org/10.13182/NT14-141 ER - TY - JOUR T1 - BWR Station Blackout: A RISMC Analysis Using RAVEN and RELAP5-3D AN - 1773913737; PQ0002706795 AB - The existing fleet of nuclear power plants is in the process of having its lifetime extended and having the power generated from these plants increased via power uprates and improved operations. In order to evaluate the impact of these factors on the safety of the plant, the Risk-Informed Safety Margin Characterization (RISMC) pathway aims to provide insights to decision makers through a series of simulations of the plant dynamics for different initial conditions and accident scenarios. This paper presents a case study in order to show the capabilities of the RISMC methodology to assess the impact of power uprate of a boiling water reactor system during a station blackout accident scenario. We employ a system simulator code, RELAP5-3D, coupled with RA VEN, which performs the stochastic analysis. Our analysis is performed by (a) sampling values from a set of parameters from the uncertainty space of interest, (b) simulating the system behavior for that specific set of parameter values, and (c) analyzing the outcomes from the set of simulation runs. JF - Nuclear Technology AU - Mandelli, D AU - Smith, C AU - Riley, T AU - Nielsen, J AU - Alfonsi, A AU - Cogliati, J AU - Rabiti, C AU - Schroeder, J AD - Idaho National Laboratory, 2525 North Fremont Avenue, Idaho Falls, Idaho 83415, diego.mandelli@inl.gov Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 161 EP - 174 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 193 IS - 1 SN - 0029-5450, 0029-5450 KW - Environment Abstracts KW - Dynamic PRA KW - safety margin KW - station blackout KW - Risk assessment KW - Nuclear power plants KW - Accidents KW - Case studies KW - Nuclear reactors KW - Behavior KW - Risk factors KW - Safety KW - Simulation KW - ENA 07:General UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1773913737?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Technology&rft.atitle=BWR+Station+Blackout%3A+A+RISMC+Analysis+Using+RAVEN+and+RELAP5-3D&rft.au=Mandelli%2C+D%3BSmith%2C+C%3BRiley%2C+T%3BNielsen%2C+J%3BAlfonsi%2C+A%3BCogliati%2C+J%3BRabiti%2C+C%3BSchroeder%2C+J&rft.aulast=Mandelli&rft.aufirst=D&rft.date=2016-01-01&rft.volume=193&rft.issue=1&rft.spage=161&rft.isbn=&rft.btitle=&rft.title=Nuclear+Technology&rft.issn=00295450&rft_id=info:doi/10.13182%2FNT14-142 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 32 N1 - Last updated - 2016-03-17 N1 - SubjectsTermNotLitGenreText - Risk assessment; Nuclear power plants; Accidents; Nuclear reactors; Case studies; Behavior; Risk factors; Safety; Simulation DO - http://dx.doi.org/10.13182/NT14-142 ER - TY - JOUR T1 - Comparison of the PHISICS/RELAP5-3D Ring and Block Model Results for Phase I of the OECD/NEA MHTGR-350 Benchmark AN - 1773847177; PQ0002706789 AB - The Parallel and Highly Innovative Simulation for INL Code System (PHISICS) has been under development at Idaho National Laboratory since 2010. It consists of several modules providing improved coupled core simulation capability: INSTANT (Intelligent Nodal and Semi-structured Treatment for Advanced Neutron Transport) (three-dimensional nodal transport core calculations); MRTAU (Multi-Reactor Transmutation Analysis Utility) (depletion and decay heat generation); and modules performing criticality searches, fuel shuffling, and generalized perturbation. Coupling of the PHISICS code suite to the thermal-hydraulic system code RELAP5-3D was finalized in 2013, and as part of the verification and validation effort, the first phase of the Organisation for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA) MHTGR-350 benchmark has now been completed. The theoretical basis and latest development status of the coupled PHISICS/RELAP5-3D tool are described in more detail in a concurrent paper. This paper provides an overview of the OECD/NEA MHTGR-350 benchmark and presents the results of exercises 2 and 3 defined for phase I. Exercise 2 required the modeling of a stand-alone thermal fluids solution at the end of equilibrium cycle for the Modular High Temperature Gas-Cooled Reactor (MHTGR). The RELAP5-3D results of four subcases are discussed, consisting of various combinations of coolant bypass flows and material thermophysical properties. Exercise 3 required a coupled neutronics and thermal fluids solution, and the PHISICS/RELAP5-3D code suite was used to calculate the results of two subcases. The main focus of this paper is a comparison of results obtained with the traditional RELAP5-3D "ring" model approach against a much more detailed model that includes kinetics feedback on individual "block" level and thermal feedbacks on a triangular submesh. The higher fidelity that can be obtained by this block model is illustrated with comparison results on the temperature, power density, and flux distributions. It is shown that the ring model leads to significantly lower fuel temperatures (up to 10%) when compared with the higher-fidelity block model and that the additional model development and run-time efforts are worth the gains obtained in the improved spatial temperature and flux distributions. JF - Nuclear Technology AU - Strydom, G AU - Epiney, A S AU - Alfonsi, A AU - Rabiti, C AD - Idaho National Laboratory, Nuclear Science and Technology Division, 2525 North Fremont Avenue, Idaho Falls, Idaho 83415, gerhard.strydom@inl.gov Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 15 EP - 35 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 193 IS - 1 SN - 0029-5450, 0029-5450 KW - Environment Abstracts KW - HTGR KW - RELAP5-3D KW - PHISICS KW - Fuels KW - Temperature KW - Simulation KW - USA, Idaho KW - Nuclear reactors KW - Kinetics KW - High temperature KW - Economics KW - Nuclear energy KW - Decay KW - Benchmarks KW - Innovations KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1773847177?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Technology&rft.atitle=Comparison+of+the+PHISICS%2FRELAP5-3D+Ring+and+Block+Model+Results+for+Phase+I+of+the+OECD%2FNEA+MHTGR-350+Benchmark&rft.au=Strydom%2C+G%3BEpiney%2C+A+S%3BAlfonsi%2C+A%3BRabiti%2C+C&rft.aulast=Strydom&rft.aufirst=G&rft.date=2016-01-01&rft.volume=193&rft.issue=1&rft.spage=15&rft.isbn=&rft.btitle=&rft.title=Nuclear+Technology&rft.issn=00295450&rft_id=info:doi/10.13182%2FNT14-146 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 15 N1 - Last updated - 2016-03-17 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; High temperature; Kinetics; Fuels; Economics; Temperature; Simulation; Nuclear energy; Decay; Benchmarks; Innovations; USA, Idaho DO - http://dx.doi.org/10.13182/NT14-146 ER - TY - JOUR T1 - Degradation of phenolic compounds by the lignocellulose deconstructing thermoacidophilic bacterium Alicyclobacillus Acidocaldarius AN - 1768569538; PQ0002648816 AB - Alicyclobacillus acidocaldarius, a thermoacidophilic bacterium, has a repertoire of thermo- and acid-stable enzymes that deconstruct lignocellulosic compounds. The work presented here describes the ability of A. acidocaldarius to reduce the concentration of the phenolic compounds: phenol, ferulic acid, Ie-coumaric acid and sinapinic acid during growth conditions. The extent and rate of the removal of these compounds were significantly increased by the presence of micro-molar copper concentrations, suggesting activity by copper oxidases that have been identified in the genome of A. acidocaldarius. Substrate removal kinetics was first order for phenol, ferulic acid, Ie-coumaric acid and sinapinic acid in the presence of 50 mu M copper sulfate. In addition, laccase enzyme assays of cellular protein fractions suggested significant activity on a lignin analog between the temperatures of 45 and 90 degree C. This work shows the potential for A. acidocaldarius to degrade phenolic compounds, demonstrating potential relevance to biofuel production and other industrial processes. JF - Journal of Industrial Microbiology & Biotechnology AU - Aston, John E AU - Apel, William A AU - Lee, Brady D AU - Thompson, David N AU - Lacey, Jeffrey A AU - Newby, Deborah T AU - Reed, DavidW AU - Thompson, Vicki S AD - Biological and Chemical Processing Department, Idaho National Laboratory, Idaho Falls, ID, USA, john.aston@inl.gov Y1 - 2016/01// PY - 2016 DA - January 2016 SP - 13 EP - 23 PB - Springer Science+Business Media, Van Godewijckstraat 30 Dordrecht 3311 GX Netherlands VL - 43 IS - 1 SN - 1367-5435, 1367-5435 KW - Biotechnology and Bioengineering Abstracts; Microbiology Abstracts A: Industrial & Applied Microbiology KW - Genomes KW - Temperature effects KW - Bacteria KW - Growth conditions KW - sinapinic acid KW - Enzymes KW - Copper KW - Alicyclobacillus acidocaldarius KW - Ferulic acid KW - Phenols KW - lignocellulose KW - Laccase KW - Kinetics KW - Lignin KW - phenolic compounds KW - copper sulfate KW - Biofuels KW - W 30940:Products KW - A 01320:Microbial Degradation UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1768569538?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Abiotechresearch&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Industrial+Microbiology+%26+Biotechnology&rft.atitle=Degradation+of+phenolic+compounds+by+the+lignocellulose+deconstructing+thermoacidophilic+bacterium+Alicyclobacillus+Acidocaldarius&rft.au=Aston%2C+John+E%3BApel%2C+William+A%3BLee%2C+Brady+D%3BThompson%2C+David+N%3BLacey%2C+Jeffrey+A%3BNewby%2C+Deborah+T%3BReed%2C+DavidW%3BThompson%2C+Vicki+S&rft.aulast=Aston&rft.aufirst=John&rft.date=2016-01-01&rft.volume=43&rft.issue=1&rft.spage=13&rft.isbn=&rft.btitle=&rft.title=Journal+of+Industrial+Microbiology+%26+Biotechnology&rft.issn=13675435&rft_id=info:doi/10.1007%2Fs10295-015-1700-z LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-02-01 N1 - Number of references - 42 N1 - Last updated - 2016-03-17 N1 - SubjectsTermNotLitGenreText - Temperature effects; Genomes; Growth conditions; sinapinic acid; Enzymes; Copper; Ferulic acid; Phenols; lignocellulose; Laccase; Kinetics; Lignin; phenolic compounds; copper sulfate; Biofuels; Bacteria; Alicyclobacillus acidocaldarius DO - http://dx.doi.org/10.1007/s10295-015-1700-z ER - TY - JOUR T1 - The DOE subsurface (SubTER) initiative; revolutionizing responsible use of the subsurface for energy production and storage AN - 1849310478; 2016-109393 AB - The subsurface supplies more than 80% of the U.S.'s total energy needs through geothermal and hydrocarbon strategies and also provides vast potential for safe storage of CO (sub 2) and disposal of nuclear waste. Responsible and efficient use of the subsurface poses many challenges, many of which require the capability to monitor and manipulate sub-surface stress, fractures, and fluid flow at all scales. Adaptive control of subsurface fractures and flow is a multi-disciplinary challenge that, if achieved, has the potential to transform all subsurface energy strategies. As part of the U.S. Department of Energy's SubTER (Subsurface Technology and Engineering Research development and demonstration) initiative, a multi-National Laboratory team is developing next-generation approaches that will allow for adaptive control of subsurface fractures and flow. SubTER has identified an initial suite of technical thrust areas to focus work, and has initiated a number of small projects. This presentation will describe early progress associated with the SubTER technical topic areas of wellbore integrity, subsurface stress and induced seismicity, permeability manipulation and new subsurface signals. It will also describe SubTER plans, and provide a venue to solicit suggestions and discuss potential partnerships associated with future research directions. JF - American Geophysical Union Fall Meeting AU - Hubbard, Susan S AU - Walck, Marianne C AU - Blankenship, Doug AU - Bonneville, Alain AU - Bromhal, Grant S AU - Daley, Thomas M AU - Pawar, Rajesh AU - Polsky, Yarom AU - Mattson, Earl AU - Mellors, Roberts J AU - Anonymous Y1 - 2015/12// PY - 2015 DA - December 2015 SP - Abstract H51M EP - 1561 PB - American Geophysical Union, Washington, DC VL - 2015 KW - 29A:Economic geology, geology of energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1849310478?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=The+DOE+subsurface+%28SubTER%29+initiative%3B+revolutionizing+responsible+use+of+the+subsurface+for+energy+production+and+storage&rft.au=Hubbard%2C+Susan+S%3BWalck%2C+Marianne+C%3BBlankenship%2C+Doug%3BBonneville%2C+Alain%3BBromhal%2C+Grant+S%3BDaley%2C+Thomas+M%3BPawar%2C+Rajesh%3BPolsky%2C+Yarom%3BMattson%2C+Earl%3BMellors%2C+Roberts+J%3BAnonymous&rft.aulast=Hubbard&rft.aufirst=Susan&rft.date=2015-12-01&rft.volume=2015&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2015 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-12-16 N1 - CODEN - #07548 ER - TY - JOUR T1 - Late Pleistocene glacial chronology and paleoclimate of Big Cottonwood Canyon, Wasatch Range, Utah AN - 1840617996; 2016-095873 AB - Development of high-resolution glacial chronologies and paleoclimate modeling play a critical role in understanding modern climate variability. The glacial chronology of Big Cottonwood Canyon, Wasatch Range, Utah is poorly understood, and has not been assessed since the early 1900's. We used a variety of modern techniques to establish new understanding of Late Pleistocene glaciation in Big Cottonwood and other Wasatch Range canyons. An absolute chronology was established through the use of cosmogenic nuclide (beryllium-10) exposure age dating; we processed seventeen samples from moraine boulders, erratics, and striated bedrock throughout Big Cottonwood Canyon. Remote mapping of glacial landforms was completed using 2-meter LiDAR digital elevation models, and all identified landforms later verified and mapped in the field. We then used a coupled energy-mass-balance and ice-flow model to 1. infer ice extents in Big Cottonwood Canyon, incorporating neighboring canyons with well constrained maxima; and 2. explore paleoclimate conditions during the Late Pleistocene necessary to reproduce these ice extents. Results reveal new information regarding the influence of Pleistocene Lake Bonneville on climate and landscape evolution in the Wasatch Range during and following the Last Glacial Maximum. JF - American Geophysical Union Fall Meeting AU - Quirk, Brendon AU - Moore, Jeffrey R AU - Laabs, Benjamin J C AU - Caffee, Marc W AU - Plummer, Mitchell A AU - Anonymous Y1 - 2015/12// PY - 2015 DA - December 2015 SP - Abstract EP53A EP - 0997 PB - American Geophysical Union, Washington, DC VL - 2015 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1840617996?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Late+Pleistocene+glacial+chronology+and+paleoclimate+of+Big+Cottonwood+Canyon%2C+Wasatch+Range%2C+Utah&rft.au=Quirk%2C+Brendon%3BMoore%2C+Jeffrey+R%3BLaabs%2C+Benjamin+J+C%3BCaffee%2C+Marc+W%3BPlummer%2C+Mitchell+A%3BAnonymous&rft.aulast=Quirk&rft.aufirst=Brendon&rft.date=2015-12-01&rft.volume=2015&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2015 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-11-17 N1 - CODEN - #07548 ER - TY - JOUR T1 - Geodetic measurements and numerical modeling of deformation at Raft River geothermal field, Idaho, U.S.A. AN - 1815670715; 2016-075506 AB - To measure time-dependent deformation at the Raft River geothermal field in Cassia County in Southwestern Idaho, we analyze interferometric synthetic aperture radar (InSAR) data acquired between 2006 and 2015 by several satellite missions, including: Envisat, ALOS, TerraSAR-X, and TanDEM-X. The resulting time-series analysis indicates that the deformation began in late 2007, shortly after a 13-megawatt geothermal power plant began commercial production. The rate of deformation appears to be decreasing over time since 2008. The resulting maps of deformation show primarily uplift with some subsidence. The uplift signal is located in an approximately 8-km-by-5-km area centered near three injection wells that recycle produced brine into the Salt Lake formation, which consists of Miocene-Pliocene lacustrine deposits, volcanic tuffs, and lava flows. Subsidence occurs in an adjacent approximately 4-km-by-4-km area to the northwest. These two signatures remain in the same location in all of the well-correlated interferometric pairs since 2008. Although all production wells are also located inside the area experiencing uplift, most of them are close to the boundary that separates the two areas, and likely associated with the steeply dipping Bridge Fault zone. We explore the relative roles of thermal (T), and hydrological (H) processes on mechanical deformation (M). To do so, we use finite element based numerical models to calculate the time-dependent deformation field due to thermal contraction/expansion of rock (T-M coupling), and changes in pore pressure (H-M coupling). JF - American Geophysical Union Fall Meeting AU - Ali, Syed Tabrez AU - Feigl, Kurt L AU - Moore, Joseph AU - Plummer, Mitchell Aaron AU - Warren, Ian AU - Anonymous Y1 - 2015/12// PY - 2015 DA - December 2015 SP - Abstract G13B EP - 05 PB - American Geophysical Union, Washington, DC VL - 2015 KW - 18:Solid-earth geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1815670715?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Geodetic+measurements+and+numerical+modeling+of+deformation+at+Raft+River+geothermal+field%2C+Idaho%2C+U.S.A.&rft.au=Ali%2C+Syed+Tabrez%3BFeigl%2C+Kurt+L%3BMoore%2C+Joseph%3BPlummer%2C+Mitchell+Aaron%3BWarren%2C+Ian%3BAnonymous&rft.aulast=Ali&rft.aufirst=Syed&rft.date=2015-12-01&rft.volume=2015&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2015 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-09-01 N1 - CODEN - #07548 ER - TY - JOUR T1 - Rapid Analysis of Inorganic Species in Herbaceous Materials Using Laser-Induced Breakdown Spectroscopy AN - 1808651778; PQ0003214914 AB - Inorganic compounds in biomass, often referred to as ash, are known to be problematic in the thermochemical conversion of biomass to bio-oil or syngas and, ultimately, hydrocarbon fuels because they negatively influence reaction pathways, contribute to fouling and corrosion, poison catalysts, and impact waste streams. The most common ash-analysis methods, such as inductively coupled plasma-optical emission spectrometry/mass spectrometry (ICP-OES/MS), require considerable time and expensive reagents. Laser-induced breakdown spectroscopy (LIBS) is emerging as a technique for rapid analysis of the inorganic constituents in a wide range of biomass materials. This study compares analytical results using LIBS data to results obtained from three separate ICP-OES/MS methods for 12 samples, including six standard reference materials. Analyzed elements include aluminum, calcium, iron, magnesium, manganese, phosphorus, potassium, sodium, and silicon, and results show that concentrations can be measured with an uncertainty of approximately 100 parts per million using univariate calibration models and relatively few calibration samples. These results indicate that the accuracy of LIBS is comparable to that of ICP-OES methods and indicate that some acid-digestion methods for ICP-OES may not be reliable for Na and Al. These results also demonstrate that germanium can be used as an internal standard to improve the reliability and accuracy of measuring many elements of interest, and that LIBS can be used for rapid determination of total ash in biomass samples. Key benefits of LIBS include little sample preparation, no reagent consumption, and the generation of meaningful analytical data instantaneously. JF - Industrial Biotechnology AU - Westover, Tyler L AU - Emerson, Rachel M AD - Energy Sciences Laboratory, Biofuels and Renewable Energy Technologies Department, Idaho National Laboratory, Idaho Falls, ID Y1 - 2015/12// PY - 2015 DA - December 2015 SP - 322 EP - 330 PB - Mary Ann Liebert, Inc. Publishers, 140 Huguenot St 3rd Fl New Rochelle NY 10801 United States VL - 11 IS - 6 SN - 1550-9087, 1550-9087 KW - Biotechnology and Bioengineering Abstracts; Microbiology Abstracts A: Industrial & Applied Microbiology KW - Fouling KW - Inorganic compounds KW - Calcium KW - Data processing KW - Hydrocarbons KW - Fuels KW - Phosphorus KW - Wastes KW - Potassium KW - Spectroscopy KW - Biomass KW - Streams KW - Mass spectroscopy KW - Sodium KW - Aluminum KW - Catalysts KW - Magnesium KW - Manganese KW - Iron KW - A 01320:Microbial Degradation KW - W 30945:Fermentation & Cell Culture UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1808651778?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Abiotechresearch&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Industrial+Biotechnology&rft.atitle=Rapid+Analysis+of+Inorganic+Species+in+Herbaceous+Materials+Using+Laser-Induced+Breakdown+Spectroscopy&rft.au=Westover%2C+Tyler+L%3BEmerson%2C+Rachel+M&rft.aulast=Westover&rft.aufirst=Tyler&rft.date=2015-12-01&rft.volume=11&rft.issue=6&rft.spage=322&rft.isbn=&rft.btitle=&rft.title=Industrial+Biotechnology&rft.issn=15509087&rft_id=info:doi/10.1089%2Find.2015.0019 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-07-01 N1 - Number of references - 20 N1 - Last updated - 2016-08-04 N1 - SubjectsTermNotLitGenreText - Fouling; Inorganic compounds; Data processing; Calcium; Hydrocarbons; Fuels; Wastes; Phosphorus; Potassium; Biomass; Spectroscopy; Streams; Mass spectroscopy; Sodium; Aluminum; Catalysts; Magnesium; Iron; Manganese DO - http://dx.doi.org/10.1089/ind.2015.0019 ER - TY - JOUR T1 - Spatial gradients, wave gradiometry, and large N arrays AN - 1800396218; 2016-058452 AB - Accuracy of spatial gradients derived from wave field data recorded on a "geodetic" seismic array depends on the spatial distribution of array elements, signal-to-ambient-noise ratio, site amplitude statics, and instrument calibration. Application of the wave gradients in wave gradiometry additionally requires an accurate estimate of the wave field at the test location that is, in turn, subject to the same sources of noise, compounding inaccuracy in estimates of wave apparent velocity, amplitude changes, and direction. The spatial distribution of array elements can be controlled for a particular array design to yield potentially accurate spatial gradients. However, dense, large N arrays naturally alleviate problems with site statics, instrument calibration, and incoherent noise when the inverse problem is posed such that wave gradients and the wave field at the test location become the unknowns; both the wave gradients and test wave field become averages of the data over the array, reducing the effect of noise. A Taylor's series expansion of the wave field around any test point within the array becomes possible, even at those places that do not contain an array element. The resulting wave gradiometry parameters improve proportional to the number of array elements used. This method is used to examine the wave field using data from a 180 m x 300 m dense array associated with a 3D controlled source seismic experiment in southeastern Ohio demonstrating the complexity of the wavefield due to scattering in near-surface structure. The method is also used to analyze teleseismic P waves from the Long Beach, California, NodalSeismic array. JF - American Geophysical Union Fall Meeting AU - Langston, C A AU - Bockholt, B AU - Barker, L AU - Anonymous Y1 - 2015/12// PY - 2015 DA - December 2015 SP - Abstract S24B EP - 05 PB - American Geophysical Union, Washington, DC VL - 2015 KW - 19:Seismology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1800396218?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Spatial+gradients%2C+wave+gradiometry%2C+and+large+N+arrays&rft.au=Langston%2C+C+A%3BBockholt%2C+B%3BBarker%2C+L%3BAnonymous&rft.aulast=Langston&rft.aufirst=C&rft.date=2015-12-01&rft.volume=2015&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2015 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-06-30 N1 - CODEN - #07548 ER - TY - JOUR T1 - Reassessing site effects in Idaho National Laboratory in light of new data AN - 1784737850; 2016-036072 AB - The impact of local site conditions on the amplification of ground motions and associated damage to infrastructure has long been known. Modeling site effects is a fundamental step in the development of a site-specific seismic hazard curve and soil surface spectra in the seismic design of nuclear facilities. Five accelerometers have been installed near facilities at Idaho National Laboratory (INL) since 2013. A large number of ground motions from regional earthquakes (magnitudes 3.0 to 5.0) have been recorded, including the January 3, 2015, M5.0 Challis, ID, earthquake, providing a valuable dataset for studying site response at INL, especially wave propagation in a unique profile consisting of basalt that is fractured and interbedded with unconsolidated sediments. Previous site-response analyses conducted at INL have been based on one-dimensional (1D) equivalent-linear analysis using statistically generated soil profiles with shallow depths (up to 65 ft) (e.g., Payne and Costantino, 2003). While these analyses followed appropriate codes and standards for developing soil design spectra, they did not consider 1) representativeness of statistically generated soil velocity profiles, 2) the influence of strong velocity reversal below the elastic half-space boundary, and 3) two-dimensional (2D) or three-dimensional (3D) scattering effects due to sedimentary interbeds. The objective of this study is to investigate the significance of these issues using recent ground motion observations, with the ultimate goal of informing future site response and seismic hazard analyses. In this study, we first evaluate the effectiveness of the soil amplification function currently employed in seismic hazard analysis at INL by comparing it to the amplification observed from recorded ground motions. We then predict site response from alternative 1D models using measured shear wave velocity profiles with and without consideration of basalt-sediment sequence. Finally, we investigate scattering effects by using a numerical model which incorporates 3D heterogeneity of basalt and sedimentary interbeds. We observe that sedimentary interbeds can significantly reduce the amplification between 5 and 20 Hz, and the amplification function currently employed results in great conservatism. JF - American Geophysical Union Fall Meeting AU - Zhu, Jing AU - Baise, Laurie G AU - Bolisetti, Chandrakanth AU - Coleman, Justin L AU - Anonymous Y1 - 2015/12// PY - 2015 DA - December 2015 SP - Abstract S43B EP - 2813 PB - American Geophysical Union, Washington, DC VL - 2015 KW - 19:Seismology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1784737850?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Reassessing+site+effects+in+Idaho+National+Laboratory+in+light+of+new+data&rft.au=Zhu%2C+Jing%3BBaise%2C+Laurie+G%3BBolisetti%2C+Chandrakanth%3BColeman%2C+Justin+L%3BAnonymous&rft.aulast=Zhu&rft.aufirst=Jing&rft.date=2015-12-01&rft.volume=2015&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2015 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-04-28 N1 - CODEN - #07548 ER - TY - JOUR T1 - Strategic supply system design - a holistic evaluation of operational and production cost for a biorefinery supply chain AN - 1776650311; PQ0002784080 AB - Pioneer cellulosic biorefineries across the United States rely on a conventional feedstock supply system based on one-year contracts with local growers, who harvest, locally store, and deliver feedstock in low-density format to the conversion facility. While the conventional system is designed for high biomass yield areas, pilot scale operations have experienced feedstock supply shortages and price volatilities due to reduced harvests and competition from other industries. Regional supply dependency and the inability to actively manage feedstock stability and quality, provide operational risks to the biorefinery, which translate into higher investment risk. The advanced feedstock supply system based on a network of depots can mitigate many of these risks and enable wider supply system benefits. This paper compares the two concepts from a system-level perspective beyond mere logistic costs. It shows that while processing operations at the depot increase feedstock supply costs initially, they enable wider system benefits including supply risk reduction (leading to lower interest rates on loans), industry scale-up, conversion yield improvements, and reduced handling equipment and storage costs at the biorefinery. When translating these benefits into cost reductions per liter of gasoline equivalent (LGE), we find that total cost reductions between -$0.46 to -$0.21 per LGE for biochemical and -$0.32 to -$0.12 per LGE for thermochemical conversion pathways are possible. Naturally, these system level benefits will differ between individual actors along the feedstock supply chain. Further research is required with respect to depot sizing, location, and ownership structures. Published 2015. This article is a U.S. Government work and is in the public domain in the USA. Biofuels, Bioproducts and Biorefining published by Society of Industrial Chemistry and John Wiley & Sons Ltd. JF - Biofuels, Bioproducts and Biorefining AU - Lamers, Patrick AU - Tan, Eric CD AU - Searcy, Erin M AU - Scarlata, Christopher J AU - Cafferty, Kara G AU - Jacobson, Jacob J AD - Idaho National Laboratory, Idaho Falls, ID, USA. Y1 - 2015/11// PY - 2015 DA - November 2015 SP - 648 EP - 660 PB - Wiley-Blackwell, 111 River Street Hoboken NJ 07030-5774 United States VL - 9 IS - 6 SN - 1932-104X, 1932-104X KW - Sustainability Science Abstracts; Environment Abstracts; Biotechnology and Bioengineering Abstracts UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1776650311?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Abiotechresearch&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Biofuels%2C+Bioproducts+and+Biorefining&rft.atitle=Strategic+supply+system+design+-+a+holistic+evaluation+of+operational+and+production+cost+for+a+biorefinery+supply+chain&rft.au=Lamers%2C+Patrick%3BTan%2C+Eric+CD%3BSearcy%2C+Erin+M%3BScarlata%2C+Christopher+J%3BCafferty%2C+Kara+G%3BJacobson%2C+Jacob+J&rft.aulast=Lamers&rft.aufirst=Patrick&rft.date=2015-11-01&rft.volume=9&rft.issue=6&rft.spage=648&rft.isbn=&rft.btitle=&rft.title=Biofuels%2C+Bioproducts+and+Biorefining&rft.issn=1932104X&rft_id=info:doi/10.1002%2Fbbb.1575 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Last updated - 2016-03-30 DO - http://dx.doi.org/10.1002/bbb.1575 ER - TY - JOUR T1 - A third-order implicit discontinuous Galerkin method based on a Hermite WENO reconstruction for time-accurate solution of the compressible Navier-Stokes equations AN - 1727677057; PQ0002135104 AB - A space and time third-order discontinuous Galerkin method based on a Hermite weighted essentially non-oscillatory reconstruction is presented for the unsteady compressible Euler and Navier-Stokes equations. At each time step, a lower-upper symmetric Gauss-Seidel preconditioned generalized minimal residual solver is used to solve the systems of linear equations arising from an explicit first stage, single diagonal coefficient, diagonally implicit Runge-Kutta time integration scheme. The performance of the developed method is assessed through a variety of unsteady flow problems. Numerical results indicate that this method is able to deliver the designed third-order accuracy of convergence in both space and time, while requiring remarkably less storage than the standard third-order discontinous Galerkin methods, and less computing time than the lower-order discontinous Galerkin methods to achieve the same level of temporal accuracy for computing unsteady flow problems. A space and time third-order discontinuous Galerkin method based on a Hermite weighted essentially non-oscillatory reconstruction is presented for the unsteady compressible Euler and Navier-Stokes equations. Numerical results indicate that this method is able to deliver the designed third-order accuracy of convergence in both space and time while requiring less computing time than the lower-order discontinuous Galerkin methods to achieve the same level of temporal accuracy for computing unsteadyflow problems. JF - International Journal for Numerical Methods in Fluids AU - Xia, Yidong AU - Liu, Xiaodong AU - Luo, Hong AU - Nourgaliev, Robert AD - Idaho National Laboratory, Idaho Falls, Idaho, USA. Y1 - 2015/11// PY - 2015 DA - November 2015 SP - 416 EP - 435 PB - Wiley-Blackwell, 111 River Street Hoboken NJ 07030-5774 United States VL - 79 IS - 8 SN - 0271-2091, 0271-2091 KW - ASFA 2: Ocean Technology Policy & Non-Living Resources; Aqualine Abstracts; Water Resources Abstracts KW - Storage KW - Mathematical models KW - Navier-Stokes equations KW - Fluid dynamics KW - Unsteady Flow KW - Standards KW - Unsteady flow KW - AQ 00001:Water Resources and Supplies KW - SW 0810:General KW - Q2 09162:Methods and instruments UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1727677057?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aaqualine&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=International+Journal+for+Numerical+Methods+in+Fluids&rft.atitle=A+third-order+implicit+discontinuous+Galerkin+method+based+on+a+Hermite+WENO+reconstruction+for+time-accurate+solution+of+the+compressible+Navier-Stokes+equations&rft.au=Xia%2C+Yidong%3BLiu%2C+Xiaodong%3BLuo%2C+Hong%3BNourgaliev%2C+Robert&rft.aulast=Xia&rft.aufirst=Yidong&rft.date=2015-11-01&rft.volume=79&rft.issue=8&rft.spage=416&rft.isbn=&rft.btitle=&rft.title=International+Journal+for+Numerical+Methods+in+Fluids&rft.issn=02712091&rft_id=info:doi/10.1002%2Ffld.4057 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-10-01 N1 - Last updated - 2016-02-04 N1 - SubjectsTermNotLitGenreText - Mathematical models; Navier-Stokes equations; Fluid dynamics; Unsteady flow; Storage; Standards; Unsteady Flow DO - http://dx.doi.org/10.1002/fld.4057 ER - TY - JOUR T1 - An Efficient and Cost-Effective Method for Preparing Transmission Electron Microscopy Samples from Powders AN - 1846406774; PQ0003836037 AB - The preparation of transmission electron microcopy (TEM) samples from powders with particle sizes larger than ~100 nm poses a challenge. The existing methods are complicated and expensive, or have a low probability of success. Herein, we report a modified methodology for preparation of TEM samples from powders, which is efficient, cost-effective, and easy to perform. This method involves mixing powders with an epoxy on a piece of weighing paper, curing the powder-epoxy mixture to form a bulk material, grinding the bulk to obtain a thin foil, punching TEM discs from the foil, dimpling the discs, and ion milling the dimpled discs to electron transparency. Compared with the well established and robust grinding-dimpling-ion-milling method for TEM sample preparation for bulk materials, our modified approach for preparing TEM samples from powders only requires two additional simple steps. In this article, step-by-step procedures for our methodology are described in detail, and important strategies to ensure success are elucidated. Our methodology has been applied successfully for preparing TEM samples with large thin areas and high quality for many different mechanically milled metallic powders. JF - Microscopy and Microanalysis AU - Wen, Haiming AU - Lin, Yaojun AU - Seidman, David N AU - Schoenung, Julie M AU - van Rooyen, Isabella J AU - Lavernia, Enrique J AD - Department of Chemical Engineering and Materials Science, University of California at Davis, Davis, CA 95616, USA,; haiming.wen@inl.gov] hmwen@ucdavis.edu Y1 - 2015/10// PY - 2015 DA - October 2015 SP - 1184 EP - 1194 PB - Cambridge University Press, The Edinburgh Building, Cambridge CB2 2RU United Kingdom VL - 21 IS - 5 SN - 1431-9276, 1431-9276 KW - Biotechnology and Bioengineering Abstracts KW - Particle size KW - Powder KW - Transmission electron microscopy KW - W 30900:Methods UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1846406774?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Abiotechresearch&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Microscopy+and+Microanalysis&rft.atitle=An+Efficient+and+Cost-Effective+Method+for+Preparing+Transmission+Electron+Microscopy+Samples+from+Powders&rft.au=Wen%2C+Haiming%3BLin%2C+Yaojun%3BSeidman%2C+David+N%3BSchoenung%2C+Julie+M%3Bvan+Rooyen%2C+Isabella+J%3BLavernia%2C+Enrique+J&rft.aulast=Wen&rft.aufirst=Haiming&rft.date=2015-10-01&rft.volume=21&rft.issue=5&rft.spage=1184&rft.isbn=&rft.btitle=&rft.title=Microscopy+and+Microanalysis&rft.issn=14319276&rft_id=info:doi/10.1017%2FS1431927615014695 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-12-01 N1 - Number of references - 49 N1 - Last updated - 2016-12-22 N1 - SubjectsTermNotLitGenreText - Particle size; Powder; Transmission electron microscopy DO - http://dx.doi.org/10.1017/S1431927615014695 ER - TY - JOUR T1 - Modeling an unmitigated thermal quench event in a large field magnet in a DEMO reactor AN - 1786156100; PQ0002502863 AB - The superconducting magnet systems of future fusion reactors, such as a demonstration power plant (DEMO), will produce magnetic field energies in the 10 s of GJ range. The release of this energy during a fault condition could produce arcs that can damage the magnets of these systems. The public safety consequences of such events must be explored for a DEMO reactor because the magnets are located near the DEMO primary radioactive confinement barrier, the reactor's vacuum vessel (VV). Great care will be taken in the design of DEMO's magnet systems to detect and provide a rapid field energy dump to avoid any accidents conditions. During an event when a fault condition proceeds undetected, the potential of producing melting of the magnet exists. If molten material from the magnet impinges on the walls of the VV, these walls could fail, resulting in a pathway for release of radioactive material from the VV. A model is under development at Idaho National Laboratory (INL) called MAGARC to investigate the consequences of this accident in a large toroidal field (TF) coil. Recent improvements to this model are described in this paper, along with predictions for a DEMO relevant event in a toroidal field magnet. JF - Fusion Engineering and Design AU - Merrill, Brad J AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, USA Brad.Merrill@inl.gov Y1 - 2015/10// PY - 2015 DA - October 2015 SP - 2196 EP - 2200 PB - North-Holland, P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 98-99 SN - 0920-3796, 0920-3796 KW - Solid State and Superconductivity Abstracts (SO); Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Fusion safety KW - Unmitigated quench KW - Magnet accident KW - Nuclear power plants KW - Nuclear power generation KW - Walls KW - Mathematical models KW - Reactors KW - Public safety KW - Design engineering KW - Faults UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786156100?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Fusion+Engineering+and+Design&rft.atitle=Modeling+an+unmitigated+thermal+quench+event+in+a+large+field+magnet+in+a+DEMO+reactor&rft.au=Merrill%2C+Brad+J&rft.aulast=Merrill&rft.aufirst=Brad&rft.date=2015-10-01&rft.volume=98-99&rft.issue=&rft.spage=2196&rft.isbn=&rft.btitle=&rft.title=Fusion+Engineering+and+Design&rft.issn=09203796&rft_id=info:doi/10.1016%2Fj.fusengdes.2015.03.007 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 DO - http://dx.doi.org/10.1016/j.fusengdes.2015.03.007 ER - TY - JOUR T1 - TSTA piping and flame arrestor operating experience data AN - 1786155819; PQ0002502845 AB - The Tritium Systems Test Assembly (TSTA) was a facility dedicated to tritium handling technology and experiment research at the Los Alamos National Laboratory. The facility was operated with tritium for its research and development program from 1984 to 2001, running a prototype fusion fuel processing loop with ~100g of tritium as well as small experiments. There have been several operating experience reports written on this facility's operation and maintenance experience. This paper describes reliability analysis of two additional components from TSTA, small diameter copper gas piping that handled tritium in a nitrogen carrier gas, and the flame arrestor used in this piping system. The component failure rates for these components are discussed in this paper. Comparison data from other applications are also presented. JF - Fusion Engineering and Design AU - Cadwallader, Lee C AU - Willms, R Scott AD - Idaho National Laboratory, Idaho Falls, ID, United States Y1 - 2015/10// PY - 2015 DA - October 2015 SP - 2112 EP - 2115 PB - North-Holland, P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 98-99 SN - 0920-3796, 0920-3796 KW - Solid State and Superconductivity Abstracts (SO); Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Tritium piping KW - Flame arrestor KW - Failure rate KW - Piping KW - Arrestors KW - Design engineering KW - Tritium KW - Running KW - Laboratories KW - Failure rates KW - Assembly UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786155819?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Fusion+Engineering+and+Design&rft.atitle=TSTA+piping+and+flame+arrestor+operating+experience+data&rft.au=Cadwallader%2C+Lee+C%3BWillms%2C+R+Scott&rft.aulast=Cadwallader&rft.aufirst=Lee&rft.date=2015-10-01&rft.volume=98-99&rft.issue=&rft.spage=2112&rft.isbn=&rft.btitle=&rft.title=Fusion+Engineering+and+Design&rft.issn=09203796&rft_id=info:doi/10.1016%2Fj.fusengdes.2014.11.013 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 DO - http://dx.doi.org/10.1016/j.fusengdes.2014.11.013 ER - TY - JOUR T1 - Mechanical environmental transport of actinides and (super 137) Cs from an arid radioactive waste disposal site AN - 1769966471; 2016-020818 AB - Aeolian and pluvial processes represent important mechanisms for the movement of actinides and fission products at the Earth's surface. Soil samples taken in the early 1970's near a Department of Energy radioactive waste disposal site (the Subsurface Disposal Area, SDA, located in southeastern Idaho) provide a case study for studying the mechanisms and characteristics of environmental actinide and (super 137) Cs transport in an arid environment. Multi-component mixing models suggest actinide contamination within 2.5 km of the SDA can be described by mixing between 2 distinct SDA end members and regional nuclear weapons fallout. The absence of chemical fractionation between (super 241) Am and (super 239+240) Pu with depth for samples beyond the northeastern corner and lack of (super 241) Am in-growth over time (due to (super 241) Pu decay) suggest mechanical transport and mixing of discrete contaminated particles under arid conditions. Occasional samples northeast of the SDA (the direction of the prevailing winds) contain anomalously high concentrations of Pu with (super 240) Pu/ (super 239) Pu isotopic ratios statistically identical to those in the northeastern corner. Taken together, these data suggest flooding resulted in mechanical transport of contaminated particles into the area between the SDA and a flood containment dike in the northeastern corner, following which subsequent contamination spreading in the northeastern direction resulted from wind transport of discrete particles. Abstract Copyright (2015) Elsevier, B.V. JF - Journal of Environmental Radioactivity AU - Snow, Mathew S AU - Clark, Sue B AU - Morrison, Samuel S AU - Watrous, Matthew G AU - Olson, John E AU - Snyder, Darin C Y1 - 2015/10// PY - 2015 DA - October 2015 SP - 42 EP - 49 PB - Elsevier, Oxford VL - 148 SN - 0265-931X, 0265-931X KW - United States KW - hazardous waste KW - dispersivity KW - terrestrial environment KW - geophysical surveys KW - isotopes KW - radioactivity KW - plutonium KW - thermal ionization mass spectra KW - waste disposal sites KW - mass spectra KW - Idaho Falls Idaho KW - southeastern Idaho KW - radioactivity methods KW - radioactive waste KW - air pollution KW - radioactive isotopes KW - cesium KW - transport KW - movement KW - gamma-ray spectra KW - floods KW - spectra KW - water pollution KW - Idaho KW - Bonneville County Idaho KW - pollutants KW - arid environment KW - drainage KW - Subsurface Disposal Area KW - geophysical methods KW - alkali metals KW - pollution KW - mechanical properties KW - Cs-137 KW - soil pollution KW - metals KW - americium KW - surveys KW - waste disposal KW - actinides KW - winds KW - 22:Environmental geology KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1769966471?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Environmental+Radioactivity&rft.atitle=Mechanical+environmental+transport+of+actinides+and+%28super+137%29+Cs+from+an+arid+radioactive+waste+disposal+site&rft.au=Snow%2C+Mathew+S%3BClark%2C+Sue+B%3BMorrison%2C+Samuel+S%3BWatrous%2C+Matthew+G%3BOlson%2C+John+E%3BSnyder%2C+Darin+C&rft.aulast=Snow&rft.aufirst=Mathew&rft.date=2015-10-01&rft.volume=148&rft.issue=&rft.spage=42&rft.isbn=&rft.btitle=&rft.title=Journal+of+Environmental+Radioactivity&rft.issn=0265931X&rft_id=info:doi/10.1016%2Fj.jenvrad.2015.06.009 L2 - http://www.sciencedirect.com/science/journal/0265931X LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2016-01-01 N1 - Number of references - 22 N1 - Document feature - illus. incl. 4 tables, sketch map N1 - SuppNotes - Includes appendices N1 - Last updated - 2016-03-03 N1 - SubjectsTermNotLitGenreText - actinides; air pollution; alkali metals; americium; arid environment; Bonneville County Idaho; cesium; Cs-137; dispersivity; drainage; floods; gamma-ray spectra; geophysical methods; geophysical surveys; hazardous waste; Idaho; Idaho Falls Idaho; isotopes; mass spectra; mechanical properties; metals; movement; plutonium; pollutants; pollution; radioactive isotopes; radioactive waste; radioactivity; radioactivity methods; soil pollution; southeastern Idaho; spectra; Subsurface Disposal Area; surveys; terrestrial environment; thermal ionization mass spectra; transport; United States; waste disposal; waste disposal sites; water pollution; winds DO - http://dx.doi.org/10.1016/j.jenvrad.2015.06.009 ER - TY - JOUR T1 - First high temperature safety tests of AGR-1 TRISO fuel with the Fuel Accident Condition Simulator (FACS) furnace AN - 1765966225; PQ0002503678 AB - Three TRISO fuel compacts from the AGR-1 irradiation experiment were subjected to safety tests at 1600 and 1800 [degrees]C for approximately 300 h to evaluate the fission product retention characteristics. Silver behavior was dominated by rapid release of an appreciable fraction of the compact inventory (3-34%) at the beginning of the tests, believed to be from inventory residing in the compact matrix and outer pyrocarbon (OPyC) prior to the safety test. Measurable release of silver from intact particles appears to become apparent only after ~60 h at 1800 [degrees]C. The release rate for europium and strontium was nearly constant for 300 h at 1600 [degrees]C (reaching maximum values of approximately 2 x 10 super(-3) and 8 x 10 super(-4) respectively), and at this temperature the release may be mostly limited to inventory in the compact matrix and OPyC prior to the safety test. The release rate for both elements increased after approximately 120 h at 1800 [degrees]C, possibly indicating additional measurable release through the intact particle coatings. Cesium fractional release from particles with intact coatings was <10 super(-6) after 300 h at 1600 [degrees]C or 100 h at 1800 [degrees]C, but release from the rare particles that experienced SiC failure during the test could be significant. However, Kr release was still very low for 300 h 1600 [degrees]C (<2 x 10 super(-6)). At 1800 [degrees]C, krypton release increased noticeably after SiC failure, reflecting transport through the intact outer pyrocarbon layer. Nonetheless, the krypton and cesium release fractions remained less than approximately 10 super(-3) after 277 h at 1800 [degrees]C. JF - Journal of Nuclear Materials AU - Demkowicz, Paul A AU - Reber, Edward L AU - Scates, Dawn M AU - Scott, Les AU - Collin, Blaise P AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188, USA, paul.demkowicz@inl.gov Y1 - 2015/09// PY - 2015 DA - September 2015 SP - 320 EP - 330 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 464 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Cesium KW - Fuels KW - Europium KW - Safety KW - Krypton KW - Particulates KW - Accidents KW - Furnaces KW - Behavior KW - High temperature KW - Radioactive materials KW - Strontium KW - Silver KW - Coatings KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1765966225?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=First+high+temperature+safety+tests+of+AGR-1+TRISO+fuel+with+the+Fuel+Accident+Condition+Simulator+%28FACS%29+furnace&rft.au=Demkowicz%2C+Paul+A%3BReber%2C+Edward+L%3BScates%2C+Dawn+M%3BScott%2C+Les%3BCollin%2C+Blaise+P&rft.aulast=Demkowicz&rft.aufirst=Paul&rft.date=2015-09-01&rft.volume=464&rft.issue=&rft.spage=320&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2015.05.006 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-02-01 N1 - Number of references - 41 N1 - Last updated - 2016-02-29 N1 - SubjectsTermNotLitGenreText - Cesium; Fuels; Safety; Europium; Krypton; Particulates; Accidents; Behavior; Furnaces; High temperature; Radioactive materials; Strontium; Silver; Coatings DO - http://dx.doi.org/10.1016/j.jnucmat.2015.05.006 ER - TY - JOUR T1 - Thermal stability of fission gas bubble superlattice in irradiated U-10Mo fuel AN - 1765966119; PQ0002503636 AB - To investigate the thermal stability of the fission gas bubble superlattice, a key microstructural feature in both irradiated U-7Mo dispersion and U-l0Mo monolithic fuel plates, a focused ion beam-transmission electron microscopy (FIB-TEM) sample of irradiated U-10Mo fuel with a local fission density of 3.5 x 10 super(21) fissions/cm super(3) was used for an in-situ heating TEM experiment The temperature of the heating holder was raised at a ramp rate of approximately 10 [degrees]C/min up to ~700 [degrees]C, kept at that temperature for about 34 min and further increased to 850 [degrees]C with a reduced rate of 5 [degrees]C/min. The result shows a high thermal stability of the fission gas bubble superlattice. The implication of this observation on the fuel microstructural evolution and performance under irradiation is discussed. JF - Journal of Nuclear Materials AU - Gan, J AU - Keiser, D D, Jr AU - Miller, B D AU - Robinson, A B AU - Wachs, D M AU - Meyer, M K AD - Nuclear Fuels and Materials Division, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188, USA, Jian.Gan@inl.gov Y1 - 2015/09// PY - 2015 DA - September 2015 SP - 1 EP - 5 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 464 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Uranium base alloys KW - U-10Mo KW - U-7Mo KW - Fuels KW - Irradiation KW - Radioactive materials KW - Microscopy KW - Temperature KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1765966119?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Thermal+stability+of+fission+gas+bubble+superlattice+in+irradiated+U-10Mo+fuel&rft.au=Gan%2C+J%3BKeiser%2C+D+D%2C+Jr%3BMiller%2C+B+D%3BRobinson%2C+A+B%3BWachs%2C+D+M%3BMeyer%2C+M+K&rft.aulast=Gan&rft.aufirst=J&rft.date=2015-09-01&rft.volume=464&rft.issue=&rft.spage=1&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2015.04.023 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-02-01 N1 - Number of references - 30 N1 - Last updated - 2016-04-29 N1 - SubjectsTermNotLitGenreText - Irradiation; Fuels; Microscopy; Radioactive materials; Temperature DO - http://dx.doi.org/10.1016/j.jnucmat.2015.04.023 ER - TY - JOUR T1 - Characterization of phases formed between U-Pu-Mo fuels and Fe-12Cr cladding AN - 1765965865; PQ0002503640 AB - Exposure to high temperatures and irradiation can lead to interaction between fuel and cladding constituents, inter-diffusion, and formation of brittle or low-melting phases. Therefore, understanding of fuel-cladding interaction (FCCI) is critical for evaluation of fuel performance in a reactor environment. In this contribution, phases formed between U-22Pu-4Mo and U-25Pu-15Mo (in wt%) fuel alloys and Fe-12Cr cladding were characterized using scanning and transmission electron microscopy (SEM/TEM) techniques. Phases formed within FCCI layers in both alloys were identified by implementing selective area diffraction pattern analysis as Cr sub(0.3)Mo sub(0.7) (Im-3m), Fe sub(2)U (Fd-3m), UCrFe (Fd-3m), and Fe sub(2)Pu (Fd-3m). Phases formed at the end of the FCCI layer in the U-22Pu-4Mo alloy included UCrFe (Fd-3m), Fe sub(2)U (Fd-3m), and Cr sub(2)FeO sub(4) (Fd-3m) while in the U-25Pu-15Mo alloy the phases were consistent with Cr sub(0.49)Fe sub(0.51) (P4 sub(2)/mnm), Cr sub(0.8)Fe sub(0.2) (Im-3m), and UCrFe (Fd-3m). JF - Journal of Nuclear Materials AU - Aitkaliyeva, Assel AU - Madden, James W AU - Miller, Brandon D AU - Papesch, Cynthia A AU - Cole, James I AD - Idaho National Laboratory, Idaho Falls, ID 83415, United States Y1 - 2015/09// PY - 2015 DA - September 2015 SP - 28 EP - 35 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 464 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Austenitic stainless steels KW - Ferritic stainless steels KW - Uranium base alloys KW - Fe-12Cr KW - U-22Pu-4Mo KW - U-25Pu-15Mo KW - Nuclear reactors KW - Fuels KW - High temperature KW - Irradiation KW - Radioactive materials KW - Microscopy KW - Alloys KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1765965865?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Characterization+of+phases+formed+between+U-Pu-Mo+fuels+and+Fe-12Cr+cladding&rft.au=Aitkaliyeva%2C+Assel%3BMadden%2C+James+W%3BMiller%2C+Brandon+D%3BPapesch%2C+Cynthia+A%3BCole%2C+James+I&rft.aulast=Aitkaliyeva&rft.aufirst=Assel&rft.date=2015-09-01&rft.volume=464&rft.issue=&rft.spage=28&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2015.04.041 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-02-01 N1 - Number of references - 18 N1 - Last updated - 2016-04-29 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Irradiation; High temperature; Fuels; Microscopy; Radioactive materials; Alloys DO - http://dx.doi.org/10.1016/j.jnucmat.2015.04.041 ER - TY - JOUR T1 - Histamine reduces boron neutron capture therapy-induced mucositis in an oral precancer model. AN - 1702651389; 25926141 AB - OBJECTIVESSearching for more effective and selective therapies for head and neck cancer, we demonstrated the therapeutic effect of boron neutron capture therapy (BNCT) to treat oral cancer and inhibit long-term tumor development from field-cancerized tissue in the hamster cheek pouch model. However, BNCT-induced mucositis in field-cancerized tissue was dose limiting. In a clinical scenario, oral mucositis affects patients' treatment and quality of life. Our aim was to evaluate different radioprotectors, seeking to reduce the incidence of BNCT-induced severe mucositis in field-cancerized tissue.MATERIALS AND METHODSCancerized pouches treated with BNCT mediated by boronophenylalanine at 5 Gy were treated as follows: control: saline solution; Hishigh : histamine 5 mg kg(-1) ; Hislow : histamine 1 mg kg(-1) ; and JNJ7777120: 10 mg kg(-1).RESULTSHislow reduced the incidence of severe mucositis in field-cancerized tissue to 17% vsCONTROL55%; Hishigh : 67%; JNJ7777120: 57%. Hislow was non-toxic and did not compromise the long-term therapeutic effect of BNCT or alter gross boron concentration.CONCLUSIONHistamine reduces BNCT-induced mucositis in experimental oral precancer without jeopardizing therapeutic efficacy. The fact that both histamine and boronophenylalanine are approved for use in humans bridges the gap between experimental work and potential clinical application to reduce BNCT-induced radiotoxicity in patients with head and neck cancer. JF - Oral diseases AU - Monti Hughes, A AU - Pozzi, Ecc AU - Thorp, S I AU - Curotto, P AU - Medina, V A AU - Martinel Lamas, D J AU - Rivera, E S AU - Garabalino, M A AU - Farías, R O AU - Gonzalez, S J AU - Heber, E M AU - Itoiz, M E AU - Aromando, R F AU - Nigg, D W AU - Trivillin, V A AU - Schwint, A E AD - Department of Radiobiology, National Atomic Energy Commission, San Martin, Province Buenos Aires, Argentina. ; Department of Research and Production Reactors, National Atomic Energy Commission, Ezeiza, Province Buenos Aires, Argentina. ; Department of Instrumentation and Control, National Atomic Energy Commission, Ezeiza, Province Buenos Aires, Argentina. ; Radioisotopes Laboratory, School of Pharmacy and Biochemistry, University of Buenos Aires, Buenos Aires, Argentina. ; Department of Technology and Applications of Accelerators, National Atomic Energy Commission, San Martin, Province Buenos Aires, Argentina. ; National Research Council (CONICET), Buenos Aires, Argentina. ; Department of Oral Pathology, Faculty of Dentistry, University of Buenos Aires, Buenos Aires, Argentina. ; Idaho National Laboratory, Idaho Falls, ID, USA. Y1 - 2015/09// PY - 2015 DA - September 2015 SP - 770 EP - 777 VL - 21 IS - 6 KW - 1-((5-chloro-1H-indol-2-yl)carbonyl)-4-methylpiperazine KW - 0 KW - Indoles KW - Piperazines KW - Radiation-Protective Agents KW - Histamine KW - 820484N8I3 KW - Dentistry KW - radioprotector KW - BNCT KW - boron neutron capture therapy KW - mucositis KW - oral cancer KW - hamster cheek pouch precancer model KW - Animals KW - Piperazines -- therapeutic use KW - Indoles -- therapeutic use KW - Disease Models, Animal KW - Cricetinae KW - Radiation-Protective Agents -- therapeutic use KW - Precancerous Conditions -- radiotherapy KW - Mouth Neoplasms -- radiotherapy KW - Boron Neutron Capture Therapy -- adverse effects KW - Histamine -- therapeutic use KW - Stomatitis -- etiology KW - Radiation Injuries, Experimental -- etiology KW - Radiation Injuries, Experimental -- prevention & control KW - Stomatitis -- prevention & control UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1702651389?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Atoxline&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Oral+diseases&rft.atitle=Histamine+reduces+boron+neutron+capture+therapy-induced+mucositis+in+an+oral+precancer+model.&rft.au=Monti+Hughes%2C+A%3BPozzi%2C+Ecc%3BThorp%2C+S+I%3BCurotto%2C+P%3BMedina%2C+V+A%3BMartinel+Lamas%2C+D+J%3BRivera%2C+E+S%3BGarabalino%2C+M+A%3BFar%C3%ADas%2C+R+O%3BGonzalez%2C+S+J%3BHeber%2C+E+M%3BItoiz%2C+M+E%3BAromando%2C+R+F%3BNigg%2C+D+W%3BTrivillin%2C+V+A%3BSchwint%2C+A+E&rft.aulast=Monti+Hughes&rft.aufirst=A&rft.date=2015-09-01&rft.volume=21&rft.issue=6&rft.spage=770&rft.isbn=&rft.btitle=&rft.title=Oral+diseases&rft.issn=1601-0825&rft_id=info:doi/10.1111%2Fodi.12346 LA - English DB - ProQuest Environmental Science Collection N1 - Date completed - 2016-12-13 N1 - Date created - 2015-08-08 N1 - Date revised - 2017-02-17 N1 - Last updated - 2017-02-23 DO - http://dx.doi.org/10.1111/odi.12346 ER - TY - JOUR T1 - Modeling primary and secondary coolant of a nuclear power plant system with a unique framework (MCUF) AN - 1762104461; PQ0002161636 AB - Within the study and design of a nuclear power plant extensive system modeling is necessary to determine how the reactor is going to perform in any given situation, not only in the normal performance of the reactor but also transients including anticipated transients without scram (ATWS) and hypothetical accidents. Primary and other loops in multiple coolant loop systems in nuclear power plants can be modeled in nuclear system codes, such as Reactor Excursion and Leak Analysis Program (RELAP5), COBRA-TRAC, TRACE, and ATHLET, for the interaction and feedback effects between the coolant loops. This article proposes a new coupling between a system code and Laboratory Virtual Instrument Engineering Workbench (LARVIEW) in a unique framework (called as Modeling of Coolant Systems with a Unique Framework -MCUF-) that allows integrating an experimental apparatus or a facility to a whole power plant model. The results of the coupling have been compared with the typical RELAP5 results which significantly depend on "hard coded" data for second coolant loop. JF - Progress in Nuclear Energy AU - Pack, J AU - Fu, Z AU - Aydogan, F AD - Department of Mechanical Engineering, University of Idaho, Center for Advanced Energy Studies (CAES), 995 University Blvd., Idaho Falls, ID 83401, USA PY - 2015 SP - 197 EP - 211 PB - Elsevier B.V., P.O. Box 800 Kidlington Oxford OX5 1DX United Kingdom VL - 83 SN - 0149-1970, 0149-1970 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); CSA / ASCE Civil Engineering Abstracts (CE) KW - LabVIEW KW - RELAP5 KW - Coupling KW - Primary and secondary coolant loops KW - Connecting an experimental apparatus to a KW - computer model of a whole power plant KW - MCUF KW - Nuclear power plants KW - Nuclear power generation KW - Workbenches KW - Joining KW - Nuclear reactors KW - Coolants KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1762104461?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Progress+in+Nuclear+Energy&rft.atitle=Modeling+primary+and+secondary+coolant+of+a+nuclear+power+plant+system+with+a+unique+framework+%28MCUF%29&rft.au=Pack%2C+J%3BFu%2C+Z%3BAydogan%2C+F&rft.aulast=Pack&rft.aufirst=J&rft.date=2015-08-01&rft.volume=83&rft.issue=&rft.spage=197&rft.isbn=&rft.btitle=&rft.title=Progress+in+Nuclear+Energy&rft.issn=01491970&rft_id=info:doi/10.1016%2Fj.pnucene.2015.03.008 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-02-01 N1 - Last updated - 2016-02-03 DO - http://dx.doi.org/10.1016/j.pnucene.2015.03.008 ER - TY - JOUR T1 - High moisture corn stover pelleting in a flat die pellet mill fitted with a 6 mm die: physical properties and specific energy consumption AN - 1718957614; PQ0001761584 AB - The quality and specific energy consumption (SEC) of the biomass pellets produced depend upon pelleting process conditions. The present study includes understanding the effect of feedstock moisture in the range of 28-38% (wet basis [w.b.]) and preheating in the range of 30-110 degree C at two die speeds of 40 and 60 Hz on the physical properties and SEC. A flat die pellet mill fitted with a 6 mm die was used in the present study. The physical properties of pellets such as moisture content, unit, bulk and tapped density, durability, and expansion ratio and SEC of the pelleting process are measured. The results indicate that the pellets produced have durability values in the range of 87-98%, and unit bulk and tapped density in the range of 670-1100, 375-575, and 420-620 kg/m super(3). Increasing the feedstock moisture content from 33% to 38% (w.b) decreased the unit, bulk and tapped density by about 30-40%. Increasing feedstock moisture content increased the expansion ratio and decreased the density values. A higher feedstock moisture content of 38% (w.b.) and higher preheating temperature of 110 degree C resulted in lower density and a higher expansion ratio, which can be attributed to flash off of moisture as the material extrudes out of the die. The SEC was in the range of 75-275 kWh/ton. Higher feedstock moisture content of 38% (w.b.) and a lower die speed of 40 Hz increased the SEC, whereas lower to medium preheating temperature (30-70 degree C), medium feedstock moisture content of 33% (w.b.), and a higher die speed of 60 Hz minimized the SEC to <100 kWh/ton. Corn stover pellets produced in a flat die pellet mill fitted with 6 mm die at feedstock moisture content of 33% (w.b.) and at two different die speeds (40 & 60 Hz) and preheating temperatures (70 & 110 degree C). JF - Energy Science & Engineering AU - Tumuluru, Jaya Shankar AD - Biofuels and Renewable Energy Technology Department, Idaho National Laboratory, 750 University Blvd, Idaho Falls, Idaho, 83415-3570. Y1 - 2015/07// PY - 2015 DA - Jul 2015 SP - 327 EP - 341 PB - Wiley Subscription Services, Inc., 1105 N Market St Wilmington DE 19801 England VL - 3 IS - 4 SN - 2050-0505, 2050-0505 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); CSA / ASCE Civil Engineering Abstracts (CE); Aerospace & High Technology Database (AH) KW - Physical properties KW - Pelleting KW - Moisture content KW - Heating KW - Density KW - Feedstock KW - Preheating KW - Pellets UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1718957614?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Energy+Science+%26+Engineering&rft.atitle=High+moisture+corn+stover+pelleting+in+a+flat+die+pellet+mill+fitted+with+a+6+mm+die%3A+physical+properties+and+specific+energy+consumption&rft.au=Tumuluru%2C+Jaya+Shankar&rft.aulast=Tumuluru&rft.aufirst=Jaya&rft.date=2015-07-01&rft.volume=3&rft.issue=4&rft.spage=327&rft.isbn=&rft.btitle=&rft.title=Energy+Science+%26+Engineering&rft.issn=20500505&rft_id=info:doi/10.1002%2Fese3.74 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-10-01 N1 - Last updated - 2015-12-07 DO - http://dx.doi.org/10.1002/ese3.74 ER - TY - CPAPER T1 - Multivariate approaches to rapid characterization of biomass as a bioenergy source T2 - 2015 Northwest Regional Meeting of the American Chemical Society (NORM 2015) AN - 1697993748; 6353099 JF - 2015 Northwest Regional Meeting of the American Chemical Society (NORM 2015) AU - Emerson, Rachel AU - Gresham, Garold AU - Westover, Tyler Y1 - 2015/06/21/ PY - 2015 DA - 2015 Jun 21 KW - Multivariate analysis KW - Biomass KW - Biofuels UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1697993748?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2015+Northwest+Regional+Meeting+of+the+American+Chemical+Society+%28NORM+2015%29&rft.atitle=Multivariate+approaches+to+rapid+characterization+of+biomass+as+a+bioenergy+source&rft.au=Emerson%2C+Rachel%3BGresham%2C+Garold%3BWestover%2C+Tyler&rft.aulast=Emerson&rft.aufirst=Rachel&rft.date=2015-06-21&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2015+Northwest+Regional+Meeting+of+the+American+Chemical+Society+%28NORM+2015%29&rft.issn=&rft_id=info:doi/ L2 - https://ep70.eventpilot.us/web/page.php?page=Sessions&project=ACSNORM15&id=2015-06-21&title=Browse%20Program%20by%20Day LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-06-30 N1 - Last updated - 2015-07-23 ER - TY - CPAPER T1 - Microbially mediated recovery of rare earth elements from recyclable materials T2 - 2015 Northwest Regional Meeting of the American Chemical Society (NORM 2015) AN - 1697993260; 6353142 JF - 2015 Northwest Regional Meeting of the American Chemical Society (NORM 2015) AU - Reed, David AU - Fujita, Yoshiko AU - Jiao, Yongqin AU - Park, Dan AU - Daubaras, Dayna AU - Thompson, Vicki AU - Bruhn, Debra AU - Reiss, Jennalee Y1 - 2015/06/21/ PY - 2015 DA - 2015 Jun 21 KW - Rare earths KW - Rare earth elements UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1697993260?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2015+Northwest+Regional+Meeting+of+the+American+Chemical+Society+%28NORM+2015%29&rft.atitle=Microbially+mediated+recovery+of+rare+earth+elements+from+recyclable+materials&rft.au=Reed%2C+David%3BFujita%2C+Yoshiko%3BJiao%2C+Yongqin%3BPark%2C+Dan%3BDaubaras%2C+Dayna%3BThompson%2C+Vicki%3BBruhn%2C+Debra%3BReiss%2C+Jennalee&rft.aulast=Reed&rft.aufirst=David&rft.date=2015-06-21&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2015+Northwest+Regional+Meeting+of+the+American+Chemical+Society+%28NORM+2015%29&rft.issn=&rft_id=info:doi/ L2 - https://ep70.eventpilot.us/web/page.php?page=Sessions&project=ACSNORM15&id=2015-06-21&title=Browse%20Program%20by%20Day LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-06-30 N1 - Last updated - 2015-07-23 ER - TY - CPAPER T1 - Does changing experimental conditions influence Am(VI) reduction kinetics? 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6353199 JF - 2015 Northwest Regional Meeting of the American Chemical Society (NORM 2015) AU - Lister, Tedd AU - Dufek, Eric AU - Petkovic, Lucia AU - Lilga, Michael AU - Padmaperuma, Asanga Y1 - 2015/06/21/ PY - 2015 DA - 2015 Jun 21 KW - Chemicals KW - Fuels KW - Electrochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1697990027?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2015+Northwest+Regional+Meeting+of+the+American+Chemical+Society+%28NORM+2015%29&rft.atitle=Electrochemical+upgrading+for+production+of+chemicals+and+fuels&rft.au=Lister%2C+Tedd%3BDufek%2C+Eric%3BPetkovic%2C+Lucia%3BLilga%2C+Michael%3BPadmaperuma%2C+Asanga&rft.aulast=Lister&rft.aufirst=Tedd&rft.date=2015-06-21&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2015+Northwest+Regional+Meeting+of+the+American+Chemical+Society+%28NORM+2015%29&rft.issn=&rft_id=info:doi/ L2 - https://ep70.eventpilot.us/web/page.php?page=Sessions&project=ACSNORM15&id=2015-06-21&title=Browse%20Program%20by%20Day LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-06-30 N1 - Last updated - 2015-07-23 ER - TY - CPAPER T1 - Electrochemical process development for the recovery of value metals in end of life mobile electronic devices T2 - 2015 Northwest Regional Meeting of the American Chemical Society (NORM 2015) AN - 1697989938; 6353168 JF - 2015 Northwest Regional Meeting of the American Chemical Society (NORM 2015) AU - Diaz Aldana, Luis AU - Lister, Tedd AU - Parkman, Jacob AU - Clark, Gemma Y1 - 2015/06/21/ PY - 2015 DA - 2015 Jun 21 KW - Metals KW - Electronic equipment KW - Electrochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1697989938?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2015+Northwest+Regional+Meeting+of+the+American+Chemical+Society+%28NORM+2015%29&rft.atitle=Electrochemical+process+development+for+the+recovery+of+value+metals+in+end+of+life+mobile+electronic+devices&rft.au=Diaz+Aldana%2C+Luis%3BLister%2C+Tedd%3BParkman%2C+Jacob%3BClark%2C+Gemma&rft.aulast=Diaz+Aldana&rft.aufirst=Luis&rft.date=2015-06-21&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2015+Northwest+Regional+Meeting+of+the+American+Chemical+Society+%28NORM+2015%29&rft.issn=&rft_id=info:doi/ L2 - https://ep70.eventpilot.us/web/page.php?page=Sessions&project=ACSNORM15&id=2015-06-21&title=Browse%20Program%20by%20Day LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-06-30 N1 - Last updated - 2015-07-23 ER - TY - CPAPER T1 - The Water Security Test Bed - A Pilot Scale Test Bed For Water Infrastructure Decontamination T2 - 2015 American Water Works Association Annual Conference & Exposition (ACE 2015) AN - 1658698352; 6335345 JF - 2015 American Water Works Association Annual Conference & Exposition (ACE 2015) AU - Reese, Stephen Y1 - 2015/06/07/ PY - 2015 DA - 2015 Jun 07 KW - Infrastructure KW - Security KW - Decontamination UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1658698352?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2015+American+Water+Works+Association+Annual+Conference+%26+Exposition+%28ACE+2015%29&rft.atitle=The+Water+Security+Test+Bed+-+A+Pilot+Scale+Test+Bed+For+Water+Infrastructure+Decontamination&rft.au=Reese%2C+Stephen&rft.aulast=Reese&rft.aufirst=Stephen&rft.date=2015-06-07&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2015+American+Water+Works+Association+Annual+Conference+%26+Exposition+%28ACE+2015%29&rft.issn=&rft_id=info:doi/ L2 - http://www.awwa.org/conferences-education/conferences/annual-conference/ace15-professional-program.aspx LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-02-28 N1 - Last updated - 2015-02-27 ER - TY - JOUR T1 - Workplace slip, trip and fall injuries and obesity AN - 1694971293; PQ0001610971 AB - The objective of this study was to examine the relationship between slip, trip and fall injuries and obesity in a population of workers at the Idaho National Laboratory (INL) in Idaho Falls, Idaho. INL is an applied engineering facility dedicated to supporting the US Department of Energy's mission. An analysis was performed on injuries reported to the INL Medical Clinic to determine whether obesity was related to an increase in slip, trip and fall injuries. Records were analysed that spanned a 6-year period (2005-2010), and included 8581 employees (mean age, 47 plus or minus 11 years and body mass index [BMI], 29 plus or minus 5 kg/m super(2); 34% obesity rate). Of the 189 people who reported slip, trip and fall injuries (mean age, 48 plus or minus 11 years), 51% were obese (P < 0.001 compared with uninjured employees), and their mean BMI was 31 plus or minus 6 kg/m super(2) (P < 0.001). Obesity in this population was associated with a greater rate of slip, trip and fall injuries. Practitioner Summary: Slip, trip and fall injuries are a major contributor of workplace-related injuries and a great financial burden to employers. This study examines the impact of obesity in slip, trip and fall injuries. The investigation found that obesity was associated with a greater rate of slip, trip and fall injuries. JF - Ergonomics AU - Koepp, Gabriel A AU - Snedden, Bradley J AU - Levine, James A AD - Idaho National Laboratory, Department of Occupational Medicine, Idaho Falls, ID, USA PY - 2015 SP - 674 EP - 679 PB - Taylor & Francis Group Ltd., 2 Park Square Oxford OX14 4RN United Kingdom VL - 58 IS - 5 SN - 0014-0139, 0014-0139 KW - Physical Education Index; Health & Safety Science Abstracts KW - ergonomics KW - falls KW - injury KW - obesity KW - workplace KW - Obesity KW - Age KW - Injuries KW - Body mass KW - Facilities KW - Employees KW - USA, Idaho KW - Employers KW - Energy KW - Analysis KW - Ergonomics KW - H 1000:Occupational Safety and Health KW - PE 030:Exercise, Health & Physical Fitness UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1694971293?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aphysicaleducation&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Ergonomics&rft.atitle=Workplace+slip%2C+trip+and+fall+injuries+and+obesity&rft.au=Koepp%2C+Gabriel+A%3BSnedden%2C+Bradley+J%3BLevine%2C+James+A&rft.aulast=Koepp&rft.aufirst=Gabriel&rft.date=2015-05-04&rft.volume=58&rft.issue=5&rft.spage=674&rft.isbn=&rft.btitle=&rft.title=Ergonomics&rft.issn=00140139&rft_id=info:doi/10.1080%2F00140139.2014.985260 LA - English DB - Physical Education Index; ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2016-01-06 N1 - SubjectsTermNotLitGenreText - Obesity; Employers; Injuries; Facilities; Analysis; Body mass; Employees; Ergonomics; Age; Energy; USA, Idaho DO - http://dx.doi.org/10.1080/00140139.2014.985260 ER - TY - JOUR T1 - A point implicit time integration technique for slow transient flow problems AN - 1753541293; PQ0002043893 AB - We introduce a point implicit time integration technique for slow transient flow problems. The method treats the solution variables of interest (that can be located at cell centers, cell edges, or cell nodes) implicitly and the rest of the information related to same or other variables are handled explicitly. The method does not require implicit iteration; instead it time advances the solutions in a similar spirit to explicit methods, except it involves a few additional function(s) evaluation steps. Moreover, the method is unconditionally stable, as a fully implicit method would be. This new approach exhibits the simplicity of implementation of explicit methods and the stability of implicit methods. It is specifically designed for slow transient flow problems of long duration wherein one would like to perform time integrations with very large time steps. Because the method can be time inaccurate for fast transient problems, particularly with larger time steps, an appropriate solution strategy for a problem that evolves from a fast to a slow transient would be to integrate the fast transient with an explicit or semi-implicit technique and then switch to this point implicit method as soon as the time variation slows sufficiently. We have solved several test problems that result from scalar or systems of flow equations. Our findings indicate the new method can integrate slow transient problems very efficiently; and its implementation is very robust. JF - Nuclear Engineering and Design AU - Kadioglu, Samet Y AU - Berry, Ray A AU - Martineau, Richard C AD - Department of Mathematical Engineering, Yildiz Technical University, 34210 Davutpasa-Esenler, Istanbul, Turkey PY - 2015 SP - 130 EP - 138 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 286 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Implicit methods KW - Design engineering KW - Switches KW - Scalars KW - Strategy KW - Nuclear reactor components KW - Time integration KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1753541293?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=A+point+implicit+time+integration+technique+for+slow+transient+flow+problems&rft.au=Kadioglu%2C+Samet+Y%3BBerry%2C+Ray+A%3BMartineau%2C+Richard+C&rft.aulast=Kadioglu&rft.aufirst=Samet&rft.date=2015-05-01&rft.volume=286&rft.issue=&rft.spage=130&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2015.02.002 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-01-01 N1 - Number of references - 23 N1 - Last updated - 2016-01-06 DO - http://dx.doi.org/10.1016/j.nucengdes.2015.02.002 ER - TY - JOUR T1 - Associations of Pd, U and Ag in the SiC layer of neutron-irradiated TRISO fuel AN - 1687665733; PQ0001548381 AB - Knowledge of the associations and composition of fission products in the neutron irradiated SiC layer of high-temperature gas reactor TRISO fuel is important to the understanding of various aspects of fuel performance that presently are not well understood. Recently, advanced characterization techniques have been used to examine fuel particles from the Idaho National Laboratory's AGR-1 experiment. Nano-sized Ag and Pd precipitates were previously identified in grain boundaries and triple points in the SiC layer of irradiated TRISO nuclear fuel. Continuation of this initial research is reported in this paper and consists of the characterization of a relatively large number of nano-sized precipitates in three areas of the SiC layer of a single irradiated TRISO nuclear fuel particle using standardless EDS analysis on focused ion beam-prepared transmission electron microscopy samples. Composition and distribution analyses of these precipitates, which were located on grain boundaries, triple junctions and intragranular precipitates, revealed low levels, generally <10 atomic %, of palladium, silver and/or uranium with palladium being the most common element found. Palladium by itself, or associated with either silver or uranium, was found throughout the SiC layer. A small number of precipitates on grain boundaries and triple junctions were found to contain only silver or silver in association with palladium while uranium was always associated with palladium but never found by itself or in association with silver. Intergranular precipitates containing uranium were found to have migrated ~23 mu m along a radial direction through the 35 mu m thick SiC coating during the AGR-1 experiment while silver-containing intergranular precipitates were found at depths up to ~24 mu m in the SiC layer. Also, Pd-rich, nano-precipitates (~10 nm in diameter), without evidence for the presence of either Ag or U, were revealed in intragranular regions throughout the SiC layer. Because not all grain boundaries and triple junctions contained precipitates with fission products and/or uranium, along with the differences in migration behavior between Pd, Ag and U, it was concluded that crystallographic grain boundary and triple junction parameters likely influence migration behavior. JF - Journal of Nuclear Materials AU - Lillo, T M AU - van Rooyen, I J AD - Materials Science & Engineering Department, Idaho National Laboratory, Idaho Falls, ID 83415-2211, USA, thomas.lillo@inl.gov Y1 - 2015/05// PY - 2015 DA - May 2015 SP - 97 EP - 106 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 460 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Fuels KW - Particulates KW - Migration KW - Fission products KW - USA, Idaho KW - Nuclear reactors KW - Uranium KW - Radioactive materials KW - Microscopy KW - Nuclear fuels KW - Grains KW - Silver KW - Palladium KW - Coatings KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1687665733?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Associations+of+Pd%2C+U+and+Ag+in+the+SiC+layer+of+neutron-irradiated+TRISO+fuel&rft.au=Lillo%2C+T+M%3Bvan+Rooyen%2C+I+J&rft.aulast=Lillo&rft.aufirst=T&rft.date=2015-05-01&rft.volume=460&rft.issue=&rft.spage=97&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2015.02.010 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-06-01 N1 - Number of references - 26 N1 - Last updated - 2015-11-16 N1 - SubjectsTermNotLitGenreText - Fuels; Particulates; Migration; Fission products; Nuclear reactors; Uranium; Nuclear fuels; Microscopy; Radioactive materials; Grains; Silver; Palladium; Coatings; USA, Idaho DO - http://dx.doi.org/10.1016/j.jnucmat.2015.02.010 ER - TY - JOUR T1 - Effects of heat treatment on U-Mo fuel foils with a zirconium diffusion barrier AN - 1687665335; PQ0001548387 AB - A monolith fuel design based on U-Mo alloy has been selected as the fuel type for conversion of the United States' high performance research reactors (HPRRs) from highly enriched uranium (HEU) to low-enriched uranium (LEU). In this fuel design, a thin layer of zirconium is used to eliminate the direct interaction between the U-Mo fuel meat and the aluminum-alloy cladding during irradiation. The co-rolling process used to bond the Zr barrier layer to the U-Mo foil during fabrication alters the microstructure of both the U-10Mo fuel meat and the U-Mo/Zr interface. This work studied the effects of post-rolling annealing treatment on the microstructure of the co-rolled U-Mo fuel meat and the U-Mo/Zr interaction layer. Microscopic characterization shows that the grain size of U-Mo fuel meat increases with the annealing temperature, as expected. The grain sizes were ~9, ~13, and ~20 mu n for annealing temperature of 650, 750, and 850 [degrees]C, respectively. No abnormal grain growth was observed. The U-Mo/Zr interaction-layer thickness increased with the annealing temperature with an Arrhenius constant for growth of 184 kJ/mole, consistent with a previous diffusion-couple study. The interaction layer thickness was 3.2 + or -0.5 mu n, 11.1 + or -2.1 mu n, 27.1 + or -0.9 mu n for annealing temperature of 650, 750, to 850 [degrees]C, respectively. The homogeneity of Mo improves with post rolling annealing temperature and with U-Mo coupon homogenization. The phases in the Zr/U-Mo interaction layer produced by co-rolling, however, differ from those reported in the previous diffusion couple studies. JF - Journal of Nuclear Materials AU - Jue, Jan-Fong AU - Trowbridge, Tammy L AU - Breckenridge, Cynthia R AU - Moore, Glenn A AU - Meyer, Mitchell K AU - Keiser, Dennis D, Jr AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188, USA; Idaho National Laboratory, Nuclear Fuels and Materials Division, P.O. Box 1625, Idaho Falls, ID 83415, USA, Jan-Fong.jue@inl.gov Y1 - 2015/05// PY - 2015 DA - May 2015 SP - 153 EP - 159 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 460 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Uranium base alloys KW - U-Mo KW - Particle size KW - Fuels KW - Temperature KW - Zirconium KW - Meat KW - USA KW - Nuclear reactors KW - Irradiation KW - Uranium KW - Radioactive materials KW - Nuclear fuels KW - Alloys KW - Diffusion KW - Grains KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1687665335?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Effects+of+heat+treatment+on+U-Mo+fuel+foils+with+a+zirconium+diffusion+barrier&rft.au=Jue%2C+Jan-Fong%3BTrowbridge%2C+Tammy+L%3BBreckenridge%2C+Cynthia+R%3BMoore%2C+Glenn+A%3BMeyer%2C+Mitchell+K%3BKeiser%2C+Dennis+D%2C+Jr&rft.aulast=Jue&rft.aufirst=Jan-Fong&rft.date=2015-05-01&rft.volume=460&rft.issue=&rft.spage=153&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2015.02.017 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-06-01 N1 - Number of references - 25 N1 - Last updated - 2015-11-16 N1 - SubjectsTermNotLitGenreText - Particle size; Fuels; Temperature; Zirconium; Meat; Nuclear reactors; Uranium; Irradiation; Nuclear fuels; Radioactive materials; Alloys; Diffusion; Grains; USA DO - http://dx.doi.org/10.1016/j.jnucmat.2015.02.017 ER - TY - JOUR T1 - Comparison of preparation techniques for nuclear materials for transmission electron microscopy (TEM) AN - 1732810267; PQ0001495049 AB - Preparation of highly radioactive and irradiated nuclear fuels and materials for transmission electron microscopy (TEM) is accompanied with a set of unique challenges. The paper evaluates three specimen preparation techniques for preparation of irradiated materials and determines which technique yields to the most reliable characterization of radiation damage microstructure. Various specimen preparation artifacts associated with each technique are considered and ways of minimizing these artifacts are addressed. JF - Journal of Nuclear Materials AU - Aitkaliyeva, Assel AU - Madden, James W AU - Miller, Brandon D AU - Cole, James I AU - Gan, Jian AD - Idaho National Laboratory, P.O. Box 1625, M.S. 6188, Idaho Falls, ID 83415-6188, United States, assel.aitkaliyeva@inl.gov PY - 2015 SP - 241 EP - 246 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 459 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Artifacts KW - Radiation KW - Radioactive materials KW - Microscopy KW - Nuclear fuels KW - Specimen preparation KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1732810267?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Comparison+of+preparation+techniques+for+nuclear+materials+for+transmission+electron+microscopy+%28TEM%29&rft.au=Aitkaliyeva%2C+Assel%3BMadden%2C+James+W%3BMiller%2C+Brandon+D%3BCole%2C+James+I%3BGan%2C+Jian&rft.aulast=Aitkaliyeva&rft.aufirst=Assel&rft.date=2015-04-01&rft.volume=459&rft.issue=&rft.spage=241&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2015.01.042 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-11-01 N1 - Number of references - 16 N1 - Last updated - 2015-12-09 N1 - SubjectsTermNotLitGenreText - Artifacts; Radiation; Nuclear fuels; Microscopy; Radioactive materials; Specimen preparation DO - http://dx.doi.org/10.1016/j.jnucmat.2015.01.042 ER - TY - JOUR T1 - Derivation of new mass, momentum, and energy conservation equations for two-phase flows AN - 1692402766; PQ0001453596 AB - System codes are used to analyze nuclear reactor systems during steady state and transient operations. These codes are able to predict pressure drop, void fraction distributions and temperature distributions for various coolants, heated flow geometries, and heat configurations. They also include models for various two-phase flow regimes, but extreme flow conditions that involve significant phase change can tax the current code capabilities. Current system codes have mass, momentum, and energy conservation equations for two fields (liquid and vapor), resulting in a model with six conservation equations. Recent developments in limited applications of a few of these codes have added a separate droplet field from the continuous liquid. This is part of a trend toward the inclusion of more fields (and requisite conservation equations) in system codes. The representation of two phase flow phenomena is improved by increasing the number of fields. Conservation equations based on six fields (liquid, vapor, small bubble, large bubble, small droplet and large droplet) are derived in this work. JF - Progress in Nuclear Energy AU - Roth, Glenn A AU - Aydogan, Fatih AD - University of Idaho, Center for Advanced Energy Studies, 995 University Blvd., Idaho Falls, ID 83401, USA roth1581@vandals.uidaho.edu PY - 2015 SP - 90 EP - 101 PB - Elsevier B.V., P.O. Box 800 Kidlington Oxford OX5 1DX United Kingdom VL - 80 SN - 0149-1970, 0149-1970 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); CSA / ASCE Civil Engineering Abstracts (CE) KW - Two-phase flow KW - Multi-field KW - Conservation equation KW - Conservation equations KW - Nuclear reactors KW - Mathematical models KW - Droplets KW - Energy conservation KW - Liquids KW - Bubbles KW - Mathematical analysis UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692402766?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Progress+in+Nuclear+Energy&rft.atitle=Derivation+of+new+mass%2C+momentum%2C+and+energy+conservation+equations+for+two-phase+flows&rft.au=Roth%2C+Glenn+A%3BAydogan%2C+Fatih&rft.aulast=Roth&rft.aufirst=Glenn&rft.date=2015-04-01&rft.volume=80&rft.issue=&rft.spage=90&rft.isbn=&rft.btitle=&rft.title=Progress+in+Nuclear+Energy&rft.issn=01491970&rft_id=info:doi/10.1016%2Fj.pnucene.2014.12.007 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2016-02-03 DO - http://dx.doi.org/10.1016/j.pnucene.2014.12.007 ER - TY - JOUR T1 - GIS-based geospatial infrastructure of water resource assessment for supporting oil shale development in Piceance Basin of northwestern Colorado AN - 1680752864; 2015-041674 AB - Oil shale deposits of the Green River Formation (GRF) in Northwestern Colorado, Southwestern Wyoming, and Northeastern Utah may become one of the first oil shale deposits to be developed in the U.S. because of their richness, accessibility, and extensive prior characterization. Oil shale is an organic-rich fine-grained sedimentary rock that contains significant amounts of kerogen from which liquid hydrocarbons can be produced. Water is needed to retort or extract oil shale at an approximate rate of three volumes of water for every volume of oil produced. Concerns have been raised over the demand and availability of water to produce oil shale, particularly in semiarid regions where water consumption must be limited and optimized to meet demands from other sectors. The economic benefit of oil shale development in this region may have tradeoffs within the local and regional environment. Due to these potential environmental impacts of oil shale development, water usage issues need to be further studied. A basin-wide baseline for oil shale and water resource data is the foundation of the study. This paper focuses on the design and construction of a centralized geospatial infrastructure for managing a large amount of oil shale and water resource related baseline data, and for setting up the frameworks for analytical and numerical models including but not limited to three-dimensional (3D) geologic, energy resource development systems, and surface water models. Such a centralized geospatial infrastructure made it possible to directly generate model inputs from the same database and to indirectly couple the different models through inputs/outputs. Thus ensures consistency of analyses conducted by researchers from different institutions, and help decision makers to balance water budget based on the spatial distribution of the oil shale and water resources, and the spatial variations of geologic, topographic, and hydrogeological characterization of the basin. This endeavor encountered many technical challenging and has not been done in the past for any oil shale basin. The database built during this study remains valuable for any other future studies involving oil shale and water resource management in the Piceance Basin. The methodology applied in the development of the GIS based geospatial infrastructure can be readily adapted for other professionals to develop database structure for other similar basins. Abstract Copyright (2015) Elsevier, B.V. JF - Computers & Geosciences AU - Zhou, Wei AU - Minnick, Matthew D AU - Mattson, Earl D AU - Geza, Mengistu AU - Murray, Kyle E Y1 - 2015/04// PY - 2015 DA - April 2015 SP - 44 EP - 53 PB - Elsevier, Amsterdam VL - 77 SN - 0098-3004, 0098-3004 KW - United States KW - Piceance Basin KW - sedimentary basins KW - data acquisition KW - rivers and streams KW - data processing KW - water management KW - petroleum KW - hydrogeology KW - digital terrain models KW - ground water KW - Cenozoic KW - oil shale KW - sedimentary rocks KW - geographic information systems KW - drainage basins KW - data bases KW - basins KW - numerical models KW - three-dimensional models KW - Eocene KW - surface water KW - decision-making KW - Paleogene KW - basin analysis KW - aquifers KW - Tertiary KW - mathematical methods KW - Green River Formation KW - information systems KW - Colorado KW - water resources KW - northwestern Colorado KW - 29A:Economic geology, geology of energy sources KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1680752864?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Computers+%26+Geosciences&rft.atitle=GIS-based+geospatial+infrastructure+of+water+resource+assessment+for+supporting+oil+shale+development+in+Piceance+Basin+of+northwestern+Colorado&rft.au=Zhou%2C+Wei%3BMinnick%2C+Matthew+D%3BMattson%2C+Earl+D%3BGeza%2C+Mengistu%3BMurray%2C+Kyle+E&rft.aulast=Zhou&rft.aufirst=Wei&rft.date=2015-04-01&rft.volume=77&rft.issue=&rft.spage=44&rft.isbn=&rft.btitle=&rft.title=Computers+%26+Geosciences&rft.issn=00983004&rft_id=info:doi/10.1016%2Fj.cageo.2015.01.007 L2 - http://www.sciencedirect.com/science?_ob=JournalURL&_cdi=5840&_auth=y&_acct=C000050221&_version=1&_urlVersion=0&_userid=10&md5=e5198452fad934c6346f38b57511c8e0 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2015-01-01 N1 - Number of references - 11 N1 - Document feature - illus. incl. 3 tables, sketch maps N1 - Last updated - 2016-10-25 N1 - CODEN - GGEOD5 N1 - SubjectsTermNotLitGenreText - aquifers; basin analysis; basins; Cenozoic; Colorado; data acquisition; data bases; data processing; decision-making; digital terrain models; drainage basins; Eocene; geographic information systems; Green River Formation; ground water; hydrogeology; information systems; mathematical methods; northwestern Colorado; numerical models; oil shale; Paleogene; petroleum; Piceance Basin; rivers and streams; sedimentary basins; sedimentary rocks; surface water; Tertiary; three-dimensional models; United States; water management; water resources DO - http://dx.doi.org/10.1016/j.cageo.2015.01.007 ER - TY - JOUR T1 - OBSERVATIONS ON USING INSIDE AIR CONCENTRATIONS AS A PREDICTOR OF OUTSIDE AIR CONCENTRATIONS AN - 1680453812; PQ0001486123 AB - Excavations of radiological material were performed within confined structures with known operational parameters, such as a filtered exhaust system with known filtration efficiency. Given the known efficiency, the assumption could be made that the air concentrations of radioactivity measured outside the structure would be proportional to the air concentrations measured inside the structure. To investigate this assumption, the inside concentration data was compared with the outside concentration data. The correlation of the data suggested that the inside concentrations were not a good predictor of the outside concentrations. This poor correlation was deemed to be a result of operational unknowns within the structures. JF - Health Physics AU - Hawkley, Gavin AU - Whicker, Jeffrey AU - Harris, Jason AD - Department of Nuclear Engineering and Health Physics, Idaho State University, Pocatello ID, 83209; Idaho National Laboratory, Idaho Falls ID, 83415, hawkgavi@isu.edu Y1 - 2015/04// PY - 2015 DA - Apr 2015 SP - 465 EP - 467 PB - Williams & Wilkins, 351 W. Camden St. Baltimore MD 21201 United States VL - 108 IS - 4 SN - 0017-9078, 0017-9078 KW - Pollution Abstracts KW - air sampling KW - atmospheric testing KW - dose assessment KW - environmental transport KW - Filtration KW - Radioactivity KW - P 0000:AIR POLLUTION UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1680453812?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Apollution&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Health+Physics&rft.atitle=OBSERVATIONS+ON+USING+INSIDE+AIR+CONCENTRATIONS+AS+A+PREDICTOR+OF+OUTSIDE+AIR+CONCENTRATIONS&rft.au=Hawkley%2C+Gavin%3BWhicker%2C+Jeffrey%3BHarris%2C+Jason&rft.aulast=Hawkley&rft.aufirst=Gavin&rft.date=2015-04-01&rft.volume=108&rft.issue=4&rft.spage=465&rft.isbn=&rft.btitle=&rft.title=Health+Physics&rft.issn=00179078&rft_id=info:doi/10.1097%2FHP.0000000000000223 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-05-01 N1 - Last updated - 2015-11-16 N1 - SubjectsTermNotLitGenreText - Filtration; Radioactivity DO - http://dx.doi.org/10.1097/HP.0000000000000223 ER - TY - JOUR T1 - Microstructural characterization of a thin film ZrN diffusion barrier in an As-fabricated U-7Mo/Al matrix dispersion fuel plate AN - 1687665014; PQ0001574938 AB - The United States High Performance Research Reactor Fuel Development program is developing low enriched uranium fuels for application in research and test reactors. The ZrN serves as a diffusion barrier to eliminate a deleterious reaction that can occur between U-7Mo and Al when a dispersion fuel is irradiated under aggressive reactor conditions. To investigate the final microstructure of a physically-vapor-deposited ZrN coating in a dispersion fuel plate after it was fabricated using a rolling process, characterization samples were taken from a fuel plate that was fabricated at 500[degrees]C using ZrN-coated U-7Mo particles, Al matrix and AA6061 cladding. A relatively high level of oxygen was observed in the ZrN coating, extending from the Al matrix in the ZrN coating in decreasing concentration. The above microstructural characteristics are discussed in terms of what may be most optimal for a diffusion barrier in a dispersion fuel plate application. JF - Journal of Nuclear Materials AU - Keiser, Dennis D, Jr AU - Perez, Emmanuel AU - Wiencek, Tom AU - Leenaers, Ann AU - Van den Berghe, Sven AD - Nuclear Fuels and Materials Division, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188, USA, Dennis.Keiser@inl.gov Y1 - 2015/03// PY - 2015 DA - Mar 2015 SP - 406 EP - 418 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 458 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Aluminum base alloys KW - Uranium base alloys KW - 6061 KW - U-7Mo KW - Oxygen KW - USA KW - Nuclear reactors KW - Fuels KW - Uranium KW - Nuclear fuels KW - Radioactive materials KW - Diffusion KW - Particulates KW - Coatings KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1687665014?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Microstructural+characterization+of+a+thin+film+ZrN+diffusion+barrier+in+an+As-fabricated+U-7Mo%2FAl+matrix+dispersion+fuel+plate&rft.au=Keiser%2C+Dennis+D%2C+Jr%3BPerez%2C+Emmanuel%3BWiencek%2C+Tom%3BLeenaers%2C+Ann%3BVan+den+Berghe%2C+Sven&rft.aulast=Keiser&rft.aufirst=Dennis&rft.date=2015-03-01&rft.volume=458&rft.issue=&rft.spage=406&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.12.036 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-06-01 N1 - Number of references - 50 N1 - Last updated - 2015-11-16 N1 - SubjectsTermNotLitGenreText - Oxygen; Nuclear reactors; Uranium; Fuels; Radioactive materials; Nuclear fuels; Diffusion; Particulates; Coatings; USA DO - http://dx.doi.org/10.1016/j.jnucmat.2014.12.036 ER - TY - JOUR T1 - Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U-7 wt%Mo dispersion fuels AN - 1687664800; PQ0001574902 AB - Transmission electron microscopy characterization of irradiated U-7 wt%Mo dispersion fuel were performed on various U-Mo fuel samples to understand the effect of irradiation parameters (fission density, fission rate, and temperature) on the self-organized fission-gas-bubble superlattice that forms in the irradiated U-Mo fuel. The bubble superlattice was seen to form a face centered cubic structure coherent with the host U-7 wt%Mo body-centered cubic structure. At a fission density between 3.0 and 4.5 x 10 super(21) fiss/cm super(3), the superlattice bubbles appear to have reached a saturation size with additional fission gas associated with increasing bumup predominately accumulating along grain boundaries. At a fission density of ~4.5 x 10 super(21) fiss/cm super(3), the U-7 wt%Mo microstructure starts to undergo grain subdivision and can no longer support the ordered bubble superlattice. The sub-divided fuel grains are less than 500 nm in diameter with what appears to be micron-size fission-gas bubbles present on the grain boundaries. Solid fission products typically decorate the inside surface of the micron-sized fission-gas bubbles. Residual superlattice bubbles are seen in areas where fuel grains remain micron sized. Potential mechanisms of the formation and collapse of the bubble superlattice are discussed. JF - Journal of Nuclear Materials AU - Miller, B D AU - Gan, J AU - Keiser, D D, Jr AU - Robinson, A B AU - Jue, J F AU - Madden, J W AU - Medvedev, P G AD - Idaho National Laboratory, 2525 Fremont Ave., Idaho Falls, ID 83401, United States, Dennis.Keiser@inl.gov Y1 - 2015/03// PY - 2015 DA - Mar 2015 SP - 115 EP - 121 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 458 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Fission products KW - Fuels KW - Irradiation KW - Nuclear fuels KW - Microscopy KW - Radioactive materials KW - Temperature KW - Grains KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1687664800?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Transmission+electron+microscopy+characterization+of+the+fission+gas+bubble+superlattice+in+irradiated+U-7+wt%25Mo+dispersion+fuels&rft.au=Miller%2C+B+D%3BGan%2C+J%3BKeiser%2C+D+D%2C+Jr%3BRobinson%2C+A+B%3BJue%2C+J+F%3BMadden%2C+J+W%3BMedvedev%2C+P+G&rft.aulast=Miller&rft.aufirst=B&rft.date=2015-03-01&rft.volume=458&rft.issue=&rft.spage=115&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.12.012 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-06-01 N1 - Number of references - 43 N1 - Last updated - 2015-11-16 N1 - SubjectsTermNotLitGenreText - Fission products; Irradiation; Fuels; Radioactive materials; Microscopy; Nuclear fuels; Temperature; Grains DO - http://dx.doi.org/10.1016/j.jnucmat.2014.12.012 ER - TY - JOUR T1 - Impact of process conditions on the density and durability of wheat, oat, canola, and barley straw briquettes AN - 1677948090; PQ0001252270 AB - The present study is to understand the impact of process conditions on the quality attributes of wheat oat, barley, and canola straw briquettes. Analysis of variance indicated that briquette moisture content and initial density immediately after compaction and final density after 2 weeks of storage are strong functions of feedstock moisture content and compression pressure, whereas durability rating is influenced by die temperature and feedstock moisture content. Briquettes produced at a low feedstock moisture content of 9 % (w.b.) yielded maximum densities >700 kg/m super(3) for wheat, oat, canola, and barley straws. Lower feedstock moisture content of 110 degree C and compression pressure >10 MPa minimized the briquette moisture content and maximized densities and durability rating based on surface plots observations. Optimal process conditions indicated that a low feedstock moisture content of about 9 % (w.b.), high die temperature of 120-130 degree C, medium-to-large hammer mill screen sizes of about 24 to 31.75 mm, and low to high compression pressures of 7.5 to 12.5 MPa minimized briquette moisture content to 700 kg/m super(3). Durability rating >90 % is achievable at higher die temperatures of >123 degree C, lower to medium feedstock moisture contents of 9 to 12 % (w.b.), low to high compression pressures of 7.5 to 12.5 MPa, and large hammer mill screen size of 31.75 mm, except for canola where a lower compression pressure of 7.5 to 8.5 MPa and a smaller hammer mill screen size of 19 mm for oat maximized the durability rating values. JF - BioEnergy Research AU - Tumuluru, J S AU - Tabil, L G AU - Song, Y AU - Iroba, K L AU - Meda, V AD - Biofuels and Renewable Energy Technologies Department, Energy Systems and Technologies Division, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415-2025, USA jayashankar.tumuluru@inl.gov Y1 - 2015/03// PY - 2015 DA - Mar 2015 SP - 388 EP - 401 PB - Springer Science+Business Media, Van Godewijckstraat 30 Dordrecht 3311 GX Netherlands VL - 8 IS - 1 SN - 1939-1234, 1939-1234 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA) KW - Moisture content KW - Durability KW - Briquettes KW - Hammer mills KW - Density KW - Ratings KW - Wheat KW - Feedstock KW - Compressing UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1677948090?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=BioEnergy+Research&rft.atitle=Impact+of+process+conditions+on+the+density+and+durability+of+wheat%2C+oat%2C+canola%2C+and+barley+straw+briquettes&rft.au=Tumuluru%2C+J+S%3BTabil%2C+L+G%3BSong%2C+Y%3BIroba%2C+K+L%3BMeda%2C+V&rft.aulast=Tumuluru&rft.aufirst=J&rft.date=2015-03-01&rft.volume=8&rft.issue=1&rft.spage=388&rft.isbn=&rft.btitle=&rft.title=BioEnergy+Research&rft.issn=19391234&rft_id=info:doi/10.1007%2Fs12155-014-9527-4 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-05-01 N1 - Number of references - 46 N1 - Last updated - 2015-12-07 DO - http://dx.doi.org/10.1007/s12155-014-9527-4 ER - TY - JOUR T1 - Monitoring CO (sub 2) sequestration into deep saline aquifer and associated salt intrusion using coupled multiphase flow modeling and time-lapse electrical resistivity tomography AN - 1722155166; 2015-097583 AB - Successful geological storage and sequestration of carbon dioxide (CO (sub 2) ) require efficient monitoring of the migration of CO (sub 2) plume during and after large-scale injection in order to verify the containment of the injected CO (sub 2) within the target formation and to evaluate potential leakage risk. Field studies have shown that surface and cross-borehole electrical resistivity tomography (ERT) can be a useful tool in imaging and characterizing solute transport in heterogeneous subsurface. In this synthetic study, we have coupled a 3-D multiphase flow model with a parallel 3-D time-lapse ERT inversion code to explore the feasibility of using time-lapse ERT for simultaneously monitoring the migration of CO (sub 2) plume in deep saline formation and potential brine intrusion into shallow fresh water aquifer. Direct comparisons of the inverted CO (sub 2) plumes resulting from ERT with multiphase flow simulation results indicate the ERT could be used to delineate the migration of CO (sub 2) plume. Detailed comparisons on the locations, sizes and shapes of CO (sub 2) plume and intruded brine plumes suggest that ERT inversion tends to underestimate the area review of the CO (sub 2) plume, but overestimate the thickness and total volume of the CO (sub 2) plume. The total volume of intruded brine plumes is overestimated as well. However, all discrepancies remain within reasonable ranges. Our study suggests that time-lapse ERT is a useful monitoring tool in characterizing the movement of injected CO (sub 2) into deep saline aquifer and detecting potential brine intrusion under large-scale field injection conditions. Abstract Copyright (2010), John Wiley & Sons, Ltd. JF - Greenhouse Gases AU - Lu, Chuan AU - Zhang, Chi AU - Hunag, Hai AU - Johnson, Timothy C Y1 - 2015/02// PY - 2015 DA - February 2015 SP - 34 EP - 49 PB - John Wiley & Sons, Sussex VL - 5 IS - 1 KW - solute transport KW - water quality KW - electrical resistivity tomography KW - deep aquifers KW - salt-water intrusion KW - contaminant plumes KW - Archie's law KW - coupling KW - preferential flow KW - ground water KW - carbon dioxide KW - transport KW - time-lapse methods KW - saline composition KW - stratigraphy KW - toxic materials KW - monitoring KW - carbon sequestration KW - three-dimensional models KW - injection KW - pollution KW - migration of elements KW - porosity KW - aquifers KW - boreholes KW - brines KW - cap rocks KW - permeability KW - 21:Hydrogeology KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1722155166?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Greenhouse+Gases&rft.atitle=Monitoring+CO+%28sub+2%29+sequestration+into+deep+saline+aquifer+and+associated+salt+intrusion+using+coupled+multiphase+flow+modeling+and+time-lapse+electrical+resistivity+tomography&rft.au=Lu%2C+Chuan%3BZhang%2C+Chi%3BHunag%2C+Hai%3BJohnson%2C+Timothy+C&rft.aulast=Lu&rft.aufirst=Chuan&rft.date=2015-02-01&rft.volume=5&rft.issue=1&rft.spage=34&rft.isbn=&rft.btitle=&rft.title=Greenhouse+Gases&rft.issn=2152-3878&rft_id=info:doi/10.1002%2Fghg.1437 L2 - http://onlinelibrary.wiley.com/journal/10.1002/%28ISSN%292152-3878 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data from John Wiley & Sons, Chichester, United Kingdom N1 - Date revised - 2015-01-01 N1 - Number of references - 32 N1 - Document feature - illus. incl. 1 table N1 - Last updated - 2015-10-15 N1 - SubjectsTermNotLitGenreText - aquifers; Archie's law; boreholes; brines; cap rocks; carbon dioxide; carbon sequestration; contaminant plumes; coupling; deep aquifers; electrical resistivity tomography; ground water; injection; migration of elements; monitoring; permeability; pollution; porosity; preferential flow; saline composition; salt-water intrusion; solute transport; stratigraphy; three-dimensional models; time-lapse methods; toxic materials; transport; water quality DO - http://dx.doi.org/10.1002/ghg.1437 ER - TY - JOUR T1 - Zirconium determination by cooling curve analysis during the pyroprocessing of used nuclear fuel AN - 1673400192; PQ0001285573 AB - An alternative method to sampling and chemical analyses has been developed to monitor the concentration of zirconium in real-time during the casting of uranium products from the pyroprocessing of used nuclear fuel. The method utilizes the solidilication characteristics of the uranium products to determine zirconium levels based on standard cooling curve analyses and established binary phase diagram data. Numerous uranium products have been analyzed for their zirconium content and compared against measured zirconium data. From this data, the following equation was derived for the zirconium content of uranium products: Zr = 0.14M + 131.56 - 12.63(348.65 - 0.16LT) super(1/2) where M is the mass (kg) of the ingot and LT is the liquidus temperature (K) found by cooling curve analyses. Based on this equation, a reasonable fit of calculated to measured zirconium content was established considering the errors in the system. JF - Journal of Nuclear Materials AU - Westphal, B R AU - Price, J C AU - Bateman, K J AU - Marsden, K C AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, United States, brian.westphal@inl.gov Y1 - 2015/02// PY - 2015 DA - Feb 2015 SP - 241 EP - 245 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 457 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Uranium KW - Nuclear fuels KW - Radioactive materials KW - Temperature KW - Zirconium KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1673400192?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Zirconium+determination+by+cooling+curve+analysis+during+the+pyroprocessing+of+used+nuclear+fuel&rft.au=Westphal%2C+B+R%3BPrice%2C+J+C%3BBateman%2C+K+J%3BMarsden%2C+K+C&rft.aulast=Westphal&rft.aufirst=B&rft.date=2015-02-01&rft.volume=457&rft.issue=&rft.spage=241&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.11.091 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-04-01 N1 - Number of references - 16 N1 - Last updated - 2015-05-27 N1 - SubjectsTermNotLitGenreText - Uranium; Radioactive materials; Nuclear fuels; Temperature; Zirconium DO - http://dx.doi.org/10.1016/j.jnucmat.2014.11.091 ER - TY - JOUR T1 - Overview of U.S. DOE Research and Development of Nuclear-Renewable Hybrid Energy Systems AN - 1798739035; PQ0002503012 AB - The U.S. Department of Energy Office of Nuclear Energy (DOE-NE) is supporting research and development on the direct coupling of nuclear and renewable energy technologies under the DOE Advanced Reactor Technologies (ART) program. If deployed, these conceptual systems could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options, to meet both grid demand and thermal energy needs in the industrial sector. One such concept - referred to as a "hybrid" energy system (HES) - is tighter coupling of nuclear and renewable energy sources in a manner that better optimizes energy use for the combined electricity, industrial manufacturing, and transportation sectors. The integrated energy system would be capable of dynamically apportioning thermal and electrical energy to first meet the grid demand (with appropriate power conversion systems), then utilizing excess thermal and, in some cases, electrical energy to drive a process that results in an additional product. JF - Transactions of the American Nuclear Society AU - Bragg-Sitton, Shannon M AU - Boardman, Richard AD - Nuclear Fuel Performance and Design, shannon.bragg-sitton@inl.gov Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 113 EP - 116 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Sustainability Science Abstracts KW - Transportation KW - Nuclear reactors KW - Energy KW - Renewable energy KW - Hybrids KW - Nuclear energy KW - Energy consumption KW - Research programs KW - Technology KW - M3 1010:Issues in Sustainable Development UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1798739035?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Assamodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Overview+of+U.S.+DOE+Research+and+Development+of+Nuclear-Renewable+Hybrid+Energy+Systems&rft.au=Bragg-Sitton%2C+Shannon+M%3BBoardman%2C+Richard&rft.aulast=Bragg-Sitton&rft.aufirst=Shannon&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=113&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-06-01 N1 - Last updated - 2016-07-07 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Transportation; Hybrids; Renewable energy; Energy; Nuclear energy; Energy consumption; Research programs; Technology ER - TY - JOUR T1 - Using gravity and magnetics to delineate structural controls on geothermal fluids, northern Cache Valley, Idaho AN - 1797535043; 2016-050663 AB - The Northern Cache Valley (NCV) of southeastern Idaho is a north-south trending Basin and Range graben that is receiving renewed interest for its geothermal potential. Several geophysical and hydrological studies of the NCV occurred during the 1970's motivated by the presence of thermal wells and springs in the area, culminating with geothermal exploration wells drilled by Sunedco Energy Development. The test borehole temperatures were deemed too low for power production using technology available at that time (test hole temperatures <120 degrees C). In January of 2014, a water well drilled to 79 meters, encountered Na-Cl-HCO (sub 3) water with a measured bottom hole temperature of 104 degrees C. Traditional magnesium corrected Na-K-Ca geothermometry of water from that well estimated the temperature of the thermal reservoir to be 204 degrees C. Inspired by this revived interest, new studies utilizing updated geochemical and geophysical techniques are currently under way. Present understanding of the NCV geothermal system suggests that fluid flow is associated with a fault(s) adjacent to Little Mountain - a small secondary horst complex within the primary Cache Valley graben. The existing data from the area is relatively sparse and is not suitable for pinpointing the location of faults thought to carry thermal water from depth to the near surface. To accurately characterize the plumbing of the geothermal system, lines of closely spaced potential field (gravity and magnetic) measurements were performed across the suspected location of the Little Mountain bounding faults. Analysis of these data in conjunction with existing hydrogeologic and geochemistry data will aid in determining fault locations carrying thermal fluid to shallow depths. Future work proposed to better characterize the geothermal system includes thermal imaging, utilizing an unmanned aerial vehicle (UAV), to detect elevated ground surface temperatures thought to exist based on preferential snow melt in the area. JF - Abstracts with Programs - Geological Society of America AU - Worthing, Wade AU - Wood, Thomas R AU - Glen, Jonathan AU - McLing, Travis L AU - Dobson, Patrick F AU - Ritzinger, Brent AU - Cannon, Cody AU - Neupane, Ghanashyam AU - Thorne, Michael S AU - Anonymous Y1 - 2015 PY - 2015 DA - 2015 SP - 825 PB - Geological Society of America (GSA), Boulder, CO VL - 47 IS - 7 SN - 0016-7592, 0016-7592 KW - 16:Structural geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1797535043?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Using+gravity+and+magnetics+to+delineate+structural+controls+on+geothermal+fluids%2C+northern+Cache+Valley%2C+Idaho&rft.au=Worthing%2C+Wade%3BWood%2C+Thomas+R%3BGlen%2C+Jonathan%3BMcLing%2C+Travis+L%3BDobson%2C+Patrick+F%3BRitzinger%2C+Brent%3BCannon%2C+Cody%3BNeupane%2C+Ghanashyam%3BThorne%2C+Michael+S%3BAnonymous&rft.aulast=Worthing&rft.aufirst=Wade&rft.date=2015-01-01&rft.volume=47&rft.issue=7&rft.spage=825&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2015 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2016-01-01 N1 - PubXState - CO N1 - Last updated - 2016-06-17 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Inhibition of nitrifying bacteria by simulated phosphor recycling wastewaters containing Eu and Y AN - 1793208061; 2016-048613 JF - V.M. Goldschmidt Conference - Program and Abstracts AU - Fujita, Yoshiko AU - Barnes, Joni AU - Eslamimanesh, Ali AU - Lencka, Malgorzata M AU - Anderko, Andrzej AU - Riman, Richard E AU - Navrotsky, Alexandra AU - Anonymous Y1 - 2015 PY - 2015 DA - 2015 SP - 966 PB - Goldschmidt Conference, [varies] VL - 25 SN - 1042-7287, 1042-7287 KW - experimental studies KW - tributyl phosphate KW - recycling KW - waste water KW - biochemistry KW - Nitrobacter winogradskyi KW - phosphates KW - simulation KW - toxicity KW - nitrification KW - Nitrosomonas europaea KW - metals KW - water treatment KW - Nitrosomonas KW - bacteria KW - Nitrobacter KW - rare earths KW - europium KW - nitrate ion KW - geochemistry KW - biology KW - yttrium KW - ammonia compound KW - 02B:Hydrochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1793208061?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=V.M.+Goldschmidt+Conference+-+Program+and+Abstracts&rft.atitle=Inhibition+of+nitrifying+bacteria+by+simulated+phosphor+recycling+wastewaters+containing+Eu+and+Y&rft.au=Fujita%2C+Yoshiko%3BBarnes%2C+Joni%3BEslamimanesh%2C+Ali%3BLencka%2C+Malgorzata+M%3BAnderko%2C+Andrzej%3BRiman%2C+Richard+E%3BNavrotsky%2C+Alexandra%3BAnonymous&rft.aulast=Fujita&rft.aufirst=Yoshiko&rft.date=2015-01-01&rft.volume=25&rft.issue=&rft.spage=966&rft.isbn=&rft.btitle=&rft.title=V.M.+Goldschmidt+Conference+-+Program+and+Abstracts&rft.issn=10427287&rft_id=info:doi/ L2 - http://goldschmidt.info/2015/uploads/abstracts/finalPDFs/966.pdf LA - English DB - GeoRef N1 - Conference title - Goldschmidt conference 2015 N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. N1 - Date revised - 2016-01-01 N1 - Last updated - 2016-06-02 N1 - SubjectsTermNotLitGenreText - ammonia compound; bacteria; biochemistry; biology; europium; experimental studies; geochemistry; metals; nitrate ion; nitrification; Nitrobacter; Nitrobacter winogradskyi; Nitrosomonas; Nitrosomonas europaea; phosphates; rare earths; recycling; simulation; toxicity; tributyl phosphate; waste water; water treatment; yttrium ER - TY - JOUR T1 - TREAT Fuel Assembly Characterization for Modern Neutronics Validation Methods AN - 1786163414; PQ0002503080 AB - In December 2010, the U.S. Department of Energy (DOE) released a Mission Need Statement for the resumption of transient fuel testing capabilities to support development and testing of advanced nuclear fuel concepts [1]. Data that could be obtained from a transient testing program would be used to support advanced reactor designs and validate computational predictions of fuel and core behavior. Such validation will be an important factor for U.S. Nuclear Regulatory Commission (NRC) review and approval of next generation power reactor design and safety evaluations [2]. In support of this mission, the Transient Reactor Experiment and Test Facility (TREAT) is being reactivated by DOE-NE, following an extended outage, to support transient fuel performance research and safety testing. JF - Transactions of the American Nuclear Society AU - Bess, John D AU - DeHart, Mark D AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 373 EP - 376 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Regulatory agencies KW - Missions KW - Nuclear safety KW - Fuels KW - Nuclear fuels KW - Assembly KW - Nuclear engineering KW - Government agencies UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786163414?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=TREAT+Fuel+Assembly+Characterization+for+Modern+Neutronics+Validation+Methods&rft.au=Bess%2C+John+D%3BDeHart%2C+Mark+D&rft.aulast=Bess&rft.aufirst=John&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=373&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Thermal Analysis of TREAT Experimental Devices AN - 1786163006; PQ0002503078 AB - As resumption of transient testing [1] in the United States at the Transient Reactor Test (TREAT) facility draws nearer, the designs and analyses of the static and flowing testing devices are moving forward. The engineering analyses of these devices will be key to successful testing. The types and approaches to the thermal and hydraulic analyses performed on these devices remains an area of continued exploration and work as the designs of the static and water loop devices evolve. The purpose of this work is to present the results of preliminary thermal analyses of two primary devices: the Static Environment Rodlet Transient Test Apparatus (SERTTA) and TREAT Water Environment Recirculating Loop (TWERL) [2]; and discuss the directions of their related analyses. JF - Transactions of the American Nuclear Society AU - Jensen, Colby AU - Davis, Cliff AU - Woolstenhulme, Nicolas AD - Idaho National Laboratory: 2525 Fremont Ave., Idaho Falls, ID 83415 colby.jensen@inl.gov Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 372 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Design engineering KW - Devices KW - Fluid dynamics KW - Exploration KW - Fluid flow KW - Evolution KW - Thermal analysis KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786163006?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Thermal+Analysis+of+TREAT+Experimental+Devices&rft.au=Jensen%2C+Colby%3BDavis%2C+Cliff%3BWoolstenhulme%2C+Nicolas&rft.aulast=Jensen&rft.aufirst=Colby&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=372&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - ATF-3: An Overview of the Accident Tolerant Fuels Transient Testing Campaign in the TREAT Reactor AN - 1786162970; PQ0002503074 AB - Since 2012, the United States Department of Energy (DOE) has initiated and led an Accident Tolerant Fuels (ATF) research, development and demonstration program in collaboration with several industrial, national laboratory, and academic partners under the Fuel Cycle Research & Development (FCRD) Advanced Fuels Campaign (AFC). The ATF program supports research into the concept development, fabrication, irradiation performance evaluation and accident environment testing of a number of candidate fuels for the replacement of the existing fuels used in the current light water power reactor (LWR) fleet and future power reactors [1]. The candidate fuel concepts under investigation by the ATF program include several advanced cladding concepts used in conjunction with both traditional ceramic (UO sub(2)) fuel pellets and advanced composite fuel pellets such as UN-U sub(3)Si sub(2). Similarly, some fuel concepts that are under investigation are examining the use of traditional cladding materials such as Zircaloy in conjunction with advanced composite fuel pellet designs that may provide enhanced safety performance under accident conditions such as their exposure to high temperatures and steam such as those experienced under Reactivity Initiated Accidents (RIA) and Loss of Coolant Accidents (LOCA). Overall, these fuel concepts aim to improve their reaction kinetics with steam in order to reduce oxidation of claddings and hydrogen production, minimize Fuel to Cladding Mechanical Interactions (FCMI) and Fuel to Cladding Chemical Interactions (FCCI), and improve fission product retention under these credible accident conditions [2]. JF - Transactions of the American Nuclear Society AU - O'Brien, R C AU - Wachs, D M AU - Beasley, A A AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 - USA Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 355 EP - 357 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Ceramic Abstracts/World Ceramics Abstracts (WC); Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Accidents KW - Accident conditions KW - Cladding KW - Fuels KW - Power reactors KW - Steam electric power generation KW - Pellets KW - Government agencies UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786162970?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=ATF-3%3A+An+Overview+of+the+Accident+Tolerant+Fuels+Transient+Testing+Campaign+in+the+TREAT+Reactor&rft.au=O%27Brien%2C+R+C%3BWachs%2C+D+M%3BBeasley%2C+A+A&rft.aulast=O%27Brien&rft.aufirst=R&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=355&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - New Reactor Physics Benchmark Data in the March 2015 Edition of the IRPhEP Handbook AN - 1786162782; PQ0002503150 AB - The International Reactor Physics Experiment Evaluation Project (IRPhEP) was established to preserve integral reactor physics experimental data, including separate or special effects data for nuclear energy and technology applications. Numerous experiments that have been performed worldwide, represent a large investment of infrastructure, expertise, and cost, and are valuable resources of data for present and future research. These valuable assets provide the basis for recording, development, and validation of methods. If the experimental data are lost, the high cost to repeat many of these measurements may be prohibitive. JF - Transactions of the American Nuclear Society AU - Bess, John D AU - Gulliford, Jim AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3855 Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 689 EP - 692 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Handbooks KW - Preserves KW - Benchmarking KW - Investment KW - Reactor physics KW - Special effects KW - Recording KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786162782?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=New+Reactor+Physics+Benchmark+Data+in+the+March+2015+Edition+of+the+IRPhEP+Handbook&rft.au=Bess%2C+John+D%3BGulliford%2C+Jim&rft.aulast=Bess&rft.aufirst=John&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=689&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Grain Boundary Character and Fission Product Precipitation in SiC AN - 1786162310; PQ0002503083 AB - One of the main functions of the various layers in tri-structural isotropic (TRISO) nuclear fuel particles, especially the SiC layer, is to contain fission products generated by fission of uranium in the fuel kernel. Generally, this design is effective in preventing significant release of most fission products. However, irradiation experiments in the U.S. and Europe, over the past 40 years have documented the release of silver in spite of no apparent failure of the SiC layer of TRISO fuel particles [1,2]. A considerable amount of research has attempted to understand the mechanism of fission product migration through intact SiC layers (for reviews, see [3,4]). Although none have been definitively shown to be responsible for fission product migration in TRISO fuel under expected operating conditions, the most viable migration mechanisms rely on migration of fission products along grain boundaries. JF - Transactions of the American Nuclear Society AU - Lillo, Thomas M AU - van Rooyen, Isabella J AU - Wu, Yaqiao AD - Materials Science & Engineering Department, Idaho National Laboratory, Idaho Falls, ID 83415-6188, USA Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 391 EP - 394 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Fission products KW - Grain boundaries KW - Uranium KW - Fuels KW - Nuclear fuels KW - Silicon carbide KW - Precipitation KW - Migration UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786162310?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Grain+Boundary+Character+and+Fission+Product+Precipitation+in+SiC&rft.au=Lillo%2C+Thomas+M%3Bvan+Rooyen%2C+Isabella+J%3BWu%2C+Yaqiao&rft.aulast=Lillo&rft.aufirst=Thomas&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=391&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Nuclear-Renewable Hybrid Energy System for Reverse Osmosis Desalination Process AN - 1786161433; PQ0002503014 AB - The leading cause of global climate change is generally accepted to be growing emissions of greenhouse gas (GHG) as a result of increased use of fossil fuels [1]. Among various sources of GHG, the global electricity supply sector generates the largest share of GHG emissions (37.5% of total CO sub(2) emissions) [2]. Since the current electricity production heavily relies on fossil fuels, it is envisioned that bolstering generation technologies based on non-emitting energy sources, i.e., nuclear and/or renewables could reduce future GHG emissions. JF - Transactions of the American Nuclear Society AU - Kim, Jong Suk AU - Garcia, Humberto E AD - Idaho National Laboratory, 750 University Boulevard, Idaho Falls, ID 83415-3570, USA jongsuk.kim@inl.gov Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 121 EP - 124 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Air pollution KW - Fossil fuels KW - Transaction processing KW - Greenhouse effect KW - Electricity KW - Greenhouse gases KW - Carbon dioxide KW - Hybrid systems UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786161433?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Nuclear-Renewable+Hybrid+Energy+System+for+Reverse+Osmosis+Desalination+Process&rft.au=Kim%2C+Jong+Suk%3BGarcia%2C+Humberto+E&rft.aulast=Kim&rft.aufirst=Jong&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=121&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-06-30 ER - TY - JOUR T1 - Modeling the Vitrification of Hanford Tank Waste AN - 1786161402; PQ0002503193 AB - A CFD model to study the heat transfer and flow within a waste glass melter is under development and initial results have been obtained. The model replicates the geometry of a one-third scale HLW melter used for testing at the VSL. The model provides a platform to incorporate additional physics and study the effects of changing various parameters, such as glass composition, bubbler configuration, etc. Future work includes evaluating data from experiments on bubbling in glasses and other high viscosity liquids and incorporating a rigorous sub-model for bubble behavior. Improvements and additional physics based upon laboratory data are continually being added to the cold cap model [11]. Updates to the cold cap model will be incorporated to the CFD model as they become available. Once all of the pertinent physics has been added to the model, validation of the computational predictions will be performed. JF - Transactions of the American Nuclear Society AU - Guillen, Donna Post AU - Beers, Clyde J AD - Idaho National Laboratory, Idaho Falls, ID 83415 Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 868 EP - 870 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Bubbling KW - Mathematical models KW - Wastes KW - Tanks KW - Glass KW - Liquids KW - Platforms KW - Composition effects UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786161402?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Modeling+the+Vitrification+of+Hanford+Tank+Waste&rft.au=Guillen%2C+Donna+Post%3BBeers%2C+Clyde+J&rft.aulast=Guillen&rft.aufirst=Donna&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=868&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Newton-Krylov Methods in Applications of Two-Phase Flow Problems with Phase Appearance/Disappearance AN - 1786161344; PQ0002503220 AB - In the nuclear engineering, two-phase flow is an important phenomenon closely related to the normal and accident conditions of nuclear reactor operations. Accurate modeling and simulation of two-phase flow are critical to the safety analyses of nuclear reactors. Several nuclear reactor system analysis codes have been developed to solve the simplified one-dimensional two-phase flow equations to represent the complex reactor systems. These codes, such as RELAP5 [1-2] and TRAC [3], have gained great successes in supporting reactor safety analyses, as well as design and licensing of new reactors. JF - Transactions of the American Nuclear Society AU - Zou, Ling AU - Zhao, Haihua AU - Zhang, Hongbin AD - Idaho National Laboratory, 2525 N Freemont Ave., Idaho Falls, ID 83415 Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 974 EP - 977 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Design engineering KW - Nuclear safety KW - Licensing KW - Nuclear reactor components KW - Reactor safety KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786161344?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Newton-Krylov+Methods+in+Applications+of+Two-Phase+Flow+Problems+with+Phase+Appearance%2FDisappearance&rft.au=Zou%2C+Ling%3BZhao%2C+Haihua%3BZhang%2C+Hongbin&rft.aulast=Zou&rft.aufirst=Ling&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=974&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Numerical Verification of RELAP-7 Model For A Single Phase Natural Circulation Loop AN - 1786156313; PQ0002503216 AB - Numerical verification is an essential part of modern verification and validation process for reactor safety system code development. Strict numerical verification works for a single phase natural circulation loop simulation with the RELAP-7 code have been performed. Second order convergence rates for both time and space are confirmed with selected figure of merits. For a fully implicit code like RELAP-7, although the time step and grid size are not limited by stability requirement, the numerical errors may limit their sizes. Numerical verification can tell users the proper sizes of time step and grid for different types of problems. JF - Transactions of the American Nuclear Society AU - Zhao, Haihua AU - Zou, Ling AU - Zhang, Hongbin AU - Martineau, Richard AD - Idaho National Laboratory: P.O. Box 1560, Idaho Falls, ID, 83415-3870, USA Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 961 EP - 964 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Mathematical models KW - Computer simulation KW - Convergence KW - Figure of merit KW - Circulation KW - Stability KW - Errors KW - Reactor safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786156313?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Numerical+Verification+of+RELAP-7+Model+For+A+Single+Phase+Natural+Circulation+Loop&rft.au=Zhao%2C+Haihua%3BZou%2C+Ling%3BZhang%2C+Hongbin%3BMartineau%2C+Richard&rft.aulast=Zhao&rft.aufirst=Haihua&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=961&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - The TREAT Fast-Neutron Hodoscope and Plans for Restoring it to Operation AN - 1786156276; PQ0002503079 AB - Refurbishment of the TREAT hodoscope is one small but important part of the total program to resume a U.S. capability to perform transient nuclear fuel testing. A motivation for this need is to support current research and development activities underway that are seeking to create new accident-tolerant nuclear fuels. A second motivation is to support the collection of benchmark and validation data to support the development of new meso-scale simulation codes that are needed to design, understand, and qualify new fuel concepts. The first steps of the hodoscope refurbishment program are limited in scope to reduce risk and ensure the operational capability will be ready for when it is needed. Beyond these near term requirements, there may be opportunists to develop wholly-new methods for monitoring the performance of nuclear fuel during transient conditions. JF - Transactions of the American Nuclear Society AU - Chichester, D L AU - Watson, S M AU - Johnson, J T AU - Wachs, D M AD - Idaho National Laboratory, 2525 North Fremont Avenue, Idaho Falls, Idaho 83415, USA Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 377 EP - 380 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Hodoscopes KW - Collection KW - Research and development KW - Nuclear fuels KW - Simulation KW - Benchmarking KW - Monitoring KW - Refurbishment UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786156276?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=The+TREAT+Fast-Neutron+Hodoscope+and+Plans+for+Restoring+it+to+Operation&rft.au=Chichester%2C+D+L%3BWatson%2C+S+M%3BJohnson%2C+J+T%3BWachs%2C+D+M&rft.aulast=Chichester&rft.aufirst=D&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=377&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Development of Multi-Physics Methods to Support Restart of the Transient Test Reactor AN - 1786156266; PQ0002503075 AB - The U.S. Department of Energy is preparing to restart the Transient Reactor Test Facility (TREAT) at the Idaho National Laboratory (INL). TREAT is an air-cooled, thermal-spectrum test facility designed to evaluate reactor fuels and structural materials under simulated nuclear excursions and transient power/cooling mismatch situations in a nuclear reactor [1]. Operating from February 1959 until April 1994, the TREAT facility was specifically built to conduct transient reactor tests where the test material is subjected to neutron pulses that can simulate conditions ranging from mild upsets to severe reactor accidents. The reactor was constructed to test fast reactor fuels, but has also been used for light water reactor fuel testing as well as other exotic special purpose fuels. [2, 3] TREAT has not operated since 1994 but has been maintained in a standby mode. JF - Transactions of the American Nuclear Society AU - Gleicher, Frederick N AU - DeHart, Mark D AU - Ortensi, Javier AU - Wang, Yaqi AU - Alberti, Anthony L AU - Palmer, Todd S AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 358 EP - 362 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Fuels KW - Nuclear fuels KW - Simulation KW - Nuclear reactor components KW - Test facilities KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786156266?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Development+of+Multi-Physics+Methods+to+Support+Restart+of+the+Transient+Test+Reactor&rft.au=Gleicher%2C+Frederick+N%3BDeHart%2C+Mark+D%3BOrtensi%2C+Javier%3BWang%2C+Yaqi%3BAlberti%2C+Anthony+L%3BPalmer%2C+Todd+S&rft.aulast=Gleicher&rft.aufirst=Frederick&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=358&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - TREAT Experiment Vehicle Design and Future Plans AN - 1786156151; PQ0002503077 AB - Development of advanced nuclear fuels requires testing of fuel specimens under various power-cooling mismatch conditions. The Transient Reactor Test Facility (TREAT) at Idaho National Laboratory will b e used to pro vide transient nuclear heating of fuel specimens. Experiment vehicles placed within TREAT will be used to provide the appropriate environment and cooling conditions (or lack thereof) for fuel specimens. Recent efforts to de sign TREAT experiment vehicles have focused on p roviding proper experiment conditions for p roposed Accident Tolerant Fuels (ATF). This summary addresses the engineering aspects of ATF TREAT experiment vehicles with supporting strategy and plans for safety an alysis. Further detail on ATF transient testing program plans can be found elsewhere [1]. JF - Transactions of the American Nuclear Society AU - Woolstenhulme, N E AU - Baker, C C AU - Bess, J D AU - Davis, C B AU - Housley, G K AU - Jensen, C B AU - O'Brien, R C AU - Snow, S D AD - Idaho National Laboratory P.O. Box 1625, Idaho Falls, ID 83415 - USA Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 369 EP - 371 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Accidents KW - Heating KW - Nuclear safety KW - Fuels KW - Strategy KW - Nuclear fuels KW - Vehicles KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786156151?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=TREAT+Experiment+Vehicle+Design+and+Future+Plans&rft.au=Woolstenhulme%2C+N+E%3BBaker%2C+C+C%3BBess%2C+J+D%3BDavis%2C+C+B%3BHousley%2C+G+K%3BJensen%2C+C+B%3BO%27Brien%2C+R+C%3BSnow%2C+S+D&rft.aulast=Woolstenhulme&rft.aufirst=N&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=369&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Benchmark Evaluation of HTR-PROTEUS Absorber Rod Worths (Cores 5 through 8) AN - 1786155775; PQ0002503149 AB - PROTEUS was a zero-power research reactor at the Paul Scherrer Institute (PSI) in Switzerland. The critical assembly was constructed from a large graphite annular reflector surrounding the central cylindrical core cavity. Various experimental programs were investigated in PROTEUS; during the years 1992 through 1996, it was configured as a pebble-bed reactor and designated HTR-PROTEUS. Various critical configurations were assembled with each accompanied by an assortment of reactor physics experiments including differential and integral absorber rod measurements, kinetics, reaction rate distributions, water ingress effects, and small sample reactivity effects [1]. JF - Transactions of the American Nuclear Society AU - Bess, John D AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3855 John.Bess@inl.gov Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 685 EP - 688 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Graphite KW - Proteus KW - Reflectors KW - Assembly KW - Reactor physics KW - Nuclear research reactors KW - Nuclear engineering KW - Holes UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786155775?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Benchmark+Evaluation+of+HTR-PROTEUS+Absorber+Rod+Worths+%28Cores+5+through+8%29&rft.au=Bess%2C+John+D&rft.aulast=Bess&rft.aufirst=John&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=685&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Transient Testing Scientific Infrastructure Development to Support TREAT AN - 1786154940; PQ0002503069 AB - The execution of transient testing to support development of nuclear fuels and materials requires the availability of unique reactor facilities and scientific infrastructure. The Transient Test Reactor (TREAT) facility at the Idaho National Laboratory will be resuming operations in the near future to enable these missions. The scientific infrastructure to support utilization of the reactor is being developed in parallel to the restart effort. This infrastructure includes the development of advanced modeling and simulation tools necessary to perform high fidelity experiments, irradiation vehicles that provide the desired operational environments, in-pile instrumentation (including the fast neutron hodoscope), and post irradiation examination tools targeted at evaluation of disrupted fuels. Recent progress in these areas is discussed in this paper. JF - Transactions of the American Nuclear Society AU - Wachs, Daniel M AD - Idaho National Laboratory, 2525 North Fremont Ave., Idaho Falls, Idaho 83415, USA daniel.wachs@inl.gov Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 347 EP - 349 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Infrastructure KW - Nuclear power generation KW - Nuclear reactors KW - Instrumentation KW - Availability KW - Irradiation KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786154940?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Transient+Testing+Scientific+Infrastructure+Development+to+Support+TREAT&rft.au=Wachs%2C+Daniel+M&rft.aulast=Wachs&rft.aufirst=Daniel&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=347&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Status of the TREAT Reactor Restart and the Resumption of Transient Testing AN - 1786153026; PQ0002503070 AB - The U.S. Department of Energy has authorized resumption of transient testing and the restart of the Transient Reactor Test (TREAT) facility. The TREAT facility was used from 1959 to 1994 (when in was placed in standby) to conduct more than 2,800 nuclear fuel transient tests. The plant was extensively upgraded in the 1980s, with upgrades completed in 1989. Present day assessments reveal that a sound infrastructure remains at the TREAT facility and the previous procedures, drawings, and other documentation were preserved. Several personnel who were involved in historical operations are available and are consulting on the resumption of operations activities. JF - Transactions of the American Nuclear Society AU - Bumgardner, John AD - Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415 USA john.bumgardner@inl.gov Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 350 EP - 351 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Assessments KW - Personnel KW - Nuclear fuels KW - Historic KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1786153026?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Status+of+the+TREAT+Reactor+Restart+and+the+Resumption+of+Transient+Testing&rft.au=Bumgardner%2C+John&rft.aulast=Bumgardner&rft.aufirst=John&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=350&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-05-01 N1 - Last updated - 2016-05-03 ER - TY - JOUR T1 - Reservoir fluid characterization; key to effective CCUS reservoir assessment AN - 1780805204; 2016-034316 AB - Fluid characterization is a vital component of reservoir characterization projects. In this study we present the geochemical and isotopic results of reservoir fluids and dissolved gases from the Mississippian Madison Limestone and Pennsylvanian Weber Sandstone from a potential CCUS target on the Rock Springs Uplift in southwestern Wyoming. Results are used to evaluate brine evolution, predict geochemical fluid reactions in response to CO (sub 2) injection and well completion practices, and investigate stacked reservoir confinement. The brines are Na-Cl type with total dissolved solid concentrations in excess of 85,000 mg/L. Conservative analyses indicate that the evolution of the brines in both formations have been heavily influenced by evaporite dissolution, increasing the molar ratio of Br-Na-Cl. Dolomitization at depth in each reservoir results in magnesium depletion. Comparative analysis suggests that dissolution of evaporite and other minerals has had a large influence on the evolution of the formation fluids. This has resulted in increased TDS post-burial, resulting in some of the most saline formation fluids collected in Wyoming. Simulations of CO (sub 2) injection into the formation brines suggest a decrease in pH, resulting in CaCO (sub 3) dissolution and CaSO (sub 4) precipitation. These reactions could cause an increase in porosity of 1% to 3%, and increase the viability of storage. We also note significant changes to molar ratios of Br-Na-Cl, and the concentrations of HCO (sub 3) , SO4 and volatile organic compounds before and after work over in the well-bore. The differences of solute concentrations between samples sets could be attributable to different collection methods, but are more likely recording changes to the formation fluid from work-over practices in the well-bore. The isotopic compositions of fluids and dissolved gases were found to be unique to each formation. Rare earth element concentrations further establish distinctive fluid concentrations. Though these fluids share a similar evolution, we suggest that dissimilarities in the isotopic compositions of the brines, dissolved gases and rare earth element concentrations indicate that the target formation fluids are isolated from each other. JF - Abstracts with Programs - Geological Society of America AU - Quillinan, Scott AU - McLaughlin, J Fred AU - McLing, Travis L AU - Anonymous Y1 - 2015 PY - 2015 DA - 2015 SP - 393 PB - Geological Society of America (GSA), Boulder, CO VL - 47 IS - 7 SN - 0016-7592, 0016-7592 KW - 30:Engineering geology KW - 02D:Isotope geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1780805204?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Reservoir+fluid+characterization%3B+key+to+effective+CCUS+reservoir+assessment&rft.au=Quillinan%2C+Scott%3BMcLaughlin%2C+J+Fred%3BMcLing%2C+Travis+L%3BAnonymous&rft.aulast=Quillinan&rft.aufirst=Scott&rft.date=2015-01-01&rft.volume=47&rft.issue=7&rft.spage=393&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2015 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2016-01-01 N1 - PubXState - CO N1 - Last updated - 2016-04-14 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Overview of the BISON Fuel Performance Code AN - 1773830896; PQ0002503062 AB - Since 2009, the Idaho National Laboratory (USA) has been developing a state-of-the-art multidimensional multi-physics fuel performance code called BISON. This paper presents a brief background on the code's underlying computational framework (MOOSE), governing equations, material and behavioral models. Select cases are presented that highlight recently added capabilities of the code including, used fuel disposition, and Loss of Coolant Accidents (LOCA). A brief overview of the verification and LWR validation effort is provided. Lastly, a brief discussion of continued development efforts is included. JF - Transactions of the American Nuclear Society AU - Gamble, Kyle A AU - Williamson, Richard L AU - Stafford, Shane AU - Pastore, Giovanni AU - Perez, Danielle M AU - Hales, Jason D AU - Novascone, Stephen R AU - Gardner, Russell J AU - Spencer, Benjamin W AD - Fuel Modeling and Simulation, Idaho National Laboratory, Idaho Falls, ID, 83415-3840, United States Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 315 EP - 318 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts KW - USA, Idaho KW - Fuels KW - Loss of coolant accidents KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1773830896?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Overview+of+the+BISON+Fuel+Performance+Code&rft.au=Gamble%2C+Kyle+A%3BWilliamson%2C+Richard+L%3BStafford%2C+Shane%3BPastore%2C+Giovanni%3BPerez%2C+Danielle+M%3BHales%2C+Jason+D%3BNovascone%2C+Stephen+R%3BGardner%2C+Russell+J%3BSpencer%2C+Benjamin+W&rft.aulast=Gamble&rft.aufirst=Kyle&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=315&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Last updated - 2016-04-13 N1 - SubjectsTermNotLitGenreText - Fuels; Loss of coolant accidents; USA, Idaho ER - TY - JOUR T1 - On the Characterization of a Drop-in Miniplate Experiment - Structural Response Analysis AN - 1773830440; PQ0002503204 AB - As part of the Global Threat Reduction Initiative (GTRI) / US High Performance Research Reactor (USHPRR), Fuel Development Program (FDP), flow testing was performed on a mini-plate (MP) drop-in experiment at the Oregon State University (OSU) Hydro-Mechanical Fuel Test Facility (HMFTF) to characterize the hardware and its hydro-dynamic response. The information collected from this test will be used to support the development of safety analyses for the irradiation of the samples in the Advanced Test Reactor at Idaho National Laboratory (INL) and to provide accurate flow rates for the development of as-run models in support of post-irradiation examination activities at the INL. JF - Transactions of the American Nuclear Society AU - Jones, Warren AU - Marcum, Wade AU - Weiss, A AU - Howard, T K AU - Woolstenhulme, N AU - Phillips, A M AU - Wiest, J AD - Idaho National Laboratory: 2525 Fremont Ave., Idaho Falls, ID, 83415, Warren.Jones@inl.gov Y1 - 2015///0, PY - 2015 DA - 0, 2015 SP - 911 EP - 914 PB - American Nuclear Society, Inc. VL - 112 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts KW - INE, USA, Oregon KW - USA, Idaho KW - Nuclear reactors KW - Fuels KW - Irradiation KW - Safety KW - Flow rates KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1773830440?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=On+the+Characterization+of+a+Drop-in+Miniplate+Experiment+-+Structural+Response+Analysis&rft.au=Jones%2C+Warren%3BMarcum%2C+Wade%3BWeiss%2C+A%3BHoward%2C+T+K%3BWoolstenhulme%2C+N%3BPhillips%2C+A+M%3BWiest%2C+J&rft.aulast=Jones&rft.aufirst=Warren&rft.date=2015-01-01&rft.volume=112&rft.issue=&rft.spage=911&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Last updated - 2016-03-17 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Irradiation; Fuels; Safety; Flow rates; INE, USA, Oregon; USA, Idaho ER - TY - JOUR T1 - Isotopic insights into deep geothermal systems in the Snake River plain in southeastern Idaho AN - 1756504263; 2016-007231 JF - V.M. Goldschmidt Conference - Program and Abstracts AU - Conrad, Mark E AU - Dobson, Patrick F AU - Sonnenthal, Eric L AU - Kennedy, B Mack AU - Spycher, Nicolas AU - Cannon, Cody AU - Wood, Thomas AU - McLing, Travis L AU - Neupane, Ghanashyam AU - Mattson, Earl D AU - Anonymous Y1 - 2015 PY - 2015 DA - 2015 SP - 589 PB - Goldschmidt Conference, [varies] VL - 25 SN - 1042-7287, 1042-7287 KW - United States KW - oxygen KW - isotopes KW - aliphatic hydrocarbons KW - stable isotopes KW - temperature KW - southeastern Idaho KW - ground water KW - Oregon KW - geothermal systems KW - Newberry Volcano KW - carbon KW - movement KW - Idaho KW - methane KW - isotope ratios KW - C-13/C-12 KW - solutes KW - O-18/O-16 KW - alkanes KW - samples KW - geothermal energy KW - Cascade Range KW - organic compounds KW - Deschutes County Oregon KW - D/H KW - hydrogen KW - hydrocarbons KW - Snake River plain KW - 29A:Economic geology, geology of energy sources KW - 02D:Isotope geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1756504263?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=V.M.+Goldschmidt+Conference+-+Program+and+Abstracts&rft.atitle=Isotopic+insights+into+deep+geothermal+systems+in+the+Snake+River+plain+in+southeastern+Idaho&rft.au=Conrad%2C+Mark+E%3BDobson%2C+Patrick+F%3BSonnenthal%2C+Eric+L%3BKennedy%2C+B+Mack%3BSpycher%2C+Nicolas%3BCannon%2C+Cody%3BWood%2C+Thomas%3BMcLing%2C+Travis+L%3BNeupane%2C+Ghanashyam%3BMattson%2C+Earl+D%3BAnonymous&rft.aulast=Conrad&rft.aufirst=Mark&rft.date=2015-01-01&rft.volume=25&rft.issue=&rft.spage=589&rft.isbn=&rft.btitle=&rft.title=V.M.+Goldschmidt+Conference+-+Program+and+Abstracts&rft.issn=10427287&rft_id=info:doi/ L2 - http://goldschmidt.info/2015/uploads/abstracts/finalPDFs/589.pdf LA - English DB - GeoRef N1 - Conference title - Goldschmidt 2015 N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. N1 - Date revised - 2016-01-01 N1 - Last updated - 2016-01-14 N1 - SubjectsTermNotLitGenreText - aliphatic hydrocarbons; alkanes; C-13/C-12; carbon; Cascade Range; D/H; Deschutes County Oregon; geothermal energy; geothermal systems; ground water; hydrocarbons; hydrogen; Idaho; isotope ratios; isotopes; methane; movement; Newberry Volcano; O-18/O-16; Oregon; organic compounds; oxygen; samples; Snake River plain; solutes; southeastern Idaho; stable isotopes; temperature; United States ER - TY - JOUR T1 - Experimental and modeling studies of episodic air-water two-phase flow in fractures and fracture networks AN - 1752577096; 2016-003441 JF - Geophysical Monograph AU - Wood, Thomas AU - Huang, Hai Y1 - 2015 PY - 2015 DA - 2015 SP - 209 EP - 228 PB - Wiley for American Geophysical Union, Washington, DC VL - 210 SN - 0065-8448, 0065-8448 KW - United States KW - pumping KW - characterization KW - unsaturated zone KW - mechanism KW - Box Canyon KW - observations KW - ground water KW - eastern Idaho KW - laboratory studies KW - fractures KW - transport KW - discharge KW - processes KW - Idaho KW - experimental studies KW - air-water interface KW - Hell's Half Acre KW - two-dimensional models KW - aquifers KW - models KW - infiltration KW - wettability KW - field studies KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1752577096?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Geophysical+Monograph&rft.atitle=Experimental+and+modeling+studies+of+episodic+air-water+two-phase+flow+in+fractures+and+fracture+networks&rft.au=Wood%2C+Thomas%3BHuang%2C+Hai&rft.aulast=Wood&rft.aufirst=Thomas&rft.date=2015-01-01&rft.volume=210&rft.issue=&rft.spage=209&rft.isbn=9781118877203&rft.btitle=&rft.title=Geophysical+Monograph&rft.issn=00658448&rft_id=info:doi/ L2 - http://agupubs.onlinelibrary.wiley.com/agu/books/geophysical-monograph-series.html LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. N1 - Date revised - 2016-01-01 N1 - Number of references - 50 N1 - PubXState - DC N1 - Document feature - illus. incl. sketch map N1 - Last updated - 2015-12-31 N1 - CODEN - GPMGAD N1 - SubjectsTermNotLitGenreText - air-water interface; aquifers; Box Canyon; characterization; discharge; eastern Idaho; experimental studies; field studies; fractures; ground water; Hell's Half Acre; Idaho; infiltration; laboratory studies; mechanism; models; observations; processes; pumping; transport; two-dimensional models; United States; unsaturated zone; wettability ER - TY - JOUR T1 - Development of positron annihilation spectroscopy for investigating deuterium decorated voids in neutron-irradiated tungsten AN - 1746886421; PQ0002263609 AB - The present work is a continuation of a recent research to develop and optimize positron annihilation spectroscopy (PAS) for characterizing neutron-irradiated tungsten. Tungsten samples were exposed to neutrons in the High Flux Isotope Reactor (HF1R) at Oak Ridge National Laboratory and damaged to 0.025 and 0.3 dpa. Subsequently, they were exposed to deuterium plasmas in the Tritium Plasma Experiment (TPE) at Idaho National Laboratory. The implanted deuterium was desorbed through sample heating to 900 [degrees]C, and Doppler broadening (DB)-PAS was performed both before and after heating. Results show that deuterium impregnated tungsten is identified as having a smaller S-parameter. The S-parameter increases after deuterium desorption. Microstructural changes also occur during sample heating. These effects can be isolated from deuterium desorption by comparing the S-parameters from the deuterium-free back face with the deuterium-implanted front face. The application of using DB-PAS to examine deuterium retention in tungsten is examined. JF - Journal of Nuclear Materials AU - Taylor, C N AU - Shimada, M AU - Merrill, B J AU - Akers, D W AU - Hatano, Y AD - Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID 83415, USA, chase.taylor@inl.gov PY - 2015 SP - 1009 EP - 1012 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 463 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - USA, Tennessee, Oak Ridge KW - USA, Idaho KW - Isotopes KW - Desorption KW - Nuclear reactors KW - Laboratory testing KW - Tritium KW - Radioactive materials KW - Deuterium KW - Spectroscopy KW - Tungsten KW - ENA 07:General UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1746886421?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Development+of+positron+annihilation+spectroscopy+for+investigating+deuterium+decorated+voids+in+neutron-irradiated+tungsten&rft.au=Taylor%2C+C+N%3BShimada%2C+M%3BMerrill%2C+B+J%3BAkers%2C+D+W%3BHatano%2C+Y&rft.aulast=Taylor&rft.aufirst=C&rft.date=2015-01-01&rft.volume=463&rft.issue=&rft.spage=1009&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.11.033 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-12-01 N1 - Number of references - 16 N1 - Last updated - 2015-12-23 N1 - SubjectsTermNotLitGenreText - Isotopes; Nuclear reactors; Desorption; Laboratory testing; Tritium; Radioactive materials; Deuterium; Spectroscopy; Tungsten; USA, Tennessee, Oak Ridge; USA, Idaho DO - http://dx.doi.org/10.1016/j.jnucmat.2014.11.033 ER - TY - JOUR T1 - Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten AN - 1746884568; PQ0002263608 AB - Three tungsten samples irradiated at High Flux Isotope Reactor at Oak Ridge National Laboratory were exposed to deuterium plasma (ion fluence of 1 x 10 super(26) m super(-2)) at three different temperatures (100, 200, and 500 [degrees]C) in Tritium Plasma Experiment at Idaho National Laboratory. Subsequently, thermal desorption spectroscopy was performed with a ramp rate of 10 [degrees]C min super(-1) up to 900 [degrees]C, and the samples were annealed at 900 [degrees]C for 0.5 h. These procedures were repeated three times to uncover defect-annealing effects on deuterium retention. The results show that deuterium retention decreases approximately 70% for at 500 [degrees]C after each annealing, and radiation damages were not annealed out completely even after the 3rd annealing. TMAP modeling revealed the trap concentration decreases approximately 80% after each annealing at 900 [degrees]C for 0.5 h. JF - Journal of Nuclear Materials AU - Shimada, Masashi AU - Hara, Masanori AU - Otsuka, Teppei AU - Oya, Yasuhisa AU - Hatano, Yuji AD - Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID, USA, Masashi.Shimada@inl.gov PY - 2015 SP - 1005 EP - 1008 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 463 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Isotopes KW - Desorption KW - Laboratory testing KW - Deuterium KW - Temperature KW - Spectroscopy KW - Tungsten KW - USA, Tennessee, Oak Ridge KW - USA, Idaho KW - Nuclear reactors KW - Radiation KW - Tritium KW - Radioactive materials KW - ENA 14:Radiological Contamination UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1746884568?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Defect+annealing+and+thermal+desorption+of+deuterium+in+low+dose+HFIR+neutron-irradiated+tungsten&rft.au=Shimada%2C+Masashi%3BHara%2C+Masanori%3BOtsuka%2C+Teppei%3BOya%2C+Yasuhisa%3BHatano%2C+Yuji&rft.aulast=Shimada&rft.aufirst=Masashi&rft.date=2015-01-01&rft.volume=463&rft.issue=&rft.spage=1005&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.10.054 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-12-01 N1 - Number of references - 21 N1 - Last updated - 2015-12-23 N1 - SubjectsTermNotLitGenreText - Isotopes; Nuclear reactors; Desorption; Radiation; Laboratory testing; Tritium; Radioactive materials; Temperature; Deuterium; Spectroscopy; Tungsten; USA, Tennessee, Oak Ridge; USA, Idaho DO - http://dx.doi.org/10.1016/j.jnucmat.2014.10.054 ER - TY - JOUR T1 - Unsaturated phosphazenes as co-solvents for lithium-ion battery electrolytes AN - 1686433025; PQ0001529990 AB - This paper covers the synthesis and use of a related family of cyclic phosphazene solvents containing terminal unsaturations that are being considered as electrolyte additives in lithium-ion cells. A brief synopsis on the synthesis and purification of these compounds is given. Data will be presented that covers physical and chemical properties of the phosphazenes as well as the properties when blended at various levels with representative organic carbonate baseline solvents. Electrochemical cycling data will be presented using commercially available electrode couples as well as studies focusing on cell performance at early lifetime as well as after repeated cycles. Conclusions regarding the effect of the unsaturated phosphazene compounds and their interaction with various alkyl carbonates, and their effect on cell performance will be presented. JF - Journal of Power Sources AU - Harrup, Mason K AU - Rollins, Harry W AU - Jamison, David K AU - Dufek, Eric J AU - Gering, Kevin L AU - Luther, Thomas A AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, USA Y1 - 2015 PY - 2015 DA - 2015 SP - 794 EP - 801 PB - Elesevier Science B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 278 SN - 0378-7753, 0378-7753 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Phosphazene KW - Electrolytes KW - Lithium-ion battery KW - Unsaturated KW - Electrolytic cells KW - Carbonates KW - Solvents KW - Synthesis KW - Lithium batteries UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1686433025?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Power+Sources&rft.atitle=Unsaturated+phosphazenes+as+co-solvents+for+lithium-ion+battery+electrolytes&rft.au=Harrup%2C+Mason+K%3BRollins%2C+Harry+W%3BJamison%2C+David+K%3BDufek%2C+Eric+J%3BGering%2C+Kevin+L%3BLuther%2C+Thomas+A&rft.aulast=Harrup&rft.aufirst=Mason&rft.date=2015-01-01&rft.volume=278&rft.issue=&rft.spage=794&rft.isbn=&rft.btitle=&rft.title=Journal+of+Power+Sources&rft.issn=03787753&rft_id=info:doi/10.1016%2Fj.jpowsour.2014.07.109 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-12-07 DO - http://dx.doi.org/10.1016/j.jpowsour.2014.07.109 ER - TY - JOUR T1 - Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling AN - 1673394875; PQ0001169697 AB - The role of uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the BISON fuel performance code with a recently implemented physics-based model for fission gas release and swelling. Through the integration of BISON with the DAKOTA software, a sensitivity analysis of the results to selected model parameters is carried out based on UO sub(2) single-pellet simulations covering different power regimes. The parameters are varied within ranges representative of the relative uncertainties and consistent with the information in the open literature. The study leads to an initial quantitative assessment of the uncertainty in fission gas behavior predictions with the parameter characterization presently available. Also, the relative importance of the single parameters is evaluated. Moreover, a sensitivity analysis is carried out based on simulations of a fuel rod irradiation experiment, pointing out a significant impact of the considered uncertainties on the calculated fission gas release and cladding diametral strain. The results of the study indicate that the commonly accepted deviation between calculated and measured fission gas release by a factor of 2 approximately corresponds to the inherent modeling uncertainty at high fission gas release. Nevertheless, significantly higher deviations may be expected for values around 10% and lower. Implications are discussed in terms of directions of research for the improved modeling of fission gas behavior for engineering purposes. JF - Journal of Nuclear Materials AU - Pastore, Giovanni AU - Swiler, L P AU - Hales, J D AU - Novascone, S R AU - Perez, D M AU - Spencer, B W AU - Luzzi, L AU - Van Uffelen, P AU - Williamson, R L AD - Fuel Modeling and Simulation, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3840, United States, Giovanni.Pastore@inl.gov Y1 - 2015/01// PY - 2015 DA - Jan 2015 SP - 398 EP - 408 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 456 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Prediction KW - Computer programs KW - Sensitivity analysis KW - Behavior KW - Fuels KW - Irradiation KW - Bison KW - Nuclear fuels KW - Radioactive materials KW - Simulation KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1673394875?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Uncertainty+and+sensitivity+analysis+of+fission+gas+behavior+in+engineering-scale+fuel+modeling&rft.au=Pastore%2C+Giovanni%3BSwiler%2C+L+P%3BHales%2C+J+D%3BNovascone%2C+S+R%3BPerez%2C+D+M%3BSpencer%2C+B+W%3BLuzzi%2C+L%3BVan+Uffelen%2C+P%3BWilliamson%2C+R+L&rft.aulast=Pastore&rft.aufirst=Giovanni&rft.date=2015-01-01&rft.volume=456&rft.issue=&rft.spage=398&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.09.077 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-04-01 N1 - Number of references - 68 N1 - Last updated - 2015-11-16 N1 - SubjectsTermNotLitGenreText - Prediction; Computer programs; Behavior; Sensitivity analysis; Irradiation; Fuels; Radioactive materials; Nuclear fuels; Simulation; Bison DO - http://dx.doi.org/10.1016/j.jnucmat.2014.09.077 ER - TY - JOUR T1 - Reactor Physics Measurements and Benchmark Specifications for Oak Ridge Highly Enriched Uranium Sphere (ORSphere) AN - 1770382142; PQ0002252098 AB - In the early 1970s, J. T. Mihalczo (team leader), J. J. Lynn, and J. R. Taylor performed experiments at the Oak Ridge Critical Experiments Facility with highly enriched uranium (HEU) metal (called Oak Ridge Alloy or ORALLOY) in an effort to recreate GODIVA I results with greater accuracy than those performed at Los Alamos National Laboratory in the 1950s. The purpose of the Oak Ridge ORALLOY Sphere experiments was to estimate the unreflected and unmoderated critical mass of an idealized sphere of uranium metal corrected to a density, purity, and enrichment such that it could be compared with the GODIVA I experiments. Additionally, various material reactivity worths, the surface material worth coefficient, the delayed neutron fraction, the prompt neutron decay constant, relative fission density, and relative neutron importance were all measured. The critical assembly, material reactivity worths, the surface material worth coefficient, and the delayed neutron fraction were all evaluated as benchmark experiment measurements. The reactor physics measurements are the focus of this paper; although for clarity the critical assembly benchmark specifications are briefly discussed. JF - Nuclear Science and Engineering AU - Marshall, Margaret A AD - Idaho National Laboratory 2525 North Fremont, Idaho Falls, Idaho 83415-3860 margaret.marshall@inl.gov Y1 - 2014/12// PY - 2014 DA - December 2014 SP - 446 EP - 458 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 4 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Uranium KW - Density KW - Benchmarking KW - Enrichment KW - Specifications KW - Research facilities KW - Reactor physics KW - Coefficients UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1770382142?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Reactor+Physics+Measurements+and+Benchmark+Specifications+for+Oak+Ridge+Highly+Enriched+Uranium+Sphere+%28ORSphere%29&rft.au=Marshall%2C+Margaret+A&rft.aulast=Marshall&rft.aufirst=Margaret&rft.date=2014-12-01&rft.volume=178&rft.issue=4&rft.spage=446&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-32 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 22 N1 - Last updated - 2016-03-04 DO - http://dx.doi.org/10.13182/NSE14-32 ER - TY - JOUR T1 - Evaluation of Cadmium Ratio and Foil Activation Measurements for a Beryllium-Reflected Assembly of U(93.15)O sub(2) Fuel Rods (1,506-cm Triangular Pitch) AN - 1770380589; PQ0002252099 AB - A series of small, compact critical assembly experiments was completed from 1962 to 1965 at Oak Ridge National Laboratory's Critical Experiments Facility in support of the Medium-Power Reactor Experiments program. Initial experiments, performed in November and December 1962, consisted of a core of unmoderated stainless steel tubes surrounded by a graphite reflector. Later experiments included beryllium-reflected assemblies with the fuel in a 1.506-cm triangular lattice and in seven-tube clusters. Once the critical configurations had been achieved, various measurements of reactivity, relative axial and radial activation rates of super(2)35 super(,) and cadmium ratios were performed. The critical configurations, the cadmium ratio, and activation rate measurements for the beryllium-reflected 1,506-cm-array critical configuration have been evaluated and are described in this paper. It was found that these measurements are acceptable as benchmark experiments and have been included in the International Handbook of Evaluated Reactor Physics Benchmark Experiments and the International Handbook of Evaluated Criticality Safety Benchmark Experiments JF - Nuclear Science and Engineering AU - Marshall, Margaret A AD - Idaho National Laboratory, 2525 North Fremont Avenue, Idaho Falls, Idaho 83415-3860 margaret.marshall@inl.gov Y1 - 2014/12// PY - 2014 DA - December 2014 SP - 479 EP - 495 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 4 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Activation KW - Handbooks KW - Activation analysis KW - Cadmium KW - Assembly KW - Nuclear reactor components KW - Benchmarking KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1770380589?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Evaluation+of+Cadmium+Ratio+and+Foil+Activation+Measurements+for+a+Beryllium-Reflected+Assembly+of+U%2893.15%29O+sub%282%29+Fuel+Rods+%281%2C506-cm+Triangular+Pitch%29&rft.au=Marshall%2C+Margaret+A&rft.aulast=Marshall&rft.aufirst=Margaret&rft.date=2014-12-01&rft.volume=178&rft.issue=4&rft.spage=479&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-43 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 18 N1 - Last updated - 2016-03-04 DO - http://dx.doi.org/10.13182/NSE14-43 ER - TY - JOUR T1 - Evaluation of Neutron Radiography Reactor LEU-Core Start-Up Measurements AN - 1770298794; PQ0002252105 AB - Benchmark models were developed to evaluate the cold-critical start-up measurements performed during the fresh core reload of the neutron radiography (NRAD)reactor with low-enriched uranium fuel. Experiments include criticality, control rod worth measurements, shutdown margin, and excess reactivity for four core loadings with 56, 60, 62, and 64 fuel elements. The worths of four graphite reflector block assemblies and an empty dry tube used for experiment irradiations were also measured and evaluated for the 60-fuel-element core configuration. Dominant uncertainties in the experimental k sub(e)ffcome from uncertainties in the manganese content and impurities in the stainless steel fuel cladding as well as the super(236)U and erbium poison content in the fuel matrix. Calculations with MCNP5 (Monte Carlo N-Particle version 5-1.60) and ENDF/B-VII.0 neutron nuclear data are ~1.4% (9[sigma]) greater than the benchmark model eigenvalues, which is commonly seen in Monte Carlo simulations of other TRIGA (Training, Research, Isotopes, General Atomics) reactors. Simulations of the worth measurements are within the 2[sigma] uncertainty for most of the benchmark experiment worth values. The complete benchmark evaluation details are available in the 2014 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments JF - Nuclear Science and Engineering AU - Bess, John D AU - Maddock, Thomas L AU - Smolinski, Andrew T AU - Marshall, Margaret A AD - Idaho National Laboratory, P.O. Box 1625, MS 3855, Idaho Falls, Idaho 83415 john.bess@inl.gov Y1 - 2014/12// PY - 2014 DA - December 2014 SP - 550 EP - 561 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 4 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Uncertainty KW - Nuclear power generation KW - Nuclear reactors KW - Computer simulation KW - Monte Carlo methods KW - Fuels KW - Nuclear reactor components KW - Benchmarking UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1770298794?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Evaluation+of+Neutron+Radiography+Reactor+LEU-Core+Start-Up+Measurements&rft.au=Bess%2C+John+D%3BMaddock%2C+Thomas+L%3BSmolinski%2C+Andrew+T%3BMarshall%2C+Margaret+A&rft.aulast=Bess&rft.aufirst=John&rft.date=2014-12-01&rft.volume=178&rft.issue=4&rft.spage=550&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-12 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 25 N1 - Last updated - 2016-03-04 DO - http://dx.doi.org/10.13182/NSE14-12 ER - TY - JOUR T1 - wrv; an R package for groundwater flow model construction, Wood River valley aquifer system, Idaho AN - 1765873852; 2016-011815 AB - Groundwater models are one of the main tools used in the hydrogeological sciences to assess resources and to simulate possible effects from future water demands and changes in climate. The hydrological inputs to groundwater models can be numerous and can vary in both time and space. Difficulties associated with model construction are often related to extensive datasets and cumbersome data processing tasks. To mitigate these difficulties, a graphical user interface (GUI) is often employed to aid the input of data for creating models. Unfortunately, GUI software presents an obstacle to reproducibility, a cornerstone of research. The considerable effort required to document processing steps in a GUI program, and the rapid obsoleteness of these steps with subsequent versions of the software, has prompted modelers to explicitly write down processing steps as source code to make them 'easily' reproducible. This research describes the R package wrv, a collection of datasets and functions for pre- and post-processing the numerical groundwater flow model of the Wood River Valley aquifer system, south-central Idaho. R largely facilitates reproducible modeling with the package vignette; a document that is a combination of content and source code. The code is run when the vignette is built, and all data analysis output (such as figures and tables) is created on the fly and inserted into the final document. The wrv package includes two vignettes that explain and run steps that (1) create package datasets from raw data files located on a publicly accessible repository, and (2) create and run the groundwater flow model. MODFLOW-USG, the numerical groundwater model used in this study, is executed from the vignette, and model output is returned for exploratory analyses. The ability of R to perform all processing steps in a single workflow is attributed to its comprehensive list of features; that include geographic information system and time series functionality. JF - American Geophysical Union Fall Meeting AU - Fisher, J C AU - Anonymous Y1 - 2014/12// PY - 2014 DA - December 2014 SP - Abstract H51K EP - 0754 PB - American Geophysical Union, Washington, DC VL - 2014 KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1765873852?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=wrv%3B+an+R+package+for+groundwater+flow+model+construction%2C+Wood+River+valley+aquifer+system%2C+Idaho&rft.au=Fisher%2C+J+C%3BAnonymous&rft.aulast=Fisher&rft.aufirst=J&rft.date=2014-12-01&rft.volume=2014&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2014 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-02-18 N1 - CODEN - #07548 ER - TY - JOUR T1 - Numerical modeling of rocky mountain paleoglaciers; insights into the climate of the Last Glacial Maximum and the subsequent deglaciation AN - 1722153873; 2015-097656 AB - Numerical modeling of paleoglaciers can yield information on the climatic conditions necessary to sustain those glaciers. In this study we apply a coupled 2-d mass/energy balance and flow model (Plummer and Phillips, 2003) to reconstruct local last glacial maximum (LLGM) glaciers and paleoclimate in ten study areas along the crest of the U.S. Rocky Mountains between 33 degrees N and 49 degrees N. In some of the areas, where timing of post-LLGM ice recession is constrained by surface exposure ages on either polished bedrock upvalley from the LLGM moraines or post-LLGM recessional moraines, we use the model to assess magnitudes and rates of climate change during deglaciation. The modeling reveals a complex pattern of LLGM climate. The magnitude of LLGM-to-modern climate change (temperature and/or precipitation change) was greater in both the northern (Montana) Rocky Mountains and southern (New Mexico) Rocky Mountains than in the middle (Wyoming and Colorado) Rocky Mountains. We use temperature depression estimates from global and regional climate models to infer LLGM precipitation from our glacier model results. Our results suggest a reduction of precipitation coupled with strongly depressed temperatures in the north, contrasted with strongly enhanced precipitation and much more modest temperature depression in the south. The middle Rocky Mountains of Colorado and Wyoming appear to have experienced a reduction in precipitation at the LLGM without the strong temperature depression of the northern Rocky Mountains. Preliminary work on modeling of deglaciation in the Sangre de Cristo Range in southern Colorado suggests that approximately half of the LLGM-to-modern climate change took place during the initial approximately 2400 years of deglaciation. If increasing temperature and changing solar insolation were the sole drivers of this initial deglaciation, then temperature would need to have risen by slightly more than 1 degrees C/ky through this interval to account for the observed rate of ice recession. JF - American Geophysical Union Fall Meeting AU - Leonard, E M AU - Laabs, B J C AU - Plummer, Mitchell A AU - Anonymous Y1 - 2014/12// PY - 2014 DA - December 2014 SP - Abstract C52B EP - 01 PB - American Geophysical Union, Washington, DC VL - 2014 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1722153873?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Numerical+modeling+of+rocky+mountain+paleoglaciers%3B+insights+into+the+climate+of+the+Last+Glacial+Maximum+and+the+subsequent+deglaciation&rft.au=Leonard%2C+E+M%3BLaabs%2C+B+J+C%3BPlummer%2C+Mitchell+A%3BAnonymous&rft.aulast=Leonard&rft.aufirst=E&rft.date=2014-12-01&rft.volume=2014&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2014 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2015-10-15 N1 - CODEN - #07548 ER - TY - JOUR T1 - Advanced heat exchanger development for molten salts AN - 1669864589; PQ0001118152 AB - This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non-nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, that show good corrosion resistance in molten salt at nominal operating temperatures up to 700 [degrees]C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Hastelloy N were corrosion tested in 58 mol% KF and 42 mol% ZrF sub(4) at 650, 700, and 850 [degrees]C for 200, 500, and 1000 h. Corrosion rates were similar between welded and non welded materials, typically <100 mu m per year after 1000 h of corrosion tests. No catastrophic corrosion was observed in the diffusion welded regions. For materials of construction, nickel-based alloys and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of the type of salt impurity and alloy composition, with respect to chromium and carbon, to better define the best conditions for corrosion resistance. Also presented is the division of the nuclear reactor and high-temperature components per American Society of Mechanical Engineers (ASME) standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa. JF - Nuclear Engineering and Design AU - Sabharwall, Piyush AU - Clark, Denis AU - Glazoff, Michael AU - Zheng, Guiqiu AU - Sridharan, Kumar AU - Anderson, Mark AD - Idaho National Laboratory, Idaho Falls, ID 83415, United States Y1 - 2014/12// PY - 2014 DA - Dec 2014 SP - 42 EP - 56 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 280 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); METADEX (MD); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); Corrosion Abstracts (CO); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nickel base alloys KW - Superalloys KW - Hastelloy KW - Fused salts KW - Diffusion welding KW - Heat exchangers KW - Corrosion KW - Corrosion resistance KW - Alloys KW - Standards KW - Diffusion UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1669864589?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Advanced+heat+exchanger+development+for+molten+salts&rft.au=Sabharwall%2C+Piyush%3BClark%2C+Denis%3BGlazoff%2C+Michael%3BZheng%2C+Guiqiu%3BSridharan%2C+Kumar%3BAnderson%2C+Mark&rft.aulast=Sabharwall&rft.aufirst=Piyush&rft.date=2014-12-01&rft.volume=280&rft.issue=&rft.spage=42&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2014.09.026 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-04-01 N1 - Number of references - 56 N1 - Last updated - 2015-12-07 DO - http://dx.doi.org/10.1016/j.nucengdes.2014.09.026 ER - TY - JOUR T1 - Quadrature conductivity; a quantitative indicator of bacterial abundance in porous media AN - 1645573467; 2015-006906 AB - The abundance and growth stages of bacteria in subsurface porous media affect the concentrations and distributions of charged species within the solid-solution interfaces. Therefore, spectral induced polarization (SIP) measurements can be used to monitor changes in bacterial biomass and growth stage. Our goal was to gain a better understanding of the SIP response of bacteria present in a porous material. Bacterial cell surfaces possess an electric double layer and therefore become polarized in an electric field. We performed SIP measurements over the frequency range of 0.1-1 kHz on cell suspensions alone and cell suspensions mixed with sand at four pore water conductivities. We used Zymomonas mobilis at four different cell densities (including the background). The quadrature conductivity spectra exhibited two peaks, one around 0.05-0.10 Hz and the other around 1-10 Hz. Because SIP measurements on bacterial suspensions are typically made at frequencies greater than 1 Hz, these peaks have not been previously reported. In the bacterial suspensions in growth medium, the quadrature conductivity at peak I was linearly proportional to the density of the bacteria. For the case of the suspensions mixed with sands, we observed that peak II presented a smaller increase in the quadrature conductivity with the cell density. A comparison of the experiments with and without sand grains illustrated the effect of the porous medium on the overall quadrature conductivity response (decrease in the amplitude and shift of the peaks to the lower frequencies). Our results indicate that for a given porous medium, time-lapse SIP has potential for monitoring changes in bacterial abundance within porous media. JF - Geophysics AU - Zhang, Chi AU - Revil, Andre AU - Fujita, Yoshiko AU - Munakata-Marr, Junko AU - Redden, George Y1 - 2014/12// PY - 2014 DA - December 2014 SP - D363 EP - D375 PB - Society of Exploration Geophysicists, Tulsa, OK VL - 79 IS - 6 SN - 0016-8033, 0016-8033 KW - experimental studies KW - electrical conductivity KW - monitoring KW - biomass KW - numerical analysis KW - geophysical methods KW - electrical methods KW - porous materials KW - resistivity KW - physical properties KW - bacteria KW - time-lapse methods KW - induced polarization KW - applications KW - 20:Applied geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1645573467?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Geophysics&rft.atitle=Quadrature+conductivity%3B+a+quantitative+indicator+of+bacterial+abundance+in+porous+media&rft.au=Zhang%2C+Chi%3BRevil%2C+Andre%3BFujita%2C+Yoshiko%3BMunakata-Marr%2C+Junko%3BRedden%2C+George&rft.aulast=Zhang&rft.aufirst=Chi&rft.date=2014-12-01&rft.volume=79&rft.issue=6&rft.spage=D363&rft.isbn=&rft.btitle=&rft.title=Geophysics&rft.issn=00168033&rft_id=info:doi/10.1190%2Fgeo2014-0107.1 L2 - http://library.seg.org/journal/gpysa7 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data from GeoScienceWorld, Alexandria, VA, United States | Reference includes data supplied by Society of Exploration Geophysicists, Tulsa, OK, United States N1 - Date revised - 2015-01-01 N1 - Number of references - 54 N1 - PubXState - OK N1 - Document feature - illus. incl. 3 tables N1 - Last updated - 2015-01-15 N1 - CODEN - GPYSA7 N1 - SubjectsTermNotLitGenreText - applications; bacteria; biomass; electrical conductivity; electrical methods; experimental studies; geophysical methods; induced polarization; monitoring; numerical analysis; physical properties; porous materials; resistivity; time-lapse methods DO - http://dx.doi.org/10.1190/geo2014-0107.1 ER - TY - JOUR T1 - Influence of Airflow on Laboratory Storage of High Moisture Corn Stover AN - 1635034120; 21110399 AB - Storing high moisture biomass for bioenergy use is a reality in many areas of the country where wet harvest conditions and environmental factors prevent dry storage from being feasible. Aerobic storage of high moisture biomass leads to microbial degradation and self-heating, but oxygen limitation can aid in material preservation. To understand the influence of oxygen presence on high moisture biomass (50 %, wet basis), three airflow rates were tested on corn stover stored in laboratory reactors. Temperature, carbon dioxide production, dry matter loss, chemical composition, fungal abundance, pH, and organic acids were used to monitor the effects of airflow on storage conditions. The results of this work indicate that oxygen availability impacts both the duration of self-heating and the severity of dry matter loss. High airflow systems experienced the greatest initial rates of loss but a shortened microbially active period that limited total dry matter loss (19 %). Intermediate airflow had improved preservation in short-term storage compared to high airflow systems but accumulated the greatest dry matter loss over time (up to 27 %) as a result of an extended microbially active period. Low airflow systems displayed the best performance with the lowest rates of loss and total loss (10 %) in storage at 50 days. Total structural sugar levels of the stored material were preserved, although glucan enrichment and xylan loss were documented in the high and intermediate flow conditions. By understanding the role of oxygen availability on biomass storage performance, the requirements for high moisture storage solutions may begin to be experimentally defined. JF - BioEnergy Research AU - Wendt, Lynn M AU - Bonner, Ian J AU - Hoover, Amber N AU - Emerson, Rachel M AU - Smith, William A AD - Biological and Chemical Processing Department, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, 83415, USA, lynn.wendt@inl.gov Y1 - 2014/12// PY - 2014 DA - Dec 2014 SP - 1212 EP - 1222 PB - Springer Science+Business Media, Van Godewijckstraat 30 Dordrecht 3311 GX Netherlands VL - 7 IS - 4 SN - 1939-1234, 1939-1234 KW - Environment Abstracts; Sustainability Science Abstracts KW - Chemical composition KW - Organic acids KW - Abundance KW - Biomass KW - Environmental factors KW - Flow rates KW - Storage KW - Oxygen KW - Corn KW - Dry matter KW - Carbon dioxide KW - Biofuels KW - pH KW - Air flow KW - M3 1010:Issues in Sustainable Development KW - ENA 01:Air Pollution UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1635034120?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Assamodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=BioEnergy+Research&rft.atitle=Influence+of+Airflow+on+Laboratory+Storage+of+High+Moisture+Corn+Stover&rft.au=Wendt%2C+Lynn+M%3BBonner%2C+Ian+J%3BHoover%2C+Amber+N%3BEmerson%2C+Rachel+M%3BSmith%2C+William+A&rft.aulast=Wendt&rft.aufirst=Lynn&rft.date=2014-12-01&rft.volume=7&rft.issue=4&rft.spage=1212&rft.isbn=&rft.btitle=&rft.title=BioEnergy+Research&rft.issn=19391234&rft_id=info:doi/10.1007%2Fs12155-014-9455-3 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-12-01 N1 - Number of references - 47 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Chemical composition; Organic acids; Abundance; Biomass; Environmental factors; Flow rates; Storage; Oxygen; Corn; Dry matter; Carbon dioxide; pH; Biofuels; Air flow DO - http://dx.doi.org/10.1007/s12155-014-9455-3 ER - TY - CPAPER T1 - Stress and Diffusion in Stored Pu Zppr Fuel from Alpha Generation T2 - 2014 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2014) AN - 1627965708; 6309702 JF - 2014 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2014) AU - Solbrig, Charles Y1 - 2014/11/16/ PY - 2014 DA - 2014 Nov 16 KW - Fuels KW - Stress KW - Diffusion UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1627965708?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2014%29&rft.atitle=Stress+and+Diffusion+in+Stored+Pu+Zppr+Fuel+from+Alpha+Generation&rft.au=Solbrig%2C+Charles&rft.aulast=Solbrig&rft.aufirst=Charles&rft.date=2014-11-16&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2014%29&rft.issn=&rft_id=info:doi/ L2 - https://aiche.confex.com/aiche/2014/webprogram/meeting2014-11-16.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-31 N1 - Last updated - 2014-11-26 ER - TY - CPAPER T1 - Enhanced Separation of Adjacent Rare Earth Elements T2 - 2014 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2014) AN - 1627965300; 6310119 JF - 2014 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2014) AU - Herbst, R AU - Greenhalgh, Mitchell AU - Rutledge, Veronica AU - Garn, Troy Y1 - 2014/11/16/ PY - 2014 DA - 2014 Nov 16 KW - Rare earths KW - Rare earth elements UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1627965300?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2014%29&rft.atitle=Enhanced+Separation+of+Adjacent+Rare+Earth+Elements&rft.au=Herbst%2C+R%3BGreenhalgh%2C+Mitchell%3BRutledge%2C+Veronica%3BGarn%2C+Troy&rft.aulast=Herbst&rft.aufirst=R&rft.date=2014-11-16&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2014%29&rft.issn=&rft_id=info:doi/ L2 - https://aiche.confex.com/aiche/2014/webprogram/meeting2014-11-16.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-31 N1 - Last updated - 2014-11-26 ER - TY - CPAPER T1 - Engineering Aspects of an Actinide/Lanthanide Separation Concept Based on the Oxidation of Americium T2 - 2014 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2014) AN - 1627962566; 6309460 JF - 2014 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2014) AU - Law, Jack AU - Mincher, Bruce AU - Garn, Troy AU - Tillotson, Richard AU - Greenhalgh, Mitchell AU - Schmitt, Nicholas Y1 - 2014/11/16/ PY - 2014 DA - 2014 Nov 16 KW - Oxidation KW - Lanthanides KW - Americium KW - Actinides UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1627962566?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2014%29&rft.atitle=Engineering+Aspects+of+an+Actinide%2FLanthanide+Separation+Concept+Based+on+the+Oxidation+of+Americium&rft.au=Law%2C+Jack%3BMincher%2C+Bruce%3BGarn%2C+Troy%3BTillotson%2C+Richard%3BGreenhalgh%2C+Mitchell%3BSchmitt%2C+Nicholas&rft.aulast=Law&rft.aufirst=Jack&rft.date=2014-11-16&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2014%29&rft.issn=&rft_id=info:doi/ L2 - https://aiche.confex.com/aiche/2014/webprogram/meeting2014-11-16.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-31 N1 - Last updated - 2014-11-26 ER - TY - CPAPER T1 - The Importance of Advanced Supply Systems for Coupling Sustainable Bioenergy Land Use to Biomass Trade T2 - 2014 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2014) AN - 1627961747; 6308240 JF - 2014 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2014) AU - Thompson, David AU - Hess, J AU - Roni, Mohammad Y1 - 2014/11/16/ PY - 2014 DA - 2014 Nov 16 KW - Resource management KW - Trade KW - Sustainable development KW - Biomass KW - Biofuels KW - Land use UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1627961747?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2014%29&rft.atitle=The+Importance+of+Advanced+Supply+Systems+for+Coupling+Sustainable+Bioenergy+Land+Use+to+Biomass+Trade&rft.au=Thompson%2C+David%3BHess%2C+J%3BRoni%2C+Mohammad&rft.aulast=Thompson&rft.aufirst=David&rft.date=2014-11-16&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2014%29&rft.issn=&rft_id=info:doi/ L2 - https://aiche.confex.com/aiche/2014/webprogram/meeting2014-11-16.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-31 N1 - Last updated - 2014-11-26 ER - TY - CPAPER T1 - Effects of the foil flatness on the stress-strain characteristics of U10-Mo alloy based monolithic mini-plates T2 - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AN - 1645178356; 6314005 JF - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AU - Ozaltun, Hakan AU - Medvedev, Pavel Y1 - 2014/11/14/ PY - 2014 DA - 2014 Nov 14 KW - Alloys KW - alloys UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1645178356?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.atitle=Effects+of+the+foil+flatness+on+the+stress-strain+characteristics+of+U10-Mo+alloy+based+monolithic+mini-plates&rft.au=Ozaltun%2C+Hakan%3BMedvedev%2C+Pavel&rft.aulast=Ozaltun&rft.aufirst=Hakan&rft.date=2014-11-14&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2014/ViewAcceptedAbstracts.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-11-30 N1 - Last updated - 2015-01-14 ER - TY - CPAPER T1 - Thermal Predictions of the AGR-3/4 Experiment with Time Varying Gas Gaps T2 - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AN - 1645169058; 6314007 JF - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AU - Hawkes, Grant AU - Sterbentz, James AU - Maki, John Y1 - 2014/11/14/ PY - 2014 DA - 2014 Nov 14 KW - Prediction UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1645169058?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.atitle=Thermal+Predictions+of+the+AGR-3%2F4+Experiment+with+Time+Varying+Gas+Gaps&rft.au=Hawkes%2C+Grant%3BSterbentz%2C+James%3BMaki%2C+John&rft.aulast=Hawkes&rft.aufirst=Grant&rft.date=2014-11-14&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2014/ViewAcceptedAbstracts.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-11-30 N1 - Last updated - 2015-01-14 ER - TY - CPAPER T1 - Process Development for Hot Isostatic Pressing Treatability Study T2 - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AN - 1645168809; 6315622 JF - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AU - Bateman, Kenneth AU - Wahlquist, Dennis AU - Malewitz, Timothy Y1 - 2014/11/14/ PY - 2014 DA - 2014 Nov 14 KW - Mechanical engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1645168809?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.atitle=Process+Development+for+Hot+Isostatic+Pressing+Treatability+Study&rft.au=Bateman%2C+Kenneth%3BWahlquist%2C+Dennis%3BMalewitz%2C+Timothy&rft.aulast=Bateman&rft.aufirst=Kenneth&rft.date=2014-11-14&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2014/ViewAcceptedAbstracts.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-11-30 N1 - Last updated - 2015-01-14 ER - TY - CPAPER T1 - BISON-MOOSE Simulation Framework T2 - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AN - 1645166322; 6314016 JF - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AU - Williamson, Richard AU - Hales, Jason AU - Spencer, Benjamin AU - Novascone, Stephen AU - Perez, Danielle AU - Pastore, Giovanni AU - Gleicher, Fredrick AU - Gardner, Russell Y1 - 2014/11/14/ PY - 2014 DA - 2014 Nov 14 KW - Simulation UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1645166322?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.atitle=BISON-MOOSE+Simulation+Framework&rft.au=Williamson%2C+Richard%3BHales%2C+Jason%3BSpencer%2C+Benjamin%3BNovascone%2C+Stephen%3BPerez%2C+Danielle%3BPastore%2C+Giovanni%3BGleicher%2C+Fredrick%3BGardner%2C+Russell&rft.aulast=Williamson&rft.aufirst=Richard&rft.date=2014-11-14&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2014/ViewAcceptedAbstracts.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-11-30 N1 - Last updated - 2015-01-14 ER - TY - CPAPER T1 - Transfer and Storage of Molten Salt T2 - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AN - 1645157918; 6314379 JF - 2014 International Mechanical Engineering Congress & Exposition (ASME 2014) AU - Bateman, Kenneth AU - Morrison, Matthew Y1 - 2014/11/14/ PY - 2014 DA - 2014 Nov 14 KW - Storage KW - Salts UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1645157918?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.atitle=Transfer+and+Storage+of+Molten+Salt&rft.au=Bateman%2C+Kenneth%3BMorrison%2C+Matthew&rft.aulast=Bateman&rft.aufirst=Kenneth&rft.date=2014-11-14&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2014+International+Mechanical+Engineering+Congress+%26+Exposition+%28ASME+2014%29&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2014/ViewAcceptedAbstracts.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-11-30 N1 - Last updated - 2015-01-14 ER - TY - JOUR T1 - Benchmark Evaluation of HTR-PROTEUS Pebble Bed Experimental Program AN - 1770382645; PQ0002252094 AB - Benchmark models were developed to evaluate 11 critical core configurations of the HTRPROTEUS pebble bed experimental program. Various additional reactor physics measurements were carried out as part of this program; currently, only a total of 37 absorber rod worth measurements have been evaluated as acceptable benchmark experiments for cores 4, 9, and 10. Dominant uncertainties in the experimental k sub(e)fffor all core configurations come from uncertainties in the super(235)U enrichment of the fuel, impurities in the moderator pebbles, and the density and impurity content of the radial reflector. Calculations of k sub(eff) with MCNP5 and ENDF/B-VII.0 neutron nuclear data are greater than the benchmark values but are within 1% and also within the 3[sigma] uncertainty, except for core 4, which is the only randomly packed pebble configuration. Repeated calculations of k sub(eff) with MCNP6.1 and ENDF/B-VII.1 are lower than the benchmark values but are within 1% (~3[sigma]), except for cores 5 and 9, which calculate lower than the benchmark eigenvalues by <4[sigma]. The primary difference between the two nuclear data libraries is the adjustment of the absorption cross section of graphite. Simulations of the absorber rod worth measurements are within 3[sigma] of the benchmark experiment values. The complete benchmark evaluation details are available in the 2014 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments JF - Nuclear Science and Engineering AU - Bess, John D AU - Montierth, Leland M AU - Koberl, Oliver AU - Snoj, Luka AD - Idaho National Laboratory, P.O. Box 1625, MS 3855, Idaho Falls, Idaho 83415 john.bess@inl.gov Y1 - 2014/11// PY - 2014 DA - November 2014 SP - 387 EP - 400 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 3 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Uncertainty KW - Mathematical models KW - Pebble bed KW - Density KW - Impurities KW - Benchmarking KW - Absorption cross sections KW - Reactor physics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1770382645?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Benchmark+Evaluation+of+HTR-PROTEUS+Pebble+Bed+Experimental+Program&rft.au=Bess%2C+John+D%3BMontierth%2C+Leland+M%3BKoberl%2C+Oliver%3BSnoj%2C+Luka&rft.aulast=Bess&rft.aufirst=John&rft.date=2014-11-01&rft.volume=178&rft.issue=3&rft.spage=387&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-13 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 39 N1 - Last updated - 2016-03-04 DO - http://dx.doi.org/10.13182/NSE14-13 ER - TY - JOUR T1 - An Overview of the International Reactor Physics Experiment Evaluation Project AN - 1770382092; PQ0002252085 AB - Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties associated with advanced modeling and simulation accelerate to meet the demands of next-generation reactor and advanced fuel cycle concepts. Two Organisation for Economic Cooperation and Development (OECD)/Nuclear Energy Agency (NEA) activities, the International Criticality Safety Benchmark Evaluation Project (ICSBEP), initiated in 1992, and the International Reactor Physics Experiment Evaluation Project (IRPhEP), initiated in 2003, have been identifying existing integral experiment data, evaluating those data, and providing integral benchmark specifications for methods and data validation for nearly two decades. Data provided by those two projects will be of use to the international reactor physics, criticality safety, and nuclear data communities for future decades. An overview of the IRPhEP and a brief update of the ICSBEP are provided in this paper. JF - Nuclear Science and Engineering AU - Briggs, J Blair AU - Gulliford, Jim AD - Idaho National Laboratory, P.O. Box 1625, MS 3860, Idaho Falls, Idaho 83415-3860 j.briggs@inl.gov Y1 - 2014/11// PY - 2014 DA - November 2014 SP - 269 EP - 279 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 3 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Nuclear safety KW - Integrals KW - Nuclear reactor components KW - Benchmarking KW - Reactor physics KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1770382092?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=An+Overview+of+the+International+Reactor+Physics+Experiment+Evaluation+Project&rft.au=Briggs%2C+J+Blair%3BGulliford%2C+Jim&rft.aulast=Briggs&rft.aufirst=J&rft.date=2014-11-01&rft.volume=178&rft.issue=3&rft.spage=269&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-27 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 9 N1 - Last updated - 2016-03-04 DO - http://dx.doi.org/10.13182/NSE14-27 ER - TY - JOUR T1 - Benchmark Evaluation of Start-Up and Zero-Power Measurements at the High-Temperature Engineering Test Reactor AN - 1770380468; PQ0002252096 AB - Benchmark models were developed to evaluate six cold-critical and two warm-critical, zero-power measurements of the high-temperature engineering test reactor (HTTR). Additional measurements of the subcritical configuration of the fully loaded core, core excess reactivity, shutdown margins, six isothermal temperature coefficients, and axial reaction-rate distributions were also evaluated as acceptable benchmark experiments. Insufficient information is publicly available to develop finely detailed models of the HTTR as much of the design information is still proprietary. The uncertainties in the benchmark models are judged to be of sufficient magnitude to encompass any biases and bias uncertainties incurred through the simplification process used to develop the benchmark models. However, use of the benchmark critical configurations of the HTTR for nuclear data adjustment is not recommended as the impact of these biases has not been addressed with rigorous detail. The impact of any simplification biases, if any, is not expected to significantly impact evaluation of the other reactor physics measurement calculations. Dominant uncertainties in the experimental k sub(e)fffor all core configurations come from uncertainties in the impurity content of the various graphite blocks that compose the HTTR. Monte Carlo calculations of k sub(eff) between ~0.9% and ~2.7% greater than the benchmark values. Reevaluation of the HTTR models as additional information becomes available could improve the quality of this benchmark and possibly reduce the computational biases. High-quality characterization of graphite impurities would significantly improve the quality of the HTTR benchmark assessment. Simulations of the other reactor physics measurements are in good agreement with the benchmark experiment values. The complete benchmark evaluation details are available in the 2014 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments JF - Nuclear Science and Engineering AU - Bess, John D AU - Fujimoto, Nozomu AD - Idaho National Laboratory, P.O. Box 1625, MS 3855, Idaho Falls, Idaho 83415 john.bess@inl.gov Y1 - 2014/11// PY - 2014 DA - November 2014 SP - 414 EP - 427 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 3 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Uncertainty KW - Engineering test reactors KW - Mathematical models KW - Computer simulation KW - Impurities KW - Benchmarking KW - Simplification KW - Reactor physics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1770380468?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Benchmark+Evaluation+of+Start-Up+and+Zero-Power+Measurements+at+the+High-Temperature+Engineering+Test+Reactor&rft.au=Bess%2C+John+D%3BFujimoto%2C+Nozomu&rft.aulast=Bess&rft.aufirst=John&rft.date=2014-11-01&rft.volume=178&rft.issue=3&rft.spage=414&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-14 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 27 N1 - Last updated - 2016-03-04 DO - http://dx.doi.org/10.13182/NSE14-14 ER - TY - JOUR T1 - Applications of Integral Benchmark Data AN - 1770273507; PQ0002252087 AB - The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) provide evaluated integral benchmark data that may be used for validation of reactor physics/nuclear criticality safety analytical methods and data, nuclear data testing, advanced modeling and simulation, and safety analysis licensing activities. The handbooks produced by these programs are used in over 30 countries. Five example applications are presented in this paper: (a) use of IRPhEP data in uncertainty analyses and cross-section adjustment, (b) uncertainty evaluation methods for reactor core design at Japan Atomic Energy Agency using reactor physics experimental data, (c) application of benchmarking data to a broad range of criticality safety problems, (d) cross-section data testing with ICSBEP benchmarks, and (e) use of the International Handbook of Evaluated Reactor Physics Benchmark Experiments to support the power industry. JF - Nuclear Science and Engineering AU - Palmiotti, Giuseppe AU - Briggs, J Blair AU - Kugo, Teruhiko AU - Trumble, Edward AU - Kahler, Albert C AU - Lancaster, Dale AD - Idaho National Laboratory, Nuclear Systems Design and Analysis Division, P.O. Box 1625, MS 3860, Idaho Falls, Idaho 83415-3860 giuseppe.palmiotti@inl.gov Y1 - 2014/11// PY - 2014 DA - November 2014 SP - 295 EP - 310 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 3 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Uncertainty KW - Handbooks KW - Nuclear safety KW - Integrals KW - Cross sections (physics) KW - Benchmarking KW - Reactor physics KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1770273507?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Applications+of+Integral+Benchmark+Data&rft.au=Palmiotti%2C+Giuseppe%3BBriggs%2C+J+Blair%3BKugo%2C+Teruhiko%3BTrumble%2C+Edward%3BKahler%2C+Albert+C%3BLancaster%2C+Dale&rft.aulast=Palmiotti&rft.aufirst=Giuseppe&rft.date=2014-11-01&rft.volume=178&rft.issue=3&rft.spage=295&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/10.13182%2FNSE14-33 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2016-03-01 N1 - Number of references - 33 N1 - Last updated - 2016-03-04 DO - http://dx.doi.org/10.13182/NSE14-33 ER - TY - JOUR T1 - Summary of the Snowmastodon Project special volume AN - 1656039964; 2015-016312 AB - In North America, terrestrial records of biodiversity and climate change that span Marine Oxygen Isotope Stage (MIS) 5 are rare. Where found, they provide insight into how the coupling of the ocean-atmosphere system is manifested in biotic and environmental records and how the biosphere responds to climate change. In 2010-2011, construction at Ziegler Reservoir near Snowmass Village, Colorado (USA) revealed a nearly continuous, lacustrine/wetland sedimentary sequence that preserved evidence of past plant communities between approximately 140 and 55 ka, including all of MIS 5. At an elevation of 2705 m, the Ziegler Reservoir fossil site also contained thousands of well-preserved bones of late Pleistocene megafauna, including mastodons, mammoths, ground sloths, horses, camels, deer, bison, black bear, coyotes, and bighorn sheep. In addition, the site contained more than 26,000 bones from at least 30 species of small animals including salamanders, otters, muskrats, minks, rabbits, beavers, frogs, lizards, snakes, fish, and birds. The combination of macro- and micro-vertebrates, invertebrates, terrestrial and aquatic plant macrofossils, a detailed pollen record, and a robust, directly dated stratigraphic framework shows that high-elevation ecosystems in the Rocky Mountains of Colorado are climatically sensitive and varied dramatically throughout MIS 5. Abstract Copyright (2014) Elsevier, B.V. JF - Quaternary Research AU - Miller, Ian M AU - Pigati, Jeffrey S AU - Anderson, R Scott AU - Johnson, Kirk R AU - Mahan, Shannon A AU - Ager, Thomas A AU - Baker, Richard G AU - Blaauw, Maarten AU - Bright, Jordon AU - Brown, Peter M AU - Bryant, Bruce AU - Calamari, Zachary T AU - Carrara, Paul E AU - Cherney, Michael D AU - Demboski, John R AU - Elias, Scott A AU - Fisher, Daniel C AU - Gray, Harrison J AU - Haskett, Danielle R AU - Honke, Jeffrey S AU - Jackson, Stephen T AU - Jimenez-Moreno, Gonzalo AU - Kline, Douglas AU - Leonard, Eric M AU - Lifton, Nathaniel A AU - Lucking, Carol AU - Gregory McDonald, H AU - Miller, Dane M AU - Muhs, Daniel R AU - Nash, Stephen E AU - Newton, Cody AU - Paces, James B AU - Petrie, Lesley AU - Plummer, Mitchell A AU - Porinchu, David F AU - Rountrey, Adam N AU - Scott, Eric AU - Sertich, Joseph J W AU - Sharpe, Saxon E AU - Skipp, Gary L AU - Strickland, Laura E AU - Stucky, Richard K AU - Thompson, Robert S AU - Wilson, Jim Y1 - 2014/11// PY - 2014 DA - November 2014 SP - 618 EP - 634 PB - Elsevier, New York, NY VL - 82 IS - 3 SN - 0033-5894, 0033-5894 KW - Snowmass Village Colorado KW - paleoclimatology KW - excavations KW - paleoecology KW - Elephantoidea KW - Theria KW - bones KW - Ziegler Reservoir KW - Invertebrata KW - Elephantidae KW - Eutheria KW - Snowmastodon Project KW - Insecta KW - North America KW - Chordata KW - Quaternary KW - biostratigraphy KW - Mammalia KW - faunal studies KW - Central Rocky Mountains KW - Mandibulata KW - palynomorphs KW - Pleistocene KW - Colorado KW - Diptera KW - Tetrapoda KW - United States KW - lithostratigraphy KW - fossil localities KW - Chironomidae KW - Pitkin County Colorado KW - Neoptera KW - Pterygota KW - Ostracoda KW - upper Pleistocene KW - Cenozoic KW - pollen KW - sediments KW - miospores KW - Endopterygota KW - Mammuthus KW - biodiversity KW - chronostratigraphy KW - Crustacea KW - Proboscidea KW - paleoenvironment KW - Arthropoda KW - floral studies KW - reconstruction KW - Vertebrata KW - Rocky Mountains KW - microfossils KW - 24:Quaternary geology KW - 08:General paleontology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1656039964?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Quaternary+Research&rft.atitle=Summary+of+the+Snowmastodon+Project+special+volume&rft.au=Miller%2C+Ian+M%3BPigati%2C+Jeffrey+S%3BAnderson%2C+R+Scott%3BJohnson%2C+Kirk+R%3BMahan%2C+Shannon+A%3BAger%2C+Thomas+A%3BBaker%2C+Richard+G%3BBlaauw%2C+Maarten%3BBright%2C+Jordon%3BBrown%2C+Peter+M%3BBryant%2C+Bruce%3BCalamari%2C+Zachary+T%3BCarrara%2C+Paul+E%3BCherney%2C+Michael+D%3BDemboski%2C+John+R%3BElias%2C+Scott+A%3BFisher%2C+Daniel+C%3BGray%2C+Harrison+J%3BHaskett%2C+Danielle+R%3BHonke%2C+Jeffrey+S%3BJackson%2C+Stephen+T%3BJimenez-Moreno%2C+Gonzalo%3BKline%2C+Douglas%3BLeonard%2C+Eric+M%3BLifton%2C+Nathaniel+A%3BLucking%2C+Carol%3BGregory+McDonald%2C+H%3BMiller%2C+Dane+M%3BMuhs%2C+Daniel+R%3BNash%2C+Stephen+E%3BNewton%2C+Cody%3BPaces%2C+James+B%3BPetrie%2C+Lesley%3BPlummer%2C+Mitchell+A%3BPorinchu%2C+David+F%3BRountrey%2C+Adam+N%3BScott%2C+Eric%3BSertich%2C+Joseph+J+W%3BSharpe%2C+Saxon+E%3BSkipp%2C+Gary+L%3BStrickland%2C+Laura+E%3BStucky%2C+Richard+K%3BThompson%2C+Robert+S%3BWilson%2C+Jim&rft.aulast=Miller&rft.aufirst=Ian&rft.date=2014-11-01&rft.volume=82&rft.issue=3&rft.spage=618&rft.isbn=&rft.btitle=&rft.title=Quaternary+Research&rft.issn=00335894&rft_id=info:doi/10.1016%2Fj.yqres.2014.07.004 L2 - http://www.sciencedirect.com/science/journal/00335894 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2015-01-01 N1 - Number of references - 63 N1 - PubXState - NY N1 - Document feature - illus. incl. sects., 3 tables, sketch map N1 - Last updated - 2015-04-16 N1 - CODEN - QRESAV N1 - SubjectsTermNotLitGenreText - Arthropoda; biodiversity; biostratigraphy; bones; Cenozoic; Central Rocky Mountains; Chironomidae; Chordata; chronostratigraphy; Colorado; Crustacea; Diptera; Elephantidae; Elephantoidea; Endopterygota; Eutheria; excavations; faunal studies; floral studies; fossil localities; Insecta; Invertebrata; lithostratigraphy; Mammalia; Mammuthus; Mandibulata; microfossils; miospores; Neoptera; North America; Ostracoda; paleoclimatology; paleoecology; paleoenvironment; palynomorphs; Pitkin County Colorado; Pleistocene; pollen; Proboscidea; Pterygota; Quaternary; reconstruction; Rocky Mountains; sediments; Snowmass Village Colorado; Snowmastodon Project; Tetrapoda; Theria; United States; upper Pleistocene; Vertebrata; Ziegler Reservoir DO - http://dx.doi.org/10.1016/j.yqres.2014.07.004 ER - TY - JOUR T1 - Numerical modeling of the Snowmass Creek paleoglacier, Colorado, and climate in the Rocky Mountains during the Bull Lake glaciation (MIS 6) AN - 1656039161; 2015-016304 AB - Well-preserved moraines from the penultimate, or Bull Lake, glaciation of Snowmass Creek Valley in the Elk Range of Colorado (USA) present an opportunity to examine the character of the high-altitude climate in the Rocky Mountains during Marine Oxygen Isotope Stage 6. This study employs a 2-D coupled mass/energy balance and flow model to assess the magnitudes of temperature and precipitation change that could have sustained the glacier in mass-balance equilibrium at its maximum extent during the Bull Lake glaciation. Variable substrate effects on glacier flow and ice thickness make the modeling somewhat more complex than in geologically simpler settings. Model results indicate that a temperature depression of about 6.7 degrees C compared with the present (1971-2000 AD) would have been necessary to sustain the Snowmass Creek glacier in mass-balance equilibrium during the Bull Lake glaciation, assuming no change in precipitation amount or seasonality. A 50% increase or decrease from modern precipitation would have been coupled with 5.2 degrees C and 9.1 degrees C Bull Lake temperature depressions respectively. Uncertainty in these modeled temperature depressions is about 1 degrees C. Abstract Copyright (2014) Elsevier, B.V. JF - Quaternary Research AU - Leonard, Eric M AU - Plummer, Mitchell A AU - Carrara, Paul E Y1 - 2014/11// PY - 2014 DA - November 2014 SP - 533 EP - 541 PB - Elsevier, New York, NY VL - 82 IS - 3 SN - 0033-5894, 0033-5894 KW - United States KW - glaciation KW - glacial extent KW - Pitkin County Colorado KW - finite difference analysis KW - paleoclimatology KW - energy balance KW - upper Pleistocene KW - Cenozoic KW - mass balance KW - digital simulation KW - moraines KW - Snowmastodon Project KW - MIS 6 KW - North America KW - Quaternary KW - numerical models KW - Snowmass Creek valley KW - glacial features KW - flows KW - ice movement KW - Central Rocky Mountains KW - paleoenvironment KW - Pleistocene KW - glacial geology KW - Colorado KW - Rocky Mountains KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1656039161?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Quaternary+Research&rft.atitle=Numerical+modeling+of+the+Snowmass+Creek+paleoglacier%2C+Colorado%2C+and+climate+in+the+Rocky+Mountains+during+the+Bull+Lake+glaciation+%28MIS+6%29&rft.au=Leonard%2C+Eric+M%3BPlummer%2C+Mitchell+A%3BCarrara%2C+Paul+E&rft.aulast=Leonard&rft.aufirst=Eric&rft.date=2014-11-01&rft.volume=82&rft.issue=3&rft.spage=533&rft.isbn=&rft.btitle=&rft.title=Quaternary+Research&rft.issn=00335894&rft_id=info:doi/10.1016%2Fj.yqres.2014.03.001 L2 - http://www.sciencedirect.com/science/journal/00335894 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2015-01-01 N1 - Number of references - 35 N1 - PubXState - NY N1 - Document feature - illus. incl. 2 tables, geol. sketch map N1 - Last updated - 2015-02-19 N1 - CODEN - QRESAV N1 - SubjectsTermNotLitGenreText - Cenozoic; Central Rocky Mountains; Colorado; digital simulation; energy balance; finite difference analysis; flows; glacial extent; glacial features; glacial geology; glaciation; ice movement; mass balance; MIS 6; moraines; North America; numerical models; paleoclimatology; paleoenvironment; Pitkin County Colorado; Pleistocene; Quaternary; Rocky Mountains; Snowmass Creek valley; Snowmastodon Project; United States; upper Pleistocene DO - http://dx.doi.org/10.1016/j.yqres.2014.03.001 ER - TY - JOUR T1 - Microstructural characterization of irradiated U-7Mo/Al-5Si dispersion fuel to high fission density AN - 1655732424; 21198822 AB - The fuel development program for research and test reactors calls for improved knowledge on the effect of microstructure on fuel performance in reactors. This paper summarizes the recent TEM microstructural characterization of an irradiated U-7Mo/Al-5Si dispersion fuel plate (R3R050) in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) to 5.2 x 10 super(21) fissions/cm super(3). While a large fraction of the fuel grains is decorated with large bubbles, there is no evidence showing interlinking of these bubbles at the specified fission density. The attachment of solid fission product precipitates to the bubbles is likely the result of fission product diffusion into these bubbles. The process of fission gas bubble superlattice collapse appears through bubble coalescence. The results are compared with the previous TEM work on the dispersion fuels irradiated to lower fission density from the same fuel plate. JF - Journal of Nuclear Materials AU - Gan, J AU - Miller, B D AU - Keiser, D D, Jr AU - Robinson, A B AU - Madden, J W AU - Medvedev, P G AU - Wachs, D M AD - Nuclear Fuels and Materials Division, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6146, USA, Jian.Gan@inl.gov Y1 - 2014/11// PY - 2014 DA - Nov 2014 SP - 434 EP - 445 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 454 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Fission products KW - USA, Idaho KW - Nuclear reactors KW - Fuels KW - Nuclear fuels KW - Radioactive materials KW - Diffusion KW - Grains KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1655732424?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Microstructural+characterization+of+irradiated+U-7Mo%2FAl-5Si+dispersion+fuel+to+high+fission+density&rft.au=Gan%2C+J%3BMiller%2C+B+D%3BKeiser%2C+D+D%2C+Jr%3BRobinson%2C+A+B%3BMadden%2C+J+W%3BMedvedev%2C+P+G%3BWachs%2C+D+M&rft.aulast=Gan&rft.aufirst=J&rft.date=2014-11-01&rft.volume=454&rft.issue=1-3&rft.spage=434&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.08.052 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-02-01 N1 - Number of references - 17 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Fission products; Nuclear reactors; Fuels; Radioactive materials; Nuclear fuels; Diffusion; Grains; USA, Idaho DO - http://dx.doi.org/10.1016/j.jnucmat.2014.08.052 ER - TY - JOUR T1 - Discrete element method for simulation of early-life thermal fracturing behavior in ceramic nuclear fuel pellets AN - 1642324799; 21023500 AB - A discrete element method (DEM) representation of coupled solid mechanics, fracturing and heat conduction processes is developed and applied to explicitly simulate the random initiation and subsequent propagation of interacting thermal cracks in a ceramic nuclear fuel pellet during initial rise to power and during power cycles. The DEM model clearly predicts realistic early-life crack patterns including both radial and circumferential cracks. Simulation results clearly demonstrate the formation of radial cracks during the initial power rise and formation of circumferential cracks as the power is ramped down. In these simulations, additional early-life power cycles do not lead to the formation of new thermal cracks. They do, however clearly indicate changes in the apertures of thermal cracks during later power cycles due to thermal expansion and shrinkage. The number of radial cracks increases with increasing power, which is consistent with the experimental observations. JF - Nuclear Engineering and Design AU - Huang, Hai AU - Spencer, Benjamin AU - Hales, Jason AD - Energy and Environment Science & Technology, Idaho National Laboratory, Idaho Falls, ID, USA Y1 - 2014/10/15/ PY - 2014 DA - 2014 Oct 15 SP - 515 EP - 528 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 278 SN - 0029-5493, 0029-5493 KW - Ceramic Abstracts/World Ceramics Abstracts (WC); Mechanical & Transportation Engineering Abstracts (MT); Advanced Polymers Abstracts (EP); Environmental Engineering Abstracts (EN); Composites Industry Abstracts (ED); Engineered Materials Abstracts, Ceramics (EC); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Fracture mechanics KW - Nuclear power generation KW - Discrete element method KW - Computer simulation KW - Formations KW - Fracturing KW - Ceramic nuclear fuels KW - Pellets UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1642324799?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Discrete+element+method+for+simulation+of+early-life+thermal+fracturing+behavior+in+ceramic+nuclear+fuel+pellets&rft.au=Huang%2C+Hai%3BSpencer%2C+Benjamin%3BHales%2C+Jason&rft.aulast=Huang&rft.aufirst=Hai&rft.date=2014-10-15&rft.volume=278&rft.issue=&rft.spage=515&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2014.05.049 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-01-01 N1 - Number of references - 43 N1 - Last updated - 2015-02-05 DO - http://dx.doi.org/10.1016/j.nucengdes.2014.05.049 ER - TY - JOUR T1 - An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques AN - 1642323759; 21023489 AB - AGR-1 was the first in a series of experiments designed to test US TRISO fuel under high temperature gas-cooled reactor irradiation conditions. This experiment was irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) and is currently undergoing post-irradiation examination (PIE) at INL and Oak Ridge National Laboratory. Gamma spectrometry was used to non-destructively evaluate the burnup of all 72 of the TRISO fuel compacts that comprised the AGR-1 experiment. Two methods for evaluating burnup by gamma spectrometry were developed, one based on the Cs-137 activity and the other based on the ratio of Cs-134 and Cs-137 activities. Burnup values determined from both methods compared well with the values predicted from simulations. The results confirm the accuracy of the nondestructive burnup evaluation from gamma spectrometry for TRISO fuel compacts across a burnup range of approximately 10-20% FIMA and also validate the approach used in the physics simulation of the AGR-1 experiment. JF - Nuclear Engineering and Design AU - Harp, Jason M AU - Demkowicz, Paul A AU - Winston, Philip L AU - Sterbentz, James W AD - Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-6188, USA jason.harp@inl.gov Y1 - 2014/10/15/ PY - 2014 DA - 2014 Oct 15 SP - 395 EP - 405 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 278 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear reactors KW - Computer simulation KW - Fuels KW - Compacts KW - Nuclear reactor components KW - Spectroscopy KW - Spectrometry KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1642323759?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=An+analysis+of+nuclear+fuel+burnup+in+the+AGR-1+TRISO+fuel+experiment+using+gamma+spectrometry%2C+mass+spectrometry%2C+and+computational+simulation+techniques&rft.au=Harp%2C+Jason+M%3BDemkowicz%2C+Paul+A%3BWinston%2C+Philip+L%3BSterbentz%2C+James+W&rft.aulast=Harp&rft.aufirst=Jason&rft.date=2014-10-15&rft.volume=278&rft.issue=&rft.spage=395&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2014.07.041 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-01-01 N1 - Number of references - 19 N1 - Last updated - 2015-02-05 DO - http://dx.doi.org/10.1016/j.nucengdes.2014.07.041 ER - TY - CPAPER T1 - A High Temperature Chemical Processing Route to Recycle Spent Nd2Fe14B Magnets T2 - 53rd Annual Conference of Metallurgists (COM2014) AN - 1548628733; 6290944 JF - 53rd Annual Conference of Metallurgists (COM2014) AU - Tripathy, Prabhat Y1 - 2014/09/28/ PY - 2014 DA - 2014 Sep 28 KW - Temperature effects KW - Chemical process industry KW - Magnets KW - High temperature UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1548628733?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=53rd+Annual+Conference+of+Metallurgists+%28COM2014%29&rft.atitle=A+High+Temperature+Chemical+Processing+Route+to+Recycle+Spent+Nd2Fe14B+Magnets&rft.au=Tripathy%2C+Prabhat&rft.aulast=Tripathy&rft.aufirst=Prabhat&rft.date=2014-09-28&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=53rd+Annual+Conference+of+Metallurgists+%28COM2014%29&rft.issn=&rft_id=info:doi/ L2 - http://web.cim.org/COM2014/technical_paper_list.pdf LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-06-30 N1 - Last updated - 2014-07-28 ER - TY - CPAPER T1 - Electrorecycling of Critical and Value Metals from Mobile Electronics T2 - 53rd Annual Conference of Metallurgists (COM2014) AN - 1548628275; 6290936 JF - 53rd Annual Conference of Metallurgists (COM2014) AU - Lister, Tedd AU - Wang, Peiming AU - Anderko, Andre Y1 - 2014/09/28/ PY - 2014 DA - 2014 Sep 28 KW - Metals UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1548628275?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=53rd+Annual+Conference+of+Metallurgists+%28COM2014%29&rft.atitle=Electrorecycling+of+Critical+and+Value+Metals+from+Mobile+Electronics&rft.au=Lister%2C+Tedd%3BWang%2C+Peiming%3BAnderko%2C+Andre&rft.aulast=Lister&rft.aufirst=Tedd&rft.date=2014-09-28&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=53rd+Annual+Conference+of+Metallurgists+%28COM2014%29&rft.issn=&rft_id=info:doi/ L2 - http://web.cim.org/COM2014/technical_paper_list.pdf LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-06-30 N1 - Last updated - 2014-07-28 ER - TY - JOUR T1 - Impact of Harvest Equipment on Ash Variability of Baled Corn Stover Biomass for Bioenergy AN - 1701064370; 20643518 AB - Cost-effective conversion of agricultural residues for renewable energy hinges not only on the material's quality but also the biorefinery's ability to reliably measure quality specifications. The ash content of biomass is one such specification, influencing pretreatment and disposal costs for the conversion facility and the overall value of a delivered lot of biomass. The biomass harvest process represents a primary pathway for accumulation of soil-derived ash within baled material. In this work, the influence of five collection techniques on the total ash content and variability of ash content within baled corn stover in southwest Kansas is discussed. The equipment tested included a mower for cutting the corn stover stubble, a basket rake, wheel rake, or shred flail to gather the stover, and a mixed or uniform in-feed baler for final collection. The results showed mean ash content to range from 11.5 to 28.2 % depending on operational choice. Resulting impacts on feedstock costs for a biochemical conversion process range from $5.38 to $22.30 Mg super(-1) based on the loss of convertible dry matter and ash disposal costs. Collection techniques that minimized soil contact (shred flail or nonmowed stubble) were shown to prevent excessive ash contamination, whereas more aggressive techniques (mowing and use of a wheel rake) caused greater soil disturbance and entrainment within the final baled material. Material sampling and testing were shown to become more difficult as within-bale ash variability increased, creating uncertainty around feedstock quality and the associated costs of ash mitigation. JF - BioEnergy Research AU - Bonner, Ian J AU - Smith, William A AU - Einerson, Jeffery J AU - Kenney, Kevin L AD - Biofuels and Renewable Energy Technologies Department, Idaho National Laboratory, Idaho Falls, ID, USA ian.bonner@inl.gov Y1 - 2014/09// PY - 2014 DA - Sep 2014 SP - 845 EP - 855 PB - Springer Science+Business Media, Van Godewijckstraat 30 Dordrecht 3311 GX Netherlands VL - 7 IS - 3 SN - 1939-1234, 1939-1234 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA) KW - Rakes KW - Costs KW - Collection KW - Renewable energy KW - Corn KW - Conversion KW - Biomass KW - Ashes UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1701064370?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=BioEnergy+Research&rft.atitle=Impact+of+Harvest+Equipment+on+Ash+Variability+of+Baled+Corn+Stover+Biomass+for+Bioenergy&rft.au=Bonner%2C+Ian+J%3BSmith%2C+William+A%3BEinerson%2C+Jeffery+J%3BKenney%2C+Kevin+L&rft.aulast=Bonner&rft.aufirst=Ian&rft.date=2014-09-01&rft.volume=7&rft.issue=3&rft.spage=845&rft.isbn=&rft.btitle=&rft.title=BioEnergy+Research&rft.issn=19391234&rft_id=info:doi/10.1007%2Fs12155-014-9432-x LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-11-01 N1 - Number of references - 25 N1 - Last updated - 2015-08-04 DO - http://dx.doi.org/10.1007/s12155-014-9432-x ER - TY - JOUR T1 - Electrochemical studies and analysis of 1-10 wt% UCl sub(3) concentrations in molten LiCl-KCl eutectic AN - 1611623038; 20782466 AB - Three electrochemical methods - cyclic voltammetry (CV), chronopotentiometry (CP), and anodic stripping voltammetry (ASV) - were applied to solutions of up to 10 wt% UCl sub(3) in the molten LiCl-KCl eutectic salt at 500 [degrees]C to determine electrochemical properties and behaviors and to help provide a scientific basis for the development of an in situ electrochemical probe for determining the concentration of uranium in a used nuclear fuel electrorefiner. Diffusion coefficients of UCl sub(4) and UCl sub(3) were calculated to be (6.72 + or - 0.360) x 10 super(-6) cm super(2)/s and (1.04 + or - 0.17) x 10 super(-5) cm super(2)/s, respectively. Apparent standard reduction potentials were determined to be (-0.381 + or - 0.013) V and (-1.502 + or - 0.076) V vs. 5 mol% Ag/AgCl or (-1.448 + or - 0.013) V and (-2.568 + or - 0.076) V vs. Cl sub(2)/Cl super(-) for the U(IV)/U(III) and U(III)/U redox couples, respectively. In comparing this data with supercooled thermodynamic data to determine activity coefficients, the thermodynamic database used was important with resulting activity coefficients ranging from 2.34 x 10 super(-3) to 1.08 x 10 super(-2) for UCl sub(4) and 4.94 x 10 super(-5) to 4.50 x 10 super(-4) for UCl sub(3). Of anodic stripping voltammetry and cyclic voltammetry anodic or cathodic peaks, the CV cathodic peak height divided by square root of scan rate was shown to be the most reliable method of determining UCl sub(3) concentration in the molten salt. JF - Journal of Nuclear Materials AU - Hoover, Robert O AU - Shaltry, Michael R AU - Martin, Sean AU - Sridharan, Kumar AU - Phongikaroon, Supathorn AD - Chemical and Materials Engineering Department and Nuclear Engineering Program, University of Idaho, Idaho Falls, Center for Advanced Energy Studies, 995 University Blvd, Idaho Falls, ID 83401, USA, supathor@uidaho.edu Y1 - 2014/09// PY - 2014 DA - Sep 2014 SP - 389 EP - 396 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 452 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Salts KW - Thermodynamics KW - Uranium KW - Nuclear fuels KW - Radioactive materials KW - Diffusion KW - Voltammetry KW - Electrochemistry KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1611623038?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Electrochemical+studies+and+analysis+of+1-10+wt%25+UCl+sub%283%29+concentrations+in+molten+LiCl-KCl+eutectic&rft.au=Hoover%2C+Robert+O%3BShaltry%2C+Michael+R%3BMartin%2C+Sean%3BSridharan%2C+Kumar%3BPhongikaroon%2C+Supathorn&rft.aulast=Hoover&rft.aufirst=Robert&rft.date=2014-09-01&rft.volume=452&rft.issue=1-3&rft.spage=389&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.05.057 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Number of references - 23 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Salts; Thermodynamics; Uranium; Radioactive materials; Nuclear fuels; Diffusion; Electrochemistry; Voltammetry DO - http://dx.doi.org/10.1016/j.jnucmat.2014.05.057 ER - TY - JOUR T1 - Molecular dynamics simulations of intergranular fracture in UO sub(2) with nine empirical interatomic potentials AN - 1611619430; 20782452 AB - The intergranular fracture behavior of UO sub(2) was studied using molecular dynamics simulations with a bicrystal model. The anisotropic fracture behavior due to the different grain boundary characters was investigated with the [left angle bracket]100[right angle bracket] symmetrical tilt [Sigma]5 and the [left angle bracket]110[right angle bracket] symmetrical tilt [Sigma]3 ({111} twin) grain boundaries. Nine interatomic potentials, seven rigid-ion plus two core-shell ones, were utilized to elucidate possible potential dependence. Initiating from a notch, crack propagation along grain boundaries was observed for most potentials. The [Sigma]3 boundary was found to be more prone to fracture than the [Sigma]5 one, indicated by a lower energy release rate associated with the former. However, some potential dependence was identified on the existence of transient plastic deformation at crack tips, and the results were discussed regarding the relevant material properties including the excess energies of metastable phases and the critical energy release rate for intergranular fracture. In general, local plasticity at crack tips was observed in fracture simulations with potentials that predict low excess energies for metastable phases and high critical energy release rates for intergranular fracture. JF - Journal of Nuclear Materials AU - Zhang, Yongfeng AU - Millett, Paul C AU - Tonks, Michael R AU - Bai, Xian-Ming AU - Biner, S Bulent AD - Fuels Modeling and Simulation Department, Idaho National Laboratory (INL), Idaho Falls, ID 83415, USA, yongfeng.zhang@inl.gov Y1 - 2014/09// PY - 2014 DA - Sep 2014 SP - 296 EP - 303 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 452 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Energy KW - Radioactive materials KW - Simulation KW - Grains KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1611619430?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Molecular+dynamics+simulations+of+intergranular+fracture+in+UO+sub%282%29+with+nine+empirical+interatomic+potentials&rft.au=Zhang%2C+Yongfeng%3BMillett%2C+Paul+C%3BTonks%2C+Michael+R%3BBai%2C+Xian-Ming%3BBiner%2C+S+Bulent&rft.aulast=Zhang&rft.aufirst=Yongfeng&rft.date=2014-09-01&rft.volume=452&rft.issue=1-3&rft.spage=296&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.05.034 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Number of references - 51 N1 - Last updated - 2015-04-09 N1 - SubjectsTermNotLitGenreText - Energy; Radioactive materials; Simulation; Grains DO - http://dx.doi.org/10.1016/j.jnucmat.2014.05.034 ER - TY - JOUR T1 - Modeling the influence of bubble pressure on grain boundary separation and fission gas release AN - 1611618362; 20782426 AB - Grain boundary (GB) separation as a mechanism for fission gas release (FGR), complementary to gas bubble interlinkage, has been experimentally observed in irradiated light water reactor fuel. However there has been limited effort to develop physics-based models incorporating this mechanism for the analysis of FGR. In this work, a computational study is carried out to investigate GB separation in UO sub(2) fuel under the effect of gas bubble pressure and hydrostatic stress. A non-dimensional stress intensity factor formula is obtained through 2D axisymmetric analyses considering lenticular bubbles and Mode-I crack growth. The obtained functional form can be used in higher length-scale models to estimate the contribution of GB separation to FGR. JF - Journal of Nuclear Materials AU - Chakraborty, Pritam AU - Tonks, Michael R AU - Pastore, Giovanni AD - Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83401, USA, pritam.chakraborty@inl.gov Y1 - 2014/09// PY - 2014 DA - Sep 2014 SP - 95 EP - 101 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 452 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Nuclear reactors KW - Fuels KW - Nuclear fuels KW - Radioactive materials KW - Stress KW - Hydrostatics KW - Grains KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1611618362?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Modeling+the+influence+of+bubble+pressure+on+grain+boundary+separation+and+fission+gas+release&rft.au=Chakraborty%2C+Pritam%3BTonks%2C+Michael+R%3BPastore%2C+Giovanni&rft.aulast=Chakraborty&rft.aufirst=Pritam&rft.date=2014-09-01&rft.volume=452&rft.issue=1-3&rft.spage=95&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.04.023 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Number of references - 38 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Fuels; Radioactive materials; Nuclear fuels; Hydrostatics; Stress; Grains DO - http://dx.doi.org/10.1016/j.jnucmat.2014.04.023 ER - TY - JOUR T1 - Theory and implementation of nuclear safety system codes - Part I: Conservation equations, flow regimes, numerics and significant assumptions AN - 1562665942; 20636785 AB - The design and analysis of the thermal/hydraulic systems of nuclear power plants necessitates system codes that can be used in the analysis of steady-state and transient conditions. The code comparisons provided in the two parts of this article series allow users to select the appropriate system code for their specific problems. In this comparison, the governing equations for mass, momentum and energy conservation are evaluated. It will be shown that the governing equations do not vary substantially between the codes considered. Most of them utilize a lumped approach with only two fields to represent two phase flow. In the second part of this article, the closure relations, experimental verification and validation are discussed. The results of these articles also guide the development of these system codes, the underlying thermal/hydraulic models, and indicate areas where models must be improved to adequately address issues with new reactor design and development activities. JF - Progress in Nuclear Energy AU - Roth, Glenn A AU - Aydogan, Fatih AD - University of Idaho, Center for Advanced Energy Studies, 995 University Blvd., Idaho Falls, ID 83401, United States, rothl58l@vandals.uidaho.edu Y1 - 2014/09// PY - 2014 DA - September 2014 SP - 160 EP - 182 PB - Elsevier B.V., P.O. Box 800 Kidlington Oxford OX5 1DX United Kingdom VL - 76 SN - 0149-1970, 0149-1970 KW - Sustainability Science Abstracts; Health & Safety Science Abstracts KW - System code comparison KW - Nuclear plant analysis KW - RELAP KW - TRACE KW - CATHARE KW - ATHLET KW - Nuclear power plants KW - Hydraulics KW - Nuclear reactors KW - Energy conservation KW - Conservation KW - Nuclear energy KW - H 8000:Radiation Safety/Electrical Safety KW - M3 1010:Issues in Sustainable Development UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562665942?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Assamodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Progress+in+Nuclear+Energy&rft.atitle=Theory+and+implementation+of+nuclear+safety+system+codes+-+Part+I%3A+Conservation+equations%2C+flow+regimes%2C+numerics+and+significant+assumptions&rft.au=Roth%2C+Glenn+A%3BAydogan%2C+Fatih&rft.aulast=Roth&rft.aufirst=Glenn&rft.date=2014-09-01&rft.volume=76&rft.issue=&rft.spage=160&rft.isbn=&rft.btitle=&rft.title=Progress+in+Nuclear+Energy&rft.issn=01491970&rft_id=info:doi/10.1016%2Fj.pnucene.2014.05.011 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2016-02-04 N1 - SubjectsTermNotLitGenreText - Hydraulics; Nuclear power plants; Nuclear reactors; Energy conservation; Conservation; Nuclear energy DO - http://dx.doi.org/10.1016/j.pnucene.2014.05.011 ER - TY - JOUR T1 - Theory and implementation of nuclear safety system codes - Part II: System code closure relations, validation, and limitations AN - 1562665794; 20636775 AB - This is Part II of two articles describing the details of thermal-hydraulic system codes. In this second part of the article series, the system code closure relationships (used to model thermal and mechanical non-equilibrium and the coupling of the phases) for the governing equations are discussed and evaluated. These include several thermal and hydraulic models, such as heat transfer coefficients for various flow regimes, two phase pressure correlations, two phase friction correlations, drag coefficients and interfacial models between the fields. These models are often developed from experimental data. The experiment conditions should be understood to evaluate the efficacy of the closure models. This second part completes the series on the comparison and evaluation of the selected reactor system codes by discussing the closure relations, validation and limitations. These two articles indicate areas where the models can be improved to adequately address issues with new reactor design and development. JF - Progress in Nuclear Energy AU - Roth, Glenn A AU - Aydogan, Fatih AD - University of Idaho, Center for Advanced Energy Studies, 995 University Blvd., Idaho Falls, ID 83401, United States, roth1581@vandals.uidaho.edu Y1 - 2014/09// PY - 2014 DA - September 2014 SP - 55 EP - 72 PB - Elsevier B.V., P.O. Box 800 Kidlington Oxford OX5 1DX United Kingdom VL - 76 SN - 0149-1970, 0149-1970 KW - Health & Safety Science Abstracts KW - System code comparison KW - Nuclear plant analysis KW - RELAP KW - TRACE KW - CATHARE KW - ATHLET KW - Nuclear power plants KW - Hydraulics KW - Nuclear reactors KW - Nuclear energy KW - Heat transfer KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562665794?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Progress+in+Nuclear+Energy&rft.atitle=Theory+and+implementation+of+nuclear+safety+system+codes+-+Part+II%3A+System+code+closure+relations%2C+validation%2C+and+limitations&rft.au=Roth%2C+Glenn+A%3BAydogan%2C+Fatih&rft.aulast=Roth&rft.aufirst=Glenn&rft.date=2014-09-01&rft.volume=76&rft.issue=&rft.spage=55&rft.isbn=&rft.btitle=&rft.title=Progress+in+Nuclear+Energy&rft.issn=01491970&rft_id=info:doi/10.1016%2Fj.pnucene.2014.05.003 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2016-02-04 N1 - SubjectsTermNotLitGenreText - Hydraulics; Nuclear power plants; Nuclear reactors; Nuclear energy; Heat transfer DO - http://dx.doi.org/10.1016/j.pnucene.2014.05.003 ER - TY - JOUR T1 - Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code AN - 1562673544; 20614124 AB - The Idaho National Laboratory (INL) PARFUME (PARticle FUel ModEl) code was used to assess the overall fuel performance of uranium nitride (UN) tristructural isotropic (TRISO) ceramic fuel under irradiation conditions typical of a Light Water Reactor (LWR). The dimensional changes of the fuel particle layers and kernel were calculated, including the formation of an internal gap. The survivability of the UN TRISO particle was estimated depending on the strain behavior of the constituent materials at high fast fluence and burn-up. For nominal cases, internal gas pressure and representative thermal profiles across the kernel and layers were determined along with stress levels in the inner and outer pyrolytic carbon (IPyC/OPyC) and silicon carbide (SiC) layers. These parameters were then used to evaluate fuel particle failure probabilities. Results of the study show that the survivability of UN TRISO fuel under LWR irradiation conditions might only be guaranteed if the kernel and PyC swelling rates are limited at high fast fluence and burn-up. These material properties have large uncertainties at the irradiation levels expected to be reached by UN TRISO fuel in LWRs. Therefore, a large experimental effort would be needed to establish material properties, including kernel and PyC swelling rates, under these conditions before definitive conclusions can be drawn on the behavior of UN TRISO fuel in LWRs. JF - Journal of Nuclear Materials AU - Collin, Blaise P AD - Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-3955, USA, blaise.collin@inl.gov Y1 - 2014/08// PY - 2014 DA - Aug 2014 SP - 65 EP - 77 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 451 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Ceramics KW - USA, Idaho KW - Silicon KW - Nuclear reactors KW - Fuels KW - Irradiation KW - Uranium KW - Nuclear fuels KW - Radioactive materials KW - Stress KW - Particulates KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562673544?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Modeling+and+analysis+of+UN+TRISO+fuel+for+LWR+application+using+the+PARFUME+code&rft.au=Collin%2C+Blaise+P&rft.aulast=Collin&rft.aufirst=Blaise&rft.date=2014-08-01&rft.volume=451&rft.issue=1-3&rft.spage=65&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.03.032 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 16 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Ceramics; Silicon; Nuclear reactors; Uranium; Irradiation; Fuels; Radioactive materials; Nuclear fuels; Stress; Particulates; USA, Idaho DO - http://dx.doi.org/10.1016/j.jnucmat.2014.03.032 ER - TY - JOUR T1 - Submersion criticality safety of tungsten-rhenium urania cermet fuel for space propulsion and power applications AN - 1566856897; 20469390 AB - Nuclear thermal rockets are the preferred propulsion technology for a manned mission to Mars, and tungsten-uranium oxide cermet fuels could provide significant performance and cost advantages for nuclear thermal rockets. A nuclear reactor intended for use in space must remain subcriticai before and during launch, and must remain subcriticai in launch abort scenarios where the reactor falls back to Earth and becomes submerged in terrestrial materials (including seawater, wet sand, or dry sand). Submersion increases reflection of neutrons and also thermalizes the neutron spectrum, which typically increases the reactivity of the core. This effect is typically very significant for compact, fast-spectrum reactors. This paper provides a submersion criticality safety analysis for a representative tungsten/uranium oxide fueled reactor with a range of fuel compositions. Each submersion case considers both the rhenium content in the matrix alloy and the uranium oxide volume fraction in the cermet. The inclusion of rhenium significantly improves the submersion criticality safety of the reactor. While increased uranium oxide content increases the reactivity of the core, it does not significantly affect the submersion behavior of the reactor. There is no significant difference in submersion behavior between reactors with rhenium distributed within the cermet matrix and reactors with a rhenium clad in the coolant channels. The combination of the flooding of the coolant channels in submersion scenarios and the presence of a significant amount of spectral shift absorbers (i.e. high rhenium concentration) further decreases reactivity for short reactor cores compared to longer cores. JF - Nuclear Engineering and Design AU - Craft, A E AU - O'Brien, R C AU - Howe, S D AU - King, J C AD - Center for Space Nuclear Research (CSNR), INL, Idaho Falls, ID, USA, aaron.craft@inl.gov Y1 - 2014/07/01/ PY - 2014 DA - 2014 Jul 01 SP - 143 EP - 149 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 273 SN - 0029-5493, 0029-5493 KW - Health & Safety Science Abstracts KW - Seawater KW - Fuels KW - Safety KW - Tungsten KW - Channels KW - Rhenium KW - Nuclear reactors KW - Safety engineering KW - Sand KW - Uranium KW - Nuclear fuels KW - Flooding KW - Alloys KW - Technology KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1566856897?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Submersion+criticality+safety+of+tungsten-rhenium+urania+cermet+fuel+for+space+propulsion+and+power+applications&rft.au=Craft%2C+A+E%3BO%27Brien%2C+R+C%3BHowe%2C+S+D%3BKing%2C+J+C&rft.aulast=Craft&rft.aufirst=A&rft.date=2014-07-01&rft.volume=273&rft.issue=&rft.spage=143&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2014.01.028 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 25 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Fuels; Seawater; Safety; Tungsten; Rhenium; Channels; Nuclear reactors; Safety engineering; Sand; Uranium; Nuclear fuels; Flooding; Alloys; Technology DO - http://dx.doi.org/10.1016/j.nucengdes.2014.01.028 ER - TY - JOUR T1 - Parametric study on maximum transportable distance and cost for thermal energy transportation using various coolants AN - 1562668438; 20559122 AB - The operation temperature of advanced nuclear reactors is generally higher than commercial light water reactors, and thermal energy from advanced nuclear reactor can be used for various purposes, such as district heating, desalination, hydrogen production and other process heat applications. The process heat industry/facilities will be located outside the nuclear island due to safety measures. This thermal energy from the reactor must be transported a fair distance. In this study, the analytical analysis was conducted to identify the maximum distance that thermal energy could be transported using various coolants such as molten-salts, helium, and water by varying the pipe diameter and mass flow rate. The cost required to transport each coolant was also analyzed. The coolants analyzed are molten salts (such as: KClMgCl sub(2), LiF-NaF-KF (FLiNaK) and KF-ZrF sub(4)), helium, and water. Fluoride salts are superior because of better heat transport characteristics, but chloride salts are most economical for higher temperature transportation purposes. For lower temperature, the water is a possible alternative when compared with helium because low-pressure helium requires extremely high pumping power, which makes the process very inefficient and economically not viable for both low and high-temperature application. JF - Progress in Nuclear Energy AU - Yoon, Su-Jong AU - Sabharwall, Piyush AD - Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415-6188, USA, sujong.yoon@inl.gov Y1 - 2014/07// PY - 2014 DA - July 2014 SP - 110 EP - 119 PB - Elsevier B.V., P.O. Box 800 Kidlington Oxford OX5 1DX United Kingdom VL - 74 SN - 0149-1970, 0149-1970 KW - Health & Safety Science Abstracts; Environment Abstracts KW - Advanced nuclear reactor KW - Thermal energy transportation KW - Maximum transportable distance KW - Cost estimation KW - Molten-salts KW - Helium KW - Safety KW - Chlorides KW - Temperature KW - Flow rates KW - Salts KW - Islands KW - Transportation KW - Nuclear reactors KW - Fluoride KW - Energy KW - Economics KW - Nuclear energy KW - Heat transport KW - ENA 03:Energy KW - H 2000:Transportation UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562668438?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Progress+in+Nuclear+Energy&rft.atitle=Parametric+study+on+maximum+transportable+distance+and+cost+for+thermal+energy+transportation+using+various+coolants&rft.au=Yoon%2C+Su-Jong%3BSabharwall%2C+Piyush&rft.aulast=Yoon&rft.aufirst=Su-Jong&rft.date=2014-07-01&rft.volume=74&rft.issue=&rft.spage=110&rft.isbn=&rft.btitle=&rft.title=Progress+in+Nuclear+Energy&rft.issn=01491970&rft_id=info:doi/10.1016%2Fj.pnucene.2014.02.016 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2016-02-04 N1 - SubjectsTermNotLitGenreText - Safety; Temperature; Chlorides; Flow rates; Salts; Nuclear reactors; Transportation; Islands; Fluoride; Energy; Economics; Helium; Nuclear energy; Heat transport DO - http://dx.doi.org/10.1016/j.pnucene.2014.02.016 ER - TY - JOUR T1 - Modeled Impacts of Cover Crops and Vegetative Barriers on Corn Stover Availability and Soil Quality AN - 1524408390; 19793527 AB - Environmentally benign, economically viable, and socially acceptable agronomic strategies are needed to launch a sustainable lignocellulosic biofuel industry. Our objective was to demonstrate a landscape planning process that can ensure adequate supplies of corn (Zea mays L.) stover feedstock while protecting and improving soil quality. The Landscape Environmental Assessment Framework (LEAF) was used to develop land use strategies that were then scaled up for five U.S. Corn Belt states (Nebraska, Iowa, Illinois, Indiana, and Minnesota) to illustrate the impact that could be achieved. Our results show an annual sustainable stover supply of 194 million Mg without exceeding soil erosion T values or depleting soil organic carbon [i.e., soil conditioning index (SCI)>0] when no-till, winter cover crop, and vegetative barriers were incorporated into the landscape. A second, more rigorous conservation target was set to enhance soil quality while sustainably harvesting stover. By requiring erosion to be 0, the annual sustainable quantity of harvestable stover dropped to148 million Mg. Examining removal rates by state and soil resource showed that soil capability class and slope generally determined the effectiveness of the three conservation practices and the resulting sustainable harvest rate. This emphasizes that sustainable biomass harvest must be based on subfield management decisions to ensure soil resources are conserved or enhanced, while providing sufficient biomass feedstock to support the economic growth of bioenergy enterprises. JF - BioEnergy Research AU - Bonner, Ian J AU - Muth, David J AU - Koch, Joshua B AU - Karlen, Douglas L AD - Idaho National Laboratory Department of Biofuels and Renewable Energy Technologies, US-Department of Energy (DOE), P.O. Box 1625, Idaho Falls, ID, 83415-2025, USA, ian.bonner@inl.gov Y1 - 2014/06// PY - 2014 DA - Jun 2014 SP - 576 EP - 589 PB - Springer Science+Business Media, Van Godewijckstraat 30 Dordrecht 3311 GX Netherlands VL - 7 IS - 2 SN - 1939-1234, 1939-1234 KW - Environment Abstracts; Sustainability Science Abstracts KW - No-till cropping KW - USA, Illinois KW - Environmental assessment KW - Landscape KW - Sustainable development KW - Economic growth KW - Biomass KW - USA, Minnesota KW - Land use KW - Crops KW - USA, Indiana KW - Soil KW - Erosion KW - USA, Iowa KW - Zea mays KW - Corn KW - USA, Nebraska KW - Conservation KW - Harvesting KW - Biofuels KW - ENA 03:Energy KW - M3 1010:Issues in Sustainable Development UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1524408390?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Assamodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=BioEnergy+Research&rft.atitle=Modeled+Impacts+of+Cover+Crops+and+Vegetative+Barriers+on+Corn+Stover+Availability+and+Soil+Quality&rft.au=Bonner%2C+Ian+J%3BMuth%2C+David+J%3BKoch%2C+Joshua+B%3BKarlen%2C+Douglas+L&rft.aulast=Bonner&rft.aufirst=Ian&rft.date=2014-06-01&rft.volume=7&rft.issue=2&rft.spage=576&rft.isbn=&rft.btitle=&rft.title=BioEnergy+Research&rft.issn=19391234&rft_id=info:doi/10.1007%2Fs12155-014-9423-y LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-05-01 N1 - Number of references - 46 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - No-till cropping; Environmental assessment; Landscape; Sustainable development; Economic growth; Biomass; Crops; Land use; Soil; Erosion; Corn; Conservation; Biofuels; Harvesting; Zea mays; USA, Indiana; USA, Iowa; USA, Illinois; USA, Nebraska; USA, Minnesota DO - http://dx.doi.org/10.1007/s12155-014-9423-y ER - TY - JOUR T1 - Late Quaternary glacier sensitivity to temperature and precipitation distribution in the Southern Alps of New Zealand AN - 1656033693; 2014-071457 AB - Glaciers respond to climate variations and leave geomorphic evidence that represents an important terrestrial paleoclimate record. However, the accuracy of paleoclimate reconstructions from glacial geology is limited by the challenge of representing mountain meteorology in numerical models. Precipitation is usually treated in a simple manner and yet represents difficult-to-characterize variables such as amount, distribution, and phase. Furthermore, precipitation distributions during a glacial probably differed from present-day interglacial patterns. We applied two models to investigate glacier sensitivity to temperature and precipitation in the eastern Southern Alps of New Zealand. A 2-D model was used to quantify variations in the length of the reconstructed glaciers resulting from plausible precipitation distributions compared to variations in length resulting from change in mean annual air temperature and precipitation amount. A 1-D model was used to quantify variations in length resulting from interannual climate variability. Assuming that present-day interglacial values represent precipitation distributions during the last glacial, a range of plausible present-day precipitation distributions resulted in uncertainty in the Last Glacial Maximum length of the Pukaki Glacier of 17.1 km (24%) and the Rakaia Glacier of 9.3 km (25%), corresponding to a 0.5 degrees C difference in temperature. Smaller changes in glacier length resulted from a 50% decrease in precipitation amount from present-day values (-14% and -18%) and from a 50% increase in precipitation amount (5% and 9%). Our results demonstrate that precipitation distribution can produce considerable variation in simulated glacier extents and that reconstructions of paleoglaciers should include this uncertainty. Abstract Copyright (2014) American Geophysical Union. All Rights Reserved. JF - Journal of Geophysical Research: Earth Surface AU - Rowan, Ann V AU - Brocklehurst, Simon H AU - Schultz, David M AU - Plummer, Mitchell A AU - Anderson, Leif S AU - Glasser, Neil F Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 1064 EP - 1081 PB - Wiley-Blackwell for American Geophysical Union, Washington, DC VL - 119 IS - 5 SN - 2169-9003, 2169-9003 KW - Rakaia Glacier KW - Quaternary KW - Australasia KW - one-dimensional models KW - glaciers KW - atmospheric precipitation KW - Southern Alps KW - glacial features KW - paleoclimatology KW - two-dimensional models KW - temperature KW - Cenozoic KW - South Island KW - upper Quaternary KW - glacial geology KW - geomorphology KW - Pukaki Glacier KW - New Zealand KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1656033693?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Geophysical+Research%3A+Earth+Surface&rft.atitle=Late+Quaternary+glacier+sensitivity+to+temperature+and+precipitation+distribution+in+the+Southern+Alps+of+New+Zealand&rft.au=Rowan%2C+Ann+V%3BBrocklehurst%2C+Simon+H%3BSchultz%2C+David+M%3BPlummer%2C+Mitchell+A%3BAnderson%2C+Leif+S%3BGlasser%2C+Neil+F&rft.aulast=Rowan&rft.aufirst=Ann&rft.date=2014-05-01&rft.volume=119&rft.issue=5&rft.spage=1064&rft.isbn=&rft.btitle=&rft.title=Journal+of+Geophysical+Research%3A+Earth+Surface&rft.issn=21699003&rft_id=info:doi/10.1002%2F2013JF003009 L2 - http://onlinelibrary.wiley.com/journal/10.1002/%28ISSN%292169-9011/issues?year=2013 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data from John Wiley & Sons, Chichester, United Kingdom N1 - Date revised - 2014-01-01 N1 - Number of references - 32 N1 - PubXState - DC N1 - Document feature - illus. incl. 4 tables, sketch map N1 - Last updated - 2015-02-19 N1 - SubjectsTermNotLitGenreText - atmospheric precipitation; Australasia; Cenozoic; geomorphology; glacial features; glacial geology; glaciers; New Zealand; one-dimensional models; paleoclimatology; Pukaki Glacier; Quaternary; Rakaia Glacier; South Island; Southern Alps; temperature; two-dimensional models; upper Quaternary DO - http://dx.doi.org/10.1002/2013JF003009 ER - TY - JOUR T1 - Microscopic analysis of irradiated AGR-1 coated particle fuel compacts AN - 1559699367; 20284685 AB - The AGR-1 experiment involved irradiation of 72 TRISO-coated particle fuel compacts to a peak compact-average burnup of 19.5% FIMA with no inpile failures observed out of 3 x 10 super(5) total particles. Irradiated AGR-1 fuel compacts have been cross-sectioned and analyzed with optical microscopy to characterize kernel, buffer, and coating behavior. Six compacts have been examined, spanning a range of irradiation conditions (burnup, fast fluence, and irradiation temperature) and including all fourTRlSO coating variations irradiated in the AGR-1 experiment. The cylindrical specimens were sectioned both transversely and longitudinally, then polished to expose from 36 to 79 individual particles near midplane on each mount. The analysis focused primarily on kernel swelling and porosity, buffer densification and fracturing, buffer-IPyC debonding, and fractures in the IPyC and SiC layers. Characteristic morphologies have been identified, 981 particles have been classified, and spatial distributions of particle types have been mapped. No significant spatial patterns were discovered in these cross sections. However, some trends were found between morphological types and certain behavioral aspects. Buffer fractures were found in 23% of the particles, and these fractures often resulted in unconstrained kernel protrusion into the open cavities. Fractured buffers and buffers that stayed bonded to IPyC layers appear related to larger pore size in kernels. Buffer-IPyC interface integrity evidently factored into initiation of rare IPyC fractures. Fractures through part of the SiC layer were found in only four classified particles, all in conjunction with IPyC-SiC debonding. Compiled results suggest that the deliberate coating fabrication variations influenced the frequencies of IPyC fractures and IPyC-SiC debonds. JF - Nuclear Engineering and Design AU - Ploger, Scott A AU - Demkowicz, Paul A AU - Hunn, John D AU - Kehn, Jay S AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3855, USA scott.ploger@inl.gov Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 221 EP - 230 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 271 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Fracture mechanics KW - Coating KW - Irradiation KW - Fuels KW - Buffers KW - Debonding KW - Kernels KW - Compacts UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1559699367?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Microscopic+analysis+of+irradiated+AGR-1+coated+particle+fuel+compacts&rft.au=Ploger%2C+Scott+A%3BDemkowicz%2C+Paul+A%3BHunn%2C+John+D%3BKehn%2C+Jay+S&rft.aulast=Ploger&rft.aufirst=Scott&rft.date=2014-05-01&rft.volume=271&rft.issue=&rft.spage=221&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2013.11.036 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 9 N1 - Last updated - 2014-10-03 DO - http://dx.doi.org/10.1016/j.nucengdes.2013.11.036 ER - TY - JOUR T1 - Status of the NGNP fuel experiment AGR-2 irradiated in the advanced test reactor AN - 1559695295; 20284687 AB - The United States Department of Energy's Next Generation Nuclear Plant (NGNP) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating up to seven separate low enriched uranium (LEU) trisotopic (TRISO) particle fuel experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and will be irradiated over the next several years to demonstrate and qualify new TRISO coated particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The design of this experiment and support systems will be briefly discussed, followed by the progress and status of the experiment to date. JF - Nuclear Engineering and Design AU - Grover, S Blaine AU - Petti, David A AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, United States Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 238 EP - 243 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 271 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear reactors KW - Advanced test reactors KW - Design engineering KW - Irradiation KW - Fuels KW - Nuclear fuels KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1559695295?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Status+of+the+NGNP+fuel+experiment+AGR-2+irradiated+in+the+advanced+test+reactor&rft.au=Grover%2C+S+Blaine%3BPetti%2C+David+A&rft.aulast=Grover&rft.aufirst=S&rft.date=2014-05-01&rft.volume=271&rft.issue=&rft.spage=238&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2013.11.038 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 4 N1 - Last updated - 2014-10-03 DO - http://dx.doi.org/10.1016/j.nucengdes.2013.11.038 ER - TY - JOUR T1 - Status of the NGNP graphite creep experiments AGC-1 and AGC-2 irradiated in the advanced test reactor AN - 1559689602; 20284694 AB - The United States Department of Energy's Next Generation Nuclear Plant (NGNP) Program will be irradiating six nuclear graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data, including irradiation creep, at different temperatures and loading conditions to support design of the next generation nuclear plant (NGNP) very high temperature gas reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain six peripheral stacks of graphite specimens, with half of the graphite specimens in each stack under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six peripheral stacks will have three different compressive loads applied to the top half of three diametrically opposite pairs of specimen stacks, while a seventh stack will not have a compressive load. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during irradiation of the experiment. JF - Nuclear Engineering and Design AU - Grover, S Blaine AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, United States Blaine.Grover@inl.gov Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 275 EP - 282 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 271 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Advanced Polymers Abstracts (EP); Environmental Engineering Abstracts (EN); Composites Industry Abstracts (ED); Engineered Materials Abstracts, Ceramics (EC); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Creep (materials) KW - Graphite KW - Advanced test reactors KW - Irradiation KW - Temperature KW - Stacks KW - Nuclear reactor components KW - Gas reactors UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1559689602?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Status+of+the+NGNP+graphite+creep+experiments+AGC-1+and+AGC-2+irradiated+in+the+advanced+test+reactor&rft.au=Grover%2C+S+Blaine&rft.aulast=Grover&rft.aufirst=S&rft.date=2014-05-01&rft.volume=271&rft.issue=&rft.spage=275&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2013.11.048 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 2 N1 - Last updated - 2014-10-03 DO - http://dx.doi.org/10.1016/j.nucengdes.2013.11.048 ER - TY - JOUR T1 - The effect of birthrate granularity on the release-to-birth ratio for the AGR-1 in-core experiment AN - 1559684054; 20284686 AB - The AGR-1 Advanced Gas Reactor (AGR) tristructural-isotropic-particle fuel experiment underwent 13 irradiation intervals from December 2006 until November 2009 within the Idaho National Laboratory Advanced Test Reactor in support of the Next Generation Nuclear Power Plant program. During this multi-year experiment, release-to-birth rate ratios were computed at the end of each operating interval to provide information about fuel performance. Fission products released during irradiation were tracked daily by the Fission Product Monitoring System using 8-h measurements. Birth rate calculated by MCNP with ORIGEN for as-run conditions were computed at the end of each irradiation interval. Each time step in MCNP provided neutron flux, reaction rates and AGR-1 compact composition, which were used to determine birth rate using ORIGEN. The initial birth-rate data, consisting of four values for each irradiation interval at the beginning, end, and two intermediate times, were interpolated to obtain values for each 8-h activity. The problem with this method is that any daily changes in heat rates or perturbations, such as shim control movement or core/lobe power fluctuations, would not be reflected in the interpolated data and a true picture of the system would not be presented. At the conclusion of the AGR-1 experiment, great efforts were put forth to compute daily birthrates, which were reprocessed with the 8-h release activity. The results of this study are presented in this paper. JF - Nuclear Engineering and Design AU - Scates, D M AU - Walter, J B AU - Maki, J T AU - Sterbentz, J W AU - Parry, J R AD - Idaho National Laboratory, 2525 North Fremont Avenue, Idaho Falls, ID 83415, USA Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 231 EP - 237 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 271 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Fission products KW - Birth KW - Nuclear power plants KW - Nuclear power generation KW - Computation KW - Irradiation KW - Fuels KW - Intervals UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1559684054?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=The+effect+of+birthrate+granularity+on+the+release-to-birth+ratio+for+the+AGR-1+in-core+experiment&rft.au=Scates%2C+D+M%3BWalter%2C+J+B%3BMaki%2C+J+T%3BSterbentz%2C+J+W%3BParry%2C+J+R&rft.aulast=Scates&rft.aufirst=D&rft.date=2014-05-01&rft.volume=271&rft.issue=&rft.spage=231&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2013.11.037 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 14 N1 - Last updated - 2014-10-03 DO - http://dx.doi.org/10.1016/j.nucengdes.2013.11.037 ER - TY - JOUR T1 - Improving thermal model prediction through statistical analysis of irradiation and post-irradiation data from AGR experiments AN - 1559683999; 20284683 AB - As part of the High Temperature Reactors (HTR) R&D program, a series of irradiation tests, designated as Advanced Gas-cooled Reactor (AGR), have been defined to support development and qualification of fuel design, fabrication process, and fuel performance under normal operation and accident conditions. The AGR tests employ fuel compacts placed in a graphite cylinder shrouded by a steel capsule and instrumented with thermocouples (TC) embedded in graphite blocks enabling temperature control. While not possible to obtain by direct measurements in the tests, crucial fuel conditions are calculated using core physics and thermal modeling codes. This paper is focused on AGR test fuel temperature predicted by the ABAQUS code's finite element-based thermal models. This suggests a more physics-based modification of the thermal model that leads to a better fit with experimental data, thus reducing model uncertainty and increasing confidence in the calculated fuel temperatures of the AGR-1 test. JF - Nuclear Engineering and Design AU - Pham, Binh T AU - Hawkes, Grant L AU - Einerson, Jeffrey J AD - Human Factor, Controls and Statistics Department, Nuclear Science and Technology, Idaho National Laboratory, Idaho Falls, ID 83415, USA Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 209 EP - 216 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 271 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Mathematical models KW - Cylinders KW - AGR KW - Fuels KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1559683999?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Improving+thermal+model+prediction+through+statistical+analysis+of+irradiation+and+post-irradiation+data+from+AGR+experiments&rft.au=Pham%2C+Binh+T%3BHawkes%2C+Grant+L%3BEinerson%2C+Jeffrey+J&rft.aulast=Pham&rft.aufirst=Binh&rft.date=2014-05-01&rft.volume=271&rft.issue=&rft.spage=209&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2013.11.034 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 11 N1 - Last updated - 2014-10-03 DO - http://dx.doi.org/10.1016/j.nucengdes.2013.11.034 ER - TY - JOUR T1 - Silver (Ag) transport mechanisms in TRISO coated particles: A critical review AN - 1559678511; 20284678 AB - Transport of super(110m)Ag in the intact SIC layer of TRISO coated particles has been studied for approximately 30 years without arriving at a satisfactory explanation of the transport mechanism. In this paper the possible mechanisms postulated in previous experimental studies, both in-reactor and out-of reactor research environment studies are critically reviewed and of particular interest are relevance to very high temperature gas reactor operating and accident conditions. Among the factors thought to influence Ag transport are grain boundary stoichiometry. SIC grain size and shape, the presence of free silicon, nano-cracks, thermal decomposition, palladium attack, transmutation products, layer thinning and coated particle shape. Additionally new insight to nature and location of fission products has been gained via recent post irradiation electron microscopy examination of TRISO coated particles from the DOE's fuel development program. The combined effect of critical review and new analyses indicates a direction for investigating possible the Ag transport mechanism including the confidence level with which these mechanisms may be experimentally verified. JF - Nuclear Engineering and Design AU - van Rooyena, I J AU - Dunzik-Gougar, M L AU - van Rooyen, P M AD - Idaho National Laboratory, Idaho Falls, ID 83415-6188, USA Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 180 EP - 188 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 271 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear reactors KW - Coated particles KW - Transport KW - Nuclear reactor components KW - Silver KW - Palladium KW - Confidence intervals KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1559678511?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Silver+%28Ag%29+transport+mechanisms+in+TRISO+coated+particles%3A+A+critical+review&rft.au=van+Rooyena%2C+I+J%3BDunzik-Gougar%2C+M+L%3Bvan+Rooyen%2C+P+M&rft.aulast=van+Rooyena&rft.aufirst=I&rft.date=2014-05-01&rft.volume=271&rft.issue=&rft.spage=180&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2013.11.029 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 44 N1 - Last updated - 2014-10-03 DO - http://dx.doi.org/10.1016/j.nucengdes.2013.11.029 ER - TY - JOUR T1 - Design and status of the NGNP fuel experiment AGR-3/4 irradiated in the advanced test reactor AN - 1559678414; 20284671 AB - The United States Department of Energy's Next Generation Nuclear Plant (NGNP) advanced gas reactor (AGR) Fuel Development and Qualification Program will be irradiating up to seven separate low enriched uranium (LEU) trisotopic (TRISO) particle fuel experiments in the advanced test reactor (ATR) located at the Idaho National Laboratory (INL). The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The third and fourth experiments have been combined into a single experiment designated AGR-3/4, which started its irradiation in December 2011 and is currently scheduled to be completed in November 2013. The purpose and design of this experiment will be discussed followed by its progress and status to date. JF - Nuclear Engineering and Design AU - Grover, S Blaine AU - Petti, David A AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, United States Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 142 EP - 148 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 271 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Energy (nuclear) KW - Advanced test reactors KW - Uranium KW - Nuclear safety KW - Irradiation KW - Fuels KW - Nuclear fuels KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1559678414?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Design+and+status+of+the+NGNP+fuel+experiment+AGR-3%2F4+irradiated+in+the+advanced+test+reactor&rft.au=Grover%2C+S+Blaine%3BPetti%2C+David+A&rft.aulast=Grover&rft.aufirst=S&rft.date=2014-05-01&rft.volume=271&rft.issue=&rft.spage=142&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2013.11.022 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 3 N1 - Last updated - 2014-10-03 DO - http://dx.doi.org/10.1016/j.nucengdes.2013.11.022 ER - TY - JOUR T1 - Electron microscopic evaluation and fission product identification of irradiated TRISO coated particles from the AGR-1 experiment: A preliminary review AN - 1559678084; 20284668 AB - Post-irradiation examination of coated particle fuel from the AGR-1 experiment is in progress at Idaho National Laboratory and Oak Ridge National Laboratory. In this paper a brief summary of results from characterization of microstructures in the coating layers of selected irradiated fuel particles with burnup of 11.3% and 19.3% FIMA will be given. The main objectives of the characterization were to study irradiation effects, fuel kernel porosity, layer debonding, layer degradation or corrosion, fission-product precipitation, grain sizes, and transport of fission products from the kernels across the TRISO layers. Characterization techniques such as scanning electron microscopy, transmission electron microscopy, energy dispersive spectroscopy, and wavelength dispersive spectroscopy were used. A new approach to microscopic quantification of fission-product precipitates is also briefly demonstrated. Microstructural characterization focused on fission-product precipitates in the SiC-IPyC interface, the SIC layer and the fuel-buffer interlayer. The results provide significant new insights into mechanisms of fission-product transport. Although Pd-rich precipitates were identified at the SiC-IPyC interlayer. no significant SiC-layer thinning was observed for the particles investigated. Characterization of these precipitates highlighted the difficulty of measuring low concentrations of Ag in precipitates with significantly higher concentrations of Pd and U. Different approaches to resolving this problem are discussed. An initial hypothesis is provided to explain fission-product precipitate compositions and locations. No SiC phase transformations were observed and no debonding of the SiC-IPyC interlayer as a result of irradiation was observed for the samples investigated. Lessons learned from the post-irradiation examination are described and future actions are recommended. JF - Nuclear Engineering and Design AU - van Rooyen, I J AU - Janneya, D E AU - Miller, B D AU - Demkowicz, P A AU - Riesterer, J AD - Idaho National Laboratory, Idaho Falls, ID 83415-6188, USA Y1 - 2014/05// PY - 2014 DA - May 2014 SP - 114 EP - 122 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 271 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); METADEX (MD); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); Corrosion Abstracts (CO); CSA / ASCE Civil Engineering Abstracts (CE) KW - Interlayers KW - Coated particles KW - Irradiation KW - Fuels KW - Debonding KW - Precipitates KW - Precipitation KW - Palladium UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1559678084?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Electron+microscopic+evaluation+and+fission+product+identification+of+irradiated+TRISO+coated+particles+from+the+AGR-1+experiment%3A+A+preliminary+review&rft.au=van+Rooyen%2C+I+J%3BJanneya%2C+D+E%3BMiller%2C+B+D%3BDemkowicz%2C+P+A%3BRiesterer%2C+J&rft.aulast=van+Rooyen&rft.aufirst=I&rft.date=2014-05-01&rft.volume=271&rft.issue=&rft.spage=114&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2013.11.019 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 12 N1 - Last updated - 2014-10-03 DO - http://dx.doi.org/10.1016/j.nucengdes.2013.11.019 ER - TY - JOUR T1 - Utilization of dual-column focused ion beam and scanning electron microscope for three dimensional characterization of high burn-up mixed oxide fuel AN - 1677961688; 20500747 AB - Developing a more fundamental understanding of fuel performance requires detailed characterization of irradiated fuel under a variety of conditions. Historically characterization was limited by instrumentation available. Great strides have been made in new characterization techniques, yet there application to irradiated fuels has been delayed due to the difficulty of working with the samples. This paper outlines the first results from the application of a dual-column focused ion beam along with energy dispersive spectroscopy and electron backscatter diffraction detectors to analyze the 3D structure of high burn-up MOX fuel. The applicability and advantages of the advanced techniques to irradiated fuel are also discussed. JF - Progress in Nuclear Energy AU - Teague, Melissa AU - Gorman, Brian AD - Fuel Performance and Design, Idaho National Laboratory, 2505 Fremont Ave., Idaho Falls, ID 83415, United States Melissa.teague@inl.gov PY - 2014 SP - 67 EP - 71 PB - Elsevier B.V., P.O. Box 800 Kidlington Oxford OX5 1DX United Kingdom VL - 72 SN - 0149-1970, 0149-1970 KW - Solid State and Superconductivity Abstracts (SO); Mechanical & Transportation Engineering Abstracts (MT); Advanced Polymers Abstracts (EP); Environmental Engineering Abstracts (EN); Composites Industry Abstracts (ED); Engineered Materials Abstracts, Ceramics (EC); CSA / ASCE Civil Engineering Abstracts (CE) KW - Focused ion beam KW - Novel characterization techniques KW - High burn-up mixed oxide fuel KW - Three dimensional KW - Scanning electron microscopy KW - Ion beams KW - Fuel consumption KW - Irradiation KW - Fuels KW - Detectors KW - Nuclear reactor components UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1677961688?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Progress+in+Nuclear+Energy&rft.atitle=Utilization+of+dual-column+focused+ion+beam+and+scanning+electron+microscope+for+three+dimensional+characterization+of+high+burn-up+mixed+oxide+fuel&rft.au=Teague%2C+Melissa%3BGorman%2C+Brian&rft.aulast=Teague&rft.aufirst=Melissa&rft.date=2014-04-01&rft.volume=72&rft.issue=&rft.spage=67&rft.isbn=&rft.btitle=&rft.title=Progress+in+Nuclear+Energy&rft.issn=01491970&rft_id=info:doi/10.1016%2Fj.pnucene.2013.08.006 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-11-01 N1 - Last updated - 2016-02-03 DO - http://dx.doi.org/10.1016/j.pnucene.2013.08.006 ER - TY - JOUR T1 - Physical constraints on geologic CO (sub 2) sequestration in low-volume basalt formations AN - 1492586325; 2014-008111 AB - Deep basalt formations within large igneous provinces have been proposed as target reservoirs for carbon capture and sequestration on the basis of favorable CO (sub 2) -water-rock reaction kinetics that suggest carbonate mineralization rates on the order of 10 (super 2) -10 (super 3) d. Although these results are encouraging, there exists much uncertainty surrounding the influence of fracture-controlled reservoir heterogeneity on commercial-scale CO (sub 2) injections in basalt formations. This work investigates the physical response of a low-volume basalt reservoir to commercial-scale CO (sub 2) injections using a Monte Carlo numerical modeling experiment such that model variability is solely a function of spatially distributed reservoir heterogeneity. Fifty equally probable reservoirs are simulated using properties inferred from the deep eastern Snake River Plain aquifer in southeast Idaho, and CO (sub 2) injections are modeled within each reservoir for 20 yr at a constant mass rate of 21.6 kg s (super -1) . Results from this work suggest that (1) formation injectivity is generally favorable, although injection pressures in excess of the fracture gradient were observed in 4% of the simulations; (2) for an extensional stress regime (as exists within the eastern Snake River Plain), shear failure is theoretically possible for optimally oriented fractures if S (sub h) < or = 0.70S (sub V) ; and (3) low-volume basalt reservoirs exhibit sufficient CO (sub 2) confinement potential over a 20 yr injection program to accommodate mineral trapping rates suggested in the literature. JF - Geological Society of America Bulletin AU - Pollyea, Ryan M AU - Fairley, Jerry P AU - Podgorney, Robert K AU - Mcling, Travis L Y1 - 2014/01/07/ PY - 2014 DA - 2014 Jan 07 PB - Geological Society of America (GSA), Boulder, CO VL - Pre-Issue Publication SN - 0016-7606, 0016-7606 KW - United States KW - Snake River Plain Aquifer KW - volcanic rocks KW - engineering properties KW - site exploration KW - igneous rocks KW - southeastern Idaho KW - carbon dioxide KW - sedimentary rocks KW - chemical reactions KW - water-rock interaction KW - pore pressure KW - basalts KW - Idaho KW - failures KW - carbon sequestration KW - numerical models KW - underground storage KW - three-dimensional models KW - Monte Carlo analysis KW - statistical analysis KW - underground installations KW - shear KW - carbonate rocks KW - tension KW - 30:Engineering geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1492586325?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Geological+Society+of+America+Bulletin&rft.atitle=Physical+constraints+on+geologic+CO+%28sub+2%29+sequestration+in+low-volume+basalt+formations&rft.au=Pollyea%2C+Ryan+M%3BFairley%2C+Jerry+P%3BPodgorney%2C+Robert+K%3BMcling%2C+Travis+L&rft.aulast=Pollyea&rft.aufirst=Ryan&rft.date=2014-01-07&rft.volume=Pre-Issue+Publication&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Geological+Society+of+America+Bulletin&rft.issn=00167606&rft_id=info:doi/10.1130%2FB30874.1 L2 - http://www.gsajournals.org/ LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data from GeoScienceWorld, Alexandria, VA, United States | Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2014-01-01 N1 - Number of references - 36 N1 - PubXState - CO N1 - Document feature - illus. incl. 3 tables N1 - Last updated - 2014-01-30 N1 - CODEN - BUGMAF N1 - SubjectsTermNotLitGenreText - basalts; carbon dioxide; carbon sequestration; carbonate rocks; chemical reactions; engineering properties; failures; Idaho; igneous rocks; Monte Carlo analysis; numerical models; pore pressure; sedimentary rocks; shear; site exploration; Snake River Plain Aquifer; southeastern Idaho; statistical analysis; tension; three-dimensional models; underground installations; underground storage; United States; volcanic rocks; water-rock interaction DO - http://dx.doi.org/10.1130/B30874.1 ER - TY - JOUR T1 - Ambient changes in tracer concentrations from a multilevel monitoring system in basalt AN - 1832656539; 692091-9 AB - Starting in 2008, a 4-year tracer study was conducted to evaluate ambient changes in groundwater concentrations of a 1,3,6-naphthalene trisulfonate tracer that was added to drill water. Samples were collected under open borehole conditions and after installing a multilevel groundwater monitoring system completed with 11 discrete monitoring zones within dense and fractured basalt and sediment layers in the eastern Snake River aquifer. The study was done in cooperation with the U.S. Department of Energy to test whether ambient fracture flow conditions were sufficient to remove the effects of injected drill water prior to sample collection. Results from thief samples indicated that the tracer was present in minor concentrations 28 days after coring, but was not present 6 months after coring or 7 days after reaming the borehole. Results from sampling the multilevel monitoring system indicated that small concentrations of the tracer remained in 5 of 10 zones during some period after installation. All concentrations were several orders of magnitude lower than the initial concentrations in the drill water. The ports that had remnant concentrations of the tracer were either located near sediment layers or were located in dense basalt, which suggests limited groundwater flow near these ports. The ports completed in well-fractured and vesicular basalt had no detectable concentrations. Abstract Copyright Published 2013. This article is a U.S. Government work and is in the public domain in the USA. JF - Ground Water Monitoring & Remediation AU - Bartholomay, Roy C AU - Twining, Brian V AU - Rose, Peter E Y1 - 2014 PY - 2014 DA - 2014 SP - 79 EP - 88 PB - Wiley-Blackwell on behalf of National Ground Water Association, Malden, MA VL - 34 IS - 1 SN - 1069-3629, 1069-3629 KW - United States KW - Snake River Plain Aquifer KW - fractured materials KW - aquifer vulnerability KW - water quality KW - volcanic rocks KW - caliper logging KW - naphthalene sulfonate KW - igneous rocks KW - well-logging KW - observation wells KW - preferential flow KW - ground water KW - Idaho National Laboratory KW - basalts KW - tracers KW - Idaho KW - concentration KW - monitoring KW - naphthalene KW - pollution KW - migration of elements KW - aquifers KW - organic compounds KW - boreholes KW - transmissivity KW - hydrocarbons KW - polycyclic aromatic hydrocarbons KW - aromatic hydrocarbons KW - 21:Hydrogeology KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1832656539?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefinprocess&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Ground+Water+Monitoring+%26+Remediation&rft.atitle=Ambient+changes+in+tracer+concentrations+from+a+multilevel+monitoring+system+in+basalt&rft.au=Bartholomay%2C+Roy+C%3BTwining%2C+Brian+V%3BRose%2C+Peter+E&rft.aulast=Bartholomay&rft.aufirst=Roy&rft.date=2014-01-01&rft.volume=34&rft.issue=1&rft.spage=79&rft.isbn=&rft.btitle=&rft.title=Ground+Water+Monitoring+%26+Remediation&rft.issn=10693629&rft_id=info:doi/10.1111%2Fgwmr.12038 L2 - http://onlinelibrary.wiley.com/journal/10.1111/(ISSN)1745-6592 LA - English DB - GeoRef N1 - Copyright - GeoRef in Process, Copyright 2017, American Geosciences Institute. After editing and indexing, this record will be added to Georef. Reference includes data from John Wiley & Sons, Chichester, United Kingdom N1 - Number of references - 26 N1 - PubXState - MA N1 - Document feature - illus. incl. 3 tables, sketch map N1 - Last updated - 2017-01-24 N1 - SubjectsTermNotLitGenreText - aquifer vulnerability; aquifers; aromatic hydrocarbons; basalts; boreholes; caliper logging; concentration; fractured materials; ground water; hydrocarbons; Idaho; Idaho National Laboratory; igneous rocks; migration of elements; monitoring; naphthalene; naphthalene sulfonate; observation wells; organic compounds; pollution; polycyclic aromatic hydrocarbons; preferential flow; Snake River Plain Aquifer; tracers; transmissivity; United States; volcanic rocks; water quality; well-logging DO - http://dx.doi.org/10.1111/gwmr.12038 ER - TY - JOUR T1 - Adaptive Dynamic Event Tree in RAVEN code AN - 1692315775; PQ0001263173 AB - RAVEN [1, 2, 3] is a software tool that is focused on performing statistical analysis of stochastic dynamic systems. RAVEN has been designed in a high modular and pluggable way in order to enable easy integration of different programming languages (i.e., C++, Python) and coupling with other applications (system codes). Among the several capabilities currently present in RAVEN, there are five different sampling strategies: Monte Carlo, Latin Hyper Cube, Grid, Adaptive and Dynamic Event Tree (DET) sampling methodologies [4]. JF - Transactions of the American Nuclear Society AU - Alfonsi, Andrea AU - Rabiti, Cristian AU - Mandelli, Diego AU - Cogliati, Joshua AU - Kinoshita, Robert AD - Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83402, United States andrea.alfonsi@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 924 EP - 926 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Modular KW - Computer programs KW - Computer simulation KW - Monte Carlo methods KW - Dynamical systems KW - Sampling KW - Tools KW - Dynamics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692315775?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Adaptive+Dynamic+Event+Tree+in+RAVEN+code&rft.au=Alfonsi%2C+Andrea%3BRabiti%2C+Cristian%3BMandelli%2C+Diego%3BCogliati%2C+Joshua%3BKinoshita%2C+Robert&rft.aulast=Alfonsi&rft.aufirst=Andrea&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=924&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - A NUMERICAL APPROACH TO SOLVE GOVERNOR EQUATIONS OF A SYSTEM CODE AN - 1692313213; PQ0001263364 AB - The design and analysis of the thermal/hydraulic systems of nuclear power plants necessitates system codes (Roth and Aydogan [1,2]) that can be used in the analysis of steady-state and transient conditions. Due to the dispersed development of system codes over many laboratories and universities, there are several system codes available for use. Many of the available codes have multiple similar versions developed for specific user needs. JF - Transactions of the American Nuclear Society AU - Fu, Zheng AU - Aydogan, Fatih AD - Center for Advanced Energy Studies (CAES), 995 University Blvd., Idaho Falls, ID 83401 fu6217@vandals.uidaho.edu Y1 - 2014 PY - 2014 DA - 2014 SP - 1663 EP - 1665 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power plants KW - Nuclear power generation KW - Design engineering KW - Laboratories KW - Governors KW - Hydraulic systems KW - Mathematical analysis KW - Dispersion UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692313213?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=A+NUMERICAL+APPROACH+TO+SOLVE+GOVERNOR+EQUATIONS+OF+A+SYSTEM+CODE&rft.au=Fu%2C+Zheng%3BAydogan%2C+Fatih&rft.aulast=Fu&rft.aufirst=Zheng&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=1663&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - Reevaluation of Room Return Corrections for Two ORCEF HEU-Metal-Cylinder Benchmark Evaluations AN - 1692313145; PQ0001263149 AB - Numerous critical experiments comprised of highly enriched uranium (HEU) metal were performed at the Oak Ridge Critical Experiments Facility (ORCEF) during the 1960s and 1970s in support of criticality safety operations at the Y-12 Plant. These experiments supported evaluation of storage, casting, and handling limits, providing data for verification of calculation, methods and cross-sections. Many of these experiments have been evaluated as benchmarks and are available in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook) [1]: [bullet] Bare Cylinders [whitecircle] HEU-MET-FAST-051 [bullet] Beryllium Reflected Cylinder and Annuli [whitecircle] HEU-MET-FAST-05 9 [whitecircle] HEU -MET-FAST-069 [bullet] Graphite Reflected Annuli [whitecircle] HEU-MET-FAST-071 [bullet] Polyethylene Reflected/Moderated Cylinders and Annuli [whitecircle] HEU-MET-FAST-076 [whitecircle] HEU-MET-FAST-081 [bullet] ORSPHERE [whitecircle] HEU-MET-FAST-100 JF - Transactions of the American Nuclear Society AU - Bess, John D AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 John.Bess@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 826 EP - 829 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Cylinders KW - Critical experiments KW - Nuclear safety KW - Annuli KW - Benchmarking KW - Bullets KW - Projectiles KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692313145?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Reevaluation+of+Room+Return+Corrections+for+Two+ORCEF+HEU-Metal-Cylinder+Benchmark+Evaluations&rft.au=Bess%2C+John+D&rft.aulast=Bess&rft.aufirst=John&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=826&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - Nuclear Fuel Cycle Options Evaluation and Screening AN - 1692312915; PQ0001262991 AB - An Evaluation, and Screening (E&S) study[1] of nuclear fuel cycle options has been conducted for the U.S. Department of Energy (DOE) Office of Nuclear Energy to provide information about the potential benefits and challenges of nuclear fuel cycle options and to identify a relatively small number of promising fuel cycle options with the potential for achieving substantial improvements compared to the current nuclear fuel cycle in the United States. The study was required to consider the complete nuclear energy system extending from mining to disposal. The set of fuel cycle options was to be as comprehensive as possible with respect to potential fuel cycle performance. JF - Transactions of the American Nuclear Society AU - Wigeland, R AU - Taiwo, T AU - Todosow, M AU - Ludewig, H AU - Halsey, W AU - Gehin, J AU - Jubin, R AU - Buelt, J AU - Stockinger, S AU - Jenni, K AU - Oakley, B AD - Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-3860, U.S.A. Y1 - 2014 PY - 2014 DA - 2014 SP - 207 EP - 210 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Screening KW - Nuclear power generation KW - Nuclear reactors KW - Energy (nuclear) KW - Fuel cycles KW - Nuclear fuels KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692312915?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Nuclear+Fuel+Cycle+Options+Evaluation+and+Screening&rft.au=Wigeland%2C+R%3BTaiwo%2C+T%3BTodosow%2C+M%3BLudewig%2C+H%3BHalsey%2C+W%3BGehin%2C+J%3BJubin%2C+R%3BBuelt%2C+J%3BStockinger%2C+S%3BJenni%2C+K%3BOakley%2C+B&rft.aulast=Wigeland&rft.aufirst=R&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=207&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - Screening and Evaluation Tool for Nuclear Fuel Cycles AN - 1692312820; PQ0001262995 AB - In late 2011, the U.S. Department of Energy, Office of Nuclear Energy (DOE-NE) chartered a study[1] on the evaluation and screening of nuclear fuel cycle options. The Study Charter specified that the evaluation and screening consider the entire fuel cycle, i.e., the complete nuclear energy system from mining to disposal including both once-through and recycle fuel cycles to identify a relatively small number of promising fuel cycle options with the potential for achieving substantial improvements compared to the current nuclear fuel cycle in the United States. The Evaluation and Screening Team (EST) decided early on in the study that they would need a tool to enable the team to perform the necessary detailed analysis of the various fuel cycles. JF - Transactions of the American Nuclear Society AU - Pincock, Layne AU - Dixon, Brent AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 layne.pincock@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 221 EP - 223 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Screening KW - Nuclear power generation KW - Nuclear reactors KW - Fuel cycles KW - Nuclear fuels KW - Nuclear reactor components KW - Tools KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692312820?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Screening+and+Evaluation+Tool+for+Nuclear+Fuel+Cycles&rft.au=Pincock%2C+Layne%3BDixon%2C+Brent&rft.aulast=Pincock&rft.aufirst=Layne&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=221&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - Implementation of an Advanced Outage Control Center AN - 1692303631; PQ0001263057 AB - Managing nuclear power plant refueling outages is a complex and difficult task due to the large number of maintenance and repair activities that are accomplished in a relatively short period of time. During a refueling outage, the Outage Control Center (OCC) is the temporary command center for outage managers and provides several critical functions for successful execution of the outage schedule. Essentially, the OCC functions to facilitate information inflow, assist outage management with processing information, and facilitate the dissemination of information to stakeholders. Currently, outage management activities primarily rely on telephone communications, face-to-face reports, and periodic briefings in the OCC. It is a difficult task to maintain current information related to outage progress and any discovered conditions. JF - Transactions of the American Nuclear Society AU - St Germain, Shawn AD - Idaho National Laboratory: P.O. Box 1625, Idaho Falls, ID, Postal 83415 shawn.stgermain@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 467 EP - 470 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Schedules KW - Nuclear power plants KW - Refueling KW - Management KW - Outages KW - Tasks KW - Information dissemination KW - Maintenance UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692303631?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Implementation+of+an+Advanced+Outage+Control+Center&rft.au=St+Germain%2C+Shawn&rft.aulast=St+Germain&rft.aufirst=Shawn&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=467&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - A Multi-Purpose Thermal Hydraulic Test Facility For Support of Advanced Reactor Technologies AN - 1692303604; PQ0001263356 AB - Effective and robust high temperature heat transfer systems are fundamental to the successful deployment of advanced nuclear reactors for both power generation and non-electric applications. Plant designs often include an intermediate heat transfer loop (IHTL) with heat exchangers at either end to deliver thermal energy to the application while providing isolation of the primary reactor coolant system. In order to address technical feasibility concerns and challenges associated with the IHTL, a new high-temperature multi-fluid, multi-loop test facility called the Advanced Reactor Technology Integral System Test (ARTIST) facility is under development at the Idaho National Laboratory (INL). The facility will include three flow loops: high-temperature helium, molten salt, and steam/water. The three loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). JF - Transactions of the American Nuclear Society AU - O'Brien, James E AU - Sabharwall, Piyush AU - Yoon, SuJong AD - Idaho National Laboratory, Idaho Falls, ID 83402 Y1 - 2014 PY - 2014 DA - 2014 SP - 1639 EP - 1642 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Artists KW - Plant design KW - Nuclear reactors KW - Heat exchangers KW - Nuclear reactor components KW - Reactor technology KW - Hydraulic tests KW - Heat transfer UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692303604?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=A+Multi-Purpose+Thermal+Hydraulic+Test+Facility+For+Support+of+Advanced+Reactor+Technologies&rft.au=O%27Brien%2C+James+E%3BSabharwall%2C+Piyush%3BYoon%2C+SuJong&rft.aulast=O%27Brien&rft.aufirst=James&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=1639&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-12-07 ER - TY - JOUR T1 - Characterization of Pentavalent and Hexavalent Americium in Nitric acid using X-ray Absorption Fine Structure Spectroscopy and First-Principles Modeling AN - 1692303218; PQ0001263048 AB - The minor actinides (MAs), neptunium (Np), americium (Am), and curium (Cm) accumulate in irradiated nuclear fuels. To reduce the potential long-term hazard of radioactive wastes, transmutation of MAs is considered to be an important option for the future nuclear fuel cycle. Mixed oxide containing, MAs (MA-MOX) are a promising candidates fuel for the transmutation in fast reactor.[11, 2] The local and electronic stmctures around the Am atom in oxide fuels would yield an immense amount of information because the valence state of Am strongly affects the oxygen potentials and thermal properties of MA-MOX fuels. X-ray absorption fine structure. JF - Transactions of the American Nuclear Society AU - Riddle, C L AU - Czerwinski, K AU - Kim, E AU - Paviet, P D AU - Weck, P F AU - Poineau, F AU - Conradson, S AD - Idaho National Laboratory, Idaho Falls, ID 83415 Y1 - 2014 PY - 2014 DA - 2014 SP - 434 EP - 437 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - X-rays KW - Transmutation KW - Fuels KW - Nuclear fuels KW - Fine structure KW - Electronics KW - Americium KW - Thermal properties UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692303218?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Characterization+of+Pentavalent+and+Hexavalent+Americium+in+Nitric+acid+using+X-ray+Absorption+Fine+Structure+Spectroscopy+and+First-Principles+Modeling&rft.au=Riddle%2C+C+L%3BCzerwinski%2C+K%3BKim%2C+E%3BPaviet%2C+P+D%3BWeck%2C+P+F%3BPoineau%2C+F%3BConradson%2C+S&rft.aulast=Riddle&rft.aufirst=C&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=434&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - Extending RISMC Capabilities for Real-Time Diagnostics and Prognostics AN - 1692303162; PQ0001263183 AB - Quick and effective accident management is essential in any industry in order to limit and contain possible threats to both people and environment/assets. This ability is in particular relevant in the nuclear industry where accidents may have major impacts from an economic, health and societal point of view. As an example, the Fukushima Dai-ichi nuclear power plant accident highlighted the importance of the ability of plant operators and plant staff to react quickly and effectively in accident conditions. This particular event showed the importance of being able to: [bullet] Determine/estimate the actual status of the plant (i.e., diagnosis) when the monitoring system is corrupted or partially unavailable, and, [bullet] Forecast its future evolution (i.e., prognosis). JF - Transactions of the American Nuclear Society AU - Mandelli, Diego AU - Smith, Curtis AD - Idaho National Laboratory, 2525 North Fremont Street, Idaho Falls (ID) diego.mandelli@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 956 EP - 960 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Accidents KW - Accident conditions KW - Economics KW - Power plants KW - Accidental impacts KW - Diagnostic systems KW - Bullets KW - Projectiles UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692303162?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Extending+RISMC+Capabilities+for+Real-Time+Diagnostics+and+Prognostics&rft.au=Mandelli%2C+Diego%3BSmith%2C+Curtis&rft.aulast=Mandelli&rft.aufirst=Diego&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=956&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - Benchmark Specifications and Results for alpha and [Lambda] in a HEU Metal System Using ORSphere AN - 1692302946; PQ0001263150 AB - In the early 1970s Dr. John T. Mihalczo (team leader), J. J. Lynn, and J. R. Taylor performed experiments at the Oak Ridge Critical Experiments Facility (ORCEF) with highly enriched uranium (HEU) metal (called Oak Ridge Alloy or ORALLOY) to recreate GODIVA I results with greater accuracy than those performed at Los Alamos National Laboratory in the 1950s. The purpose of the Oak Ridge ORALLOY Sphere (ORSphere) experiments was to estimate the unreflected and unmoderated critical mass of an idealized sphere of uranium metal corrected to a density, purity, and enrichment such that it could be compared with the GODIVA I experiments [1]. Part of the experimental series was the measurement of various kinetic parameters including the prompt neutron decay constant, alpha , and the delayed neutron fraction, beta sub(eff). Although not presented by the experimenter the mean neutron generation time, [Lambda], can also be derived using the benchmark alpha and beta sub(eff) values. All three of these kinetic parameters measurements have been evaluated and found to be acceptable and are discussed in full detail in the International Handbook of Evaluated Reactor Physics Benchmark Experiments [2]. JF - Transactions of the American Nuclear Society AU - Marshall, Margaret A AU - Bess, John D AD - Idaho National Laboratory, 2525 N. Fremont, Idaho Falls, ID 83415-3860 Y1 - 2014 PY - 2014 DA - 2014 SP - 830 EP - 833 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Uranium KW - Density KW - Constants KW - Benchmarking KW - Enrichment KW - Research facilities KW - Reactor physics KW - Neutron decay UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692302946?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Benchmark+Specifications+and+Results+for+alpha+and+%5BLambda%5D+in+a+HEU+Metal+System+Using+ORSphere&rft.au=Marshall%2C+Margaret+A%3BBess%2C+John+D&rft.aulast=Marshall&rft.aufirst=Margaret&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=830&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-12-07 ER - TY - JOUR T1 - Thermal Predictions of the Cooling of Waste Glass Canisters AN - 1692300395; PQ0001263324 AB - The results presented in this paper provide a bounding estimate for the amount of heat rejected from the waste glass containers/canisters during cooling. Four different waste glass formulations were evaluated - two HLW compositions and two LAW compositions with different thermophysical properties. The thermal properties and heat generation rate used in the analysis are conservative and were chosen to match those used in the HVAC design by the WTP contractor. The two HLW formulations exhibit similar temperature distributions within the glass after 40 hrs. of cooling, as do the two LAW formulations. At initial times after pouring, thermal radiation is the dominant mode of heat transfer. At longer times, the contribution from thermal radiation to heat loss from the container/canister becomes nearly comparable to that from free convection. Thermal gradients within the glass canister are less than several degrees. Future work includes simulating the heat transfer to the surroundings resulting from discrete pours of molten glass into the containers/canisters. This will provide a more realistic estimate of the heat rejected from the containers/canisters as a function of time during cooling. JF - Transactions of the American Nuclear Society AU - Guillen, Donna Post AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 Donna.Guillen@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 1511 EP - 1514 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Estimates KW - Containers KW - Canisters KW - Formulations KW - Wastes KW - Law KW - Glass KW - Cooling UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692300395?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Thermal+Predictions+of+the+Cooling+of+Waste+Glass+Canisters&rft.au=Guillen%2C+Donna+Post&rft.aulast=Guillen&rft.aufirst=Donna&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=1511&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-12-07 ER - TY - JOUR T1 - On High Order Numerical Schemes for 1-D Fluid Model AN - 1692300386; PQ0001263358 AB - Operator-splitting type of algorithms, e.g., the classic Implicit Continuous-Fluid Eulerian (ICE) method [1, 2], were widely used to solve the one-dimensional single-phase and two-phase flow equations in the nuclear thermal hydraulics field. It is well known that the ICE method introduces first-order time integration errors. Mousseau gave excellent analyses on the operator-splitting time integration errors in several of his works [3, 4, 5]. For spatial discretization, first-order staggered grid upwind method was generally used in the existing codes, which is robust and 'regulates' the ill-posedness of the commonly used two fluid six equations two-phase flow model. However, it introduces numerical diffusion, which is not desirable for certain scenarios such as long lasting transients. JF - Transactions of the American Nuclear Society AU - Zou, Ling AU - Zhao, Haihua AU - Zhang, Hongbin AD - Idaho National Laboratory, 2525 N Freemont Ave., Idaho Falls, ID 83415 Y1 - 2014 PY - 2014 DA - 2014 SP - 1647 EP - 1650 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Computational fluid dynamics KW - Mathematical models KW - Discretization KW - Transaction processing KW - Fluids KW - Time integration KW - Fluid flow KW - Mathematical analysis UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692300386?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=On+High+Order+Numerical+Schemes+for+1-D+Fluid+Model&rft.au=Zou%2C+Ling%3BZhao%2C+Haihua%3BZhang%2C+Hongbin&rft.aulast=Zou&rft.aufirst=Ling&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=1647&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - Transient Experiment Design for Accident Tolerance Fuels AN - 1692300304; PQ0001263096 AB - Development of Accident Tolerant Fuels (ATF) will require nuclear transient testing. Use of the Transient Reactor Test facility (TREAT) at the Idaho National Laboratory is planned for this testing. TREAT has been in operational standby for several years. Hence, recovery of legacy knowledge from precedent transient experiment campaigns has been leveraged for modern design work. These efforts are focused on establishing the appropriate test environment for simulation of nuclear transients with ATF specimens. JF - Transactions of the American Nuclear Society AU - Woolstenhulme, N E AU - Wachs, D M AU - Beasley, A A AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 - USA Y1 - 2014 PY - 2014 DA - 2014 SP - 604 EP - 606 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Accidents KW - Recovery KW - Legacy KW - Fuels KW - Experiment design KW - Transient Reactor Test Facility KW - Simulation KW - Tolerances UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692300304?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Transient+Experiment+Design+for+Accident+Tolerance+Fuels&rft.au=Woolstenhulme%2C+N+E%3BWachs%2C+D+M%3BBeasley%2C+A+A&rft.aulast=Woolstenhulme&rft.aufirst=N&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=604&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - MATCHED-INDEX-OF-REFRACTION FLOW FACILITY FOR FUNDAMENTAL AND APPLIED RESEARCH AN - 1692300274; PQ0001263354 AB - Significant challenges face reactor designers with regard to thermal hydraulic design and associated modeling for advanced reactor concepts. Computational fluid dynamics (CFD) codes solve only a piece of the core. There is a need for a whole core dynamics system code with local resolution to investigate and understand flow behavior with all the relevant physics and thermomechanics. The matched index of refraction (MIR) flow facility at Idaho National Laboratory (INL) has a unique capability to contribute to the development of validated CFD codes through the use of state-of-the-art optical measurement techniques, such as Laser Doppler Velocimetry (LDV) and Particle Image Velocimetry (PIV). PIV is a non-intrusive velocity measurement technique that tracks flow by imaging the movement of small tracer particles within a fluid. JF - Transactions of the American Nuclear Society AU - Sabharwall, Piyush AU - Stoots, Carl AU - McEligot, Donald M AU - Skifton, Richard AU - McIlroy, Hugh M AD - Idaho National Laboratory, Idaho Falls, ID 83402 Y1 - 2014 PY - 2014 DA - 2014 SP - 1633 EP - 1636 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Computational fluid dynamics KW - Nuclear reactors KW - Mathematical models KW - Dynamical systems KW - Nuclear reactor components KW - Fluid flow KW - Dynamics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1692300274?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=MATCHED-INDEX-OF-REFRACTION+FLOW+FACILITY+FOR+FUNDAMENTAL+AND+APPLIED+RESEARCH&rft.au=Sabharwall%2C+Piyush%3BStoots%2C+Carl%3BMcEligot%2C+Donald+M%3BSkifton%2C+Richard%3BMcIlroy%2C+Hugh+M&rft.aulast=Sabharwall&rft.aufirst=Piyush&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=1633&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-07-01 N1 - Last updated - 2015-07-01 ER - TY - JOUR T1 - Comparison of a Traditional Probabilistic Risk Assessment Approach with Advanced Safety Analysis AN - 1673398304; PQ0001263055 AB - As part of the Light Water Sustainability Program (LWRS) [1], the purpose of the Risk Informed Safety Margin Characterization (RISMC) [2] Pathway research and development (R&D) is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain the safety of current NPPs. JF - Transactions of the American Nuclear Society AU - Mandelli, Diego AU - Ma, Zhegang AU - Smith, Curtis AD - Idaho National Laboratory, 2525 North Fremont Street, Idaho Falls (ID), diego.mandelli@iln.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 459 EP - 462 PB - American Nuclear Society, Inc. VL - 111 SN - 0003-018X, 0003-018X KW - Sustainability Science Abstracts; Risk Abstracts; Health & Safety Science Abstracts KW - Risk assessment KW - Risk management KW - Safety KW - Economics KW - Sustainability KW - Research programs KW - H 8000:Radiation Safety/Electrical Safety KW - M3 1010:Issues in Sustainable Development KW - R2 23070:Economics, organization UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1673398304?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Comparison+of+a+Traditional+Probabilistic+Risk+Assessment+Approach+with+Advanced+Safety+Analysis&rft.au=Mandelli%2C+Diego%3BMa%2C+Zhegang%3BSmith%2C+Curtis&rft.aulast=Mandelli&rft.aufirst=Diego&rft.date=2014-01-01&rft.volume=111&rft.issue=&rft.spage=459&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2015-04-01 N1 - Last updated - 2015-05-27 N1 - SubjectsTermNotLitGenreText - Risk assessment; Risk management; Economics; Safety; Research programs; Sustainability ER - TY - JOUR T1 - Preliminary Post Irradiation Examination of AFC-3A and AFC-3B AN - 1671604219; 20432558 AB - One goal of the Fuel Cycle Research & Development (FCRD) program is to develop and demonstrate the technologies needed to transmute long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products [1]. As part of this development, candidate nuclear fuels and possible transuranic transmutation compositions undergo irradiation testing in a prototypic fast reactor spectrum. Post irradiation examination of these materials provides data on the in reactor fuel performance and input into future fuel design choices. A summary of the current state of the Advanced Fuels Campaign (AFC) can be found in Reference 2. JF - Transactions of the American Nuclear Society AU - Harp, Jason M AU - Chichester, Heather JM AD - Idaho National Laboratory, PO Box 1625, MS 6188, Idaho Falls, ID 83415-6188 jason.harp@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 777 EP - 780 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Isotopes KW - Irradiation KW - Fuels KW - Nuclear fuels KW - Spent nuclear fuels KW - Nuclear reactor components KW - Nuclear engineering KW - Actinides UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1671604219?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Preliminary+Post+Irradiation+Examination+of+AFC-3A+and+AFC-3B&rft.au=Harp%2C+Jason+M%3BChichester%2C+Heather+JM&rft.aulast=Harp&rft.aufirst=Jason&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=777&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2015-04-09 ER - TY - JOUR T1 - Fluorinated phosphazene co-solvents for improved thermal and safety performance in lithium-ion battery electrolytes AN - 1671526408; 20448915 AB - The safety of lithium-ion batteries is coming under increased scrutiny as they are being adopted for large format applications especially in the vehicle transportation industry and for grid-scale energy storage. The primary short-comings of lithium-ion batteries are the flammability of the liquid electrolyte and sensitivity to high voltage and elevated temperatures. We have synthesized a series of non-flammable fluorinated phosphazene liquids and blended them with conventional carbonate solvents. While the use of these phosphazenes as standalone electrolytes is highly desirable, they simply do not satisfy all of the many requirements that must be met such as high LiPF sub(6) solubility and low viscosity, thus we have used them as additives and co-solvents in blends with typical carbonates. The physical and electro-chemical properties of the electrolyte blends were characterized, and then the blends were used to build 2032-type coin cells. We have evaluated the performance of the electrolytes by determining the physical properties, thermal stability, electrochemical window, cell cycling data, and the ability to form solid electrolyte interphase (SEI) films. This paper presents our most recent results on a new series of fluorinated cyclic phosphazene trimers, the FM series, which has exhibited numerous beneficial effects on battery performance, lifetimes, and safety aspects. JF - Journal of Power Sources AU - Rollins, Harry W AU - Harrup, Mason K AU - Dufek, Eric J AU - Jamison, David K AU - Sazhin, Sergiy V AU - Gering, Kevin L AU - Daubaras, Dayna L AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, USA harry.rollins@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 66 EP - 74 PB - Elesevier Science B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 263 SN - 0378-7753, 0378-7753 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Phosphazene KW - Electrolyte KW - Lithium-ion battery KW - Stability KW - Non-flammable KW - Blends KW - Polymer blends KW - Electrolytes KW - Electrolytic cells KW - Lithium batteries KW - Fluorination KW - Liquids UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1671526408?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Power+Sources&rft.atitle=Fluorinated+phosphazene+co-solvents+for+improved+thermal+and+safety+performance+in+lithium-ion+battery+electrolytes&rft.au=Rollins%2C+Harry+W%3BHarrup%2C+Mason+K%3BDufek%2C+Eric+J%3BJamison%2C+David+K%3BSazhin%2C+Sergiy+V%3BGering%2C+Kevin+L%3BDaubaras%2C+Dayna+L&rft.aulast=Rollins&rft.aufirst=Harry&rft.date=2014-01-01&rft.volume=263&rft.issue=&rft.spage=66&rft.isbn=&rft.btitle=&rft.title=Journal+of+Power+Sources&rft.issn=03787753&rft_id=info:doi/10.1016%2Fj.jpowsour.2014.04.015 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2015-05-04 DO - http://dx.doi.org/10.1016/j.jpowsour.2014.04.015 ER - TY - JOUR T1 - Numerical modeling of the last glacial maximum Yellowstone ice cap AN - 1656039891; 2015-015864 AB - We use two 2-D numerical glacier models with complementary strengths to address several pressing questions related to the LGM Yellowstone Ice Cap. First, we assess the potential range of paleoclimate states that promote the formation of the ice cap using an implicit 2-D ice flow and energy balance model (Plummer and Phillips, 2003). The detailed surface mass balance scheme also allows us to determine the likely locations of initial glacier growth and subsequent coalescence (e.g. the Beartooth plateau, Absaroka mountains). Second, we explore explanations for spatial asynchronies in the Yellowstone Ice Cap LGM moraine ages. The maximum terminal moraine ages from the western portion of the ice cap are one to four thousand years younger than ages on the east side of the ice cap (Licciardi and Pierce, 2008). As a potential explanation for this discrepency, we assess the importance of orographic precipitation in promoting the westward growth of the ice cap through time (e.g., Pierce, 1979) and the potential for a thickening ice cap to reduce leeside accumulation leading to the contraction of eastward-flowing outlet glaciers. For this exploration, we use an efficient semi-implicit 2-D ice-flow model with a surface mass balance scheme that allows inclusion of a simple algorithm for orographically-forced precipitation (e.g., Roe, 2005). Finally, we couple the semi-implicit 2-D ice-flow model to a fully implicit solution for flexural isostatic response to the evolving ice load, and test the sensitivity of the ice cap to a generous range of plausible solid Earth rheologies. This provides initial estimates of the effect of flexural depression on ice dynamics, potential locations of proglacial lakes, and the location and magnitude of the forebulge. This modeling effort was inspired by the instruction of Bill Locke at Montana State University and the work of Ken Pierce and Joe Licciardi, whose modeling and cosmogenic radionuclide dating efforts inform and constrain our research. JF - Abstracts with Programs - Geological Society of America AU - Anderson, Leif S AU - Plummer, Mitchell AU - Wickert, Andrew D AU - Colgan, William AU - Anderson, Robert S AU - Anonymous Y1 - 2014 PY - 2014 DA - 2014 SP - 81 PB - Geological Society of America (GSA), Boulder, CO VL - 46 IS - 5 SN - 0016-7592, 0016-7592 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1656039891?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Numerical+modeling+of+the+last+glacial+maximum+Yellowstone+ice+cap&rft.au=Anderson%2C+Leif+S%3BPlummer%2C+Mitchell%3BWickert%2C+Andrew+D%3BColgan%2C+William%3BAnderson%2C+Robert+S%3BAnonymous&rft.aulast=Anderson&rft.aufirst=Leif&rft.date=2014-01-01&rft.volume=46&rft.issue=5&rft.spage=81&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Geological Society of America, Rocky Mountain Section, 66th annual meeting; Geological Society of America, Cordilleran Section, 110th annual meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2015-01-01 N1 - PubXState - CO N1 - Last updated - 2015-02-19 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Molecular Dynamics Calculations of Grain Boundary Mobility in UO sub(2) AN - 1567085503; 20432551 AB - Grain boundaries (GBs) play a critical role in microstructure evolution in crystalline solids and they migrate under various driving forces.[1] When the driving forces are small, the velocity v at which GBs migrate is proportional to driving force P by v=MP, with M being the mobility which may or may not depend on the type of driving force. In nuclear fuels which are primarily made of UO sub(2) currently, GB motion has significant impact on fuel performance by affecting the thermal conductivity, fission gas release and defect accumulation induced by radiation damage. Obtaining GB mobility is critical for predictive modeling of fuel performance in reactors. JF - Transactions of the American Nuclear Society AU - Zhang, Yongfeng AU - Bai, Xianming AU - Tonks, Michael R AD - Idaho National Lab., 2525 N Fremont Ave, Idaho Falls, ID, 83401 Yongfeng.zhang@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 751 EP - 752 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); Computer and Information Systems Abstracts (CI); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Mathematical models KW - Grain boundaries KW - Thermal conductivity KW - Fuels KW - Molecular dynamics KW - Nuclear reactor components KW - Crystal defects UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567085503?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Molecular+Dynamics+Calculations+of+Grain+Boundary+Mobility+in+UO+sub%282%29&rft.au=Zhang%2C+Yongfeng%3BBai%2C+Xianming%3BTonks%2C+Michael+R&rft.aulast=Zhang&rft.aufirst=Yongfeng&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=751&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - The Impact of Water Saturation in Graphite Reflector Blocks on NRAD Benchmark Simulation AN - 1567085048; 20432522 AB - The neutron radiography (NRAD) reactor (Figure 1) is a 250 kW TRIGA(R)-(Training, Research, Isotope-Production, General Atomics)-conversion-type reactor located at the Idaho National Laboratory (INL). It is equipped with two beam tubes with separate radiography stations for the performance of neutron radiography irradiation on small test components. It is primarily used for analysis of both irradiated and unirradiated fuels and materials. Typical applications include examining internal features of fuel elements and assemblies for fuel pellet separations, fuel central-void formation, pellet cracking, evidence of fuel melting, and material integrity under normal and extreme conditions. JF - Transactions of the American Nuclear Society AU - Bess, John D AU - Smolinski, Andrew T AD - Idaho National Laboratory, PO Box 1625, MS 3855, Idaho Falls, ID 83415 Y1 - 2014 PY - 2014 DA - 2014 SP - 638 EP - 640 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Advanced Polymers Abstracts (EP); Environmental Engineering Abstracts (EN); Composites Industry Abstracts (ED); Engineered Materials Abstracts, Ceramics (EC); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Irradiation KW - Fuels KW - Neutron radiography KW - Nuclear reactor components KW - Pellets KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567085048?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=The+Impact+of+Water+Saturation+in+Graphite+Reflector+Blocks+on+NRAD+Benchmark+Simulation&rft.au=Bess%2C+John+D%3BSmolinski%2C+Andrew+T&rft.aulast=Bess&rft.aufirst=John&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=638&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Status Update on U.S. DOE Accident Tolerant Fuel Development AN - 1567078992; 20432543 AB - The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. Prior to the unfortunate events at the Fukushima Nuclear Power Plant in Japan in March 2011, the emphasis for these activities was on improving nuclear fuel performance in terms of increased bumup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. JF - Transactions of the American Nuclear Society AU - Bragg-Sitton, Shannon M AU - Carmack, Jon AU - Goldner, Frank J AU - Hayes, Steven L AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 shannon.bragg-sitton@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 727 EP - 730 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Energy (nuclear) KW - Research and development KW - Fuels KW - Density KW - Offices KW - Nuclear reactor components KW - Light water reactors UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567078992?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Status+Update+on+U.S.+DOE+Accident+Tolerant+Fuel+Development&rft.au=Bragg-Sitton%2C+Shannon+M%3BCarmack%2C+Jon%3BGoldner%2C+Frank+J%3BHayes%2C+Steven+L&rft.aulast=Bragg-Sitton&rft.aufirst=Shannon&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=727&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Microstructural Evolution in a UZr Alloy Irradiated at Low Fluences AN - 1567070809; 20432562 AB - Metallic alloys are candidates for nuclear transmutation fuels that can be utilized to bum long-lived minor actinides and fission products in fast spectrum reactors. Uranium-zirconium (U-Zr) alloys represent one of the types of fuels that are under consideration for use within these reactors. Metallic fuels have been investigated for over five decades in numerous reactors [1, 2], However, these previous investigations tended to focus on fuel performance phenomena, such as the maximum burn-up. This study is meant to focus on the early stages of fuel performance through the understanding of microstructural evolution of nuclear fuel subjected to low neutron fluences. Understanding the fuel behavior at low fluences is key to parameterizing and validating the microstructural nuclear fuel simulations. JF - Transactions of the American Nuclear Society AU - Okuniewski, Maria A AU - Bell, Gary AU - McDuffee, Joel AU - Ellis, Ron AU - Snead, Lance AU - Sitterson, Bob AU - Voit, Stewart AU - Ecker, Lynne AU - Miller, Brandon AU - Hayes, Steven AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188 Y1 - 2014 PY - 2014 DA - 2014 SP - 788 EP - 789 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); METADEX (MD); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Fuels KW - Nuclear fuels KW - Nuclear reactor components KW - Microstructure KW - Evolution KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567070809?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Microstructural+Evolution+in+a+UZr+Alloy+Irradiated+at+Low+Fluences&rft.au=Okuniewski%2C+Maria+A%3BBell%2C+Gary%3BMcDuffee%2C+Joel%3BEllis%2C+Ron%3BSnead%2C+Lance%3BSitterson%2C+Bob%3BVoit%2C+Stewart%3BEcker%2C+Lynne%3BMiller%2C+Brandon%3BHayes%2C+Steven&rft.aulast=Okuniewski&rft.aufirst=Maria&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=788&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Characterization of Alloy 617 Properties to Support VHTR Intermediate Heat Exchanger Design AN - 1567069899; 20432564 AB - The Very High Temperature Reactor (VHTR) is being developed as a nuclear system with helium as the primary coolant to transport thermal energy for the cogeneration of hydrogen, process heat and electricity. Conceptual design requires an outlet temperature of greater than 850[degrees]C to provide for the efficient generation of hydrogen, with a desired maximum outlet temperature of 950[degrees]C. A critical component in the VHTR system for extracting thermal energy at these temperatures is the Intermediate Heat Exchanger (IHX), which will be required to operate at reactor outlet temperatures of up to 950[degrees]C. The combination of very high temperature operation and long duration of service dictates the need for structural materials with good thermal stability as well as high temperature creep and oxidation resistance. Based on these material requirements, the nickel base alloy UNS N06617, Alloy 617, is the leading IHX candidate alloy [1]. JF - Transactions of the American Nuclear Society AU - Carroll, L J AU - Sham, T L AU - Wright, J K AU - Wright, R N AD - Idaho National Laboratory: 1955 Fremont P.O. Box 1625, Idaho Falls, ID, 83415 laura.carroll@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 796 EP - 799 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); METADEX (MD); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nickel base alloys KW - Superalloys KW - Alloy 617 KW - Nuclear power generation KW - Thermal energy KW - Outlets KW - Nuclear reactors KW - Design engineering KW - Heat exchangers KW - Nuclear reactor components KW - Oxidation resistance UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567069899?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Characterization+of+Alloy+617+Properties+to+Support+VHTR+Intermediate+Heat+Exchanger+Design&rft.au=Carroll%2C+L+J%3BSham%2C+T+L%3BWright%2C+J+K%3BWright%2C+R+N&rft.aulast=Carroll&rft.aufirst=L&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=796&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Performance evaluation of the AGR-1 TRISO fuel: Preliminary Post-Irradiation Examination Results Summary AN - 1567063623; 20432555 AB - The first in a series of tristructural isotropic (TRISO) coated particle fuel irradiation experiments, initiated as part of the US Advanced Gas Reactor (AGR) fuel development and qualification effort, was completed in November 2009 after 620 effective full power days in the Advanced Test Reactor at the Idaho National Laboratory (INL). The AGR-1 experiment contained 72 fuel compacts, each ~12.4 mm in diameter and ~25 mm long and containing approximately 4,100 TRISO particles with kernels comprised of a heterogeneous mixture of uranium oxide and uranium carbide (termed UCO)[1]. The irradiation experiment was a major success, achieving a peak compact-average burnup of 19.5% FIMA with zero particle failures detected during the irradiation based on monitoring of fission gas release from the fuel.[2] JF - Transactions of the American Nuclear Society AU - Demkowicz, Paul A AU - Hunn, John D AU - Petti, David A AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415-6188 paul.demkowicz@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 763 EP - 766 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Irradiation KW - Fuels KW - Nuclear fuels KW - Kernels KW - Monitoring KW - Gas reactors KW - Uranium oxides KW - Uranium carbide UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567063623?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Performance+evaluation+of+the+AGR-1+TRISO+fuel%3A+Preliminary+Post-Irradiation+Examination+Results+Summary&rft.au=Demkowicz%2C+Paul+A%3BHunn%2C+John+D%3BPetti%2C+David+A&rft.aulast=Demkowicz&rft.aufirst=Paul&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=763&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Obtaining Elastic Constants using Phase Field Crystal Modeling AN - 1567062695; 20432609 AB - The phase field crystal (PFC) model has attracted intensive interests among the material science community to explore materials science issues at diffusive time scales with atomistic resolution. Such information, while being coupled with continuum scale modeling methods, is invaluable to produce more accurate models for the structural evolution in fuels and materials in nuclear reactors. However, such coupling is challenging, as it requires simulations to pass information back and forth while using different time and spatial scales with different methods. In addition, PFC models capable of reproducing realistic material properties are currently highly desired in the community but yet to be realized. JF - Transactions of the American Nuclear Society AU - Butterfield, Aaron AU - Chan, Victor AU - Ghosh, Susanta AU - Thornton, Katsuyo AU - Tonks, Michael AU - Zhang, Yongfeng AD - Idaho National Lab., 2525 N Fremont Ave, Idaho Falls, ID, 83401 aaron.butterfield@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 925 EP - 926 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Production methods KW - Joining KW - Communities KW - Materials science KW - Transaction processing KW - Diffusion KW - Crystals KW - Evolution UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567062695?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Obtaining+Elastic+Constants+using+Phase+Field+Crystal+Modeling&rft.au=Butterfield%2C+Aaron%3BChan%2C+Victor%3BGhosh%2C+Susanta%3BThornton%2C+Katsuyo%3BTonks%2C+Michael%3BZhang%2C+Yongfeng&rft.aulast=Butterfield&rft.aufirst=Aaron&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=925&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Fuels Performance Modeling Based on Microstructure Rather Than Burnup AN - 1567062514; 20432548 AB - The materials models in fuels performance codes have typically been empirical or semi-empirical fits to experimental data from light water reactor (LWR) fuel. These models are correlated to temperature and bumup, where the bumup is used to characterize the history of the fuel. However, bumup is an imprecise measure of the fuel history, as it is not unique; fuels at the same bumup can have different microstructures, and therefore different properties, depending on irradiation conditions. JF - Transactions of the American Nuclear Society AU - Tonks, Michael AU - Zhang, Yongfeng AU - Bai, Xianming AU - Gaston, Derek AU - Williamson, Richard AU - Hayes, Steven AD - Fuels Modeling and Simulation, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 michael.tonks@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 741 EP - 742 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Irradiation KW - Fuels KW - Light water reactors KW - Correlation KW - Empirical analysis KW - Microstructure UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567062514?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Fuels+Performance+Modeling+Based+on+Microstructure+Rather+Than+Burnup&rft.au=Tonks%2C+Michael%3BZhang%2C+Yongfeng%3BBai%2C+Xianming%3BGaston%2C+Derek%3BWilliamson%2C+Richard%3BHayes%2C+Steven&rft.aulast=Tonks&rft.aufirst=Michael&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=741&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Results from the DOE Advanced Gas Reactor Fuel Development and Qualification Program AN - 1567062254; 20432554 AB - Modular high temperature gas-cooled reactor (HTGR) designs were developed to provide natural safety, which prevents core damage under all design basis accidents and presently envisioned severe accidents. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude and allows potential elimination of the need for evacuation and sheltering beyond a small exclusion area. This level, however, is predicated on exceptionally high quality fuel fabrication quality and performance under normal operation and accident conditions. Germany produced and demonstrated high-quality fuel for their pebble bed HTGRs in the 1980s, but no U.S. manufactured fuel had exhibited equivalent performance prior to the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The design goal of the modular HTGRs is to allow elimination of an exclusion zone and an emergency planning zone outside the plant boundary fence, typically interpreted as being about 400 meters from the reactor. To achieve this, the reactor design concepts require a level of fuel integrity that is better than that claimed for all prior U.S.-manufactured tristructural isotropic (TRISO) fuel, by a few orders of magnitude and about a factor of three better than qualified for German TRISO fuel in the 1980's. JF - Transactions of the American Nuclear Society AU - Petti, David AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415 david.petti@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 759 EP - 762 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Modular KW - Fission products KW - Nuclear power generation KW - Accidents KW - Nuclear reactors KW - Fuels KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567062254?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Results+from+the+DOE+Advanced+Gas+Reactor+Fuel+Development+and+Qualification+Program&rft.au=Petti%2C+David&rft.aulast=Petti&rft.aufirst=David&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=759&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Confidence in LWR Instrumentation Data during a Severe Accident AN - 1567059255; 20432469 AB - The accidents at the Three Mile Island Unit 2 (TMI-2) and Fukushima Daiichi Units 1, 2, and 3 nuclear power plants demonstrate the importance of accurate, relevant, and timely information on the reactor status during a severe accident. These events also highlight the importance of having confidence in instrumentation data for critical parameters when making accident management and mitigation decisions in an environment where operators are overwhelmed with superfluous and sometimes conflicting data. While progress in these areas has been made since TMI-2, the events at Fukushima indicate that there is still a need for further improvement. JF - Transactions of the American Nuclear Society AU - Rempe, Joy AU - Knudson, Darrell AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3531 joy.rempe@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 441 EP - 444 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Confidence KW - Nuclear power plants KW - Nuclear power generation KW - Accidents KW - Islands KW - Instrumentation KW - Nuclear accidents KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567059255?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Confidence+in+LWR+Instrumentation+Data+during+a+Severe+Accident&rft.au=Rempe%2C+Joy%3BKnudson%2C+Darrell&rft.aulast=Rempe&rft.aufirst=Joy&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=441&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Event Tree Success Branch Modeling Approaches in SAPHIRE/SPAR AN - 1567056192; 20432450 AB - Standardized Plant Analysis Risk (SPAR) models are a set of linked fault tree/event tree PRA models that have been used by the Nuclear Regulatory Commission (NRC) to evaluate the risk of operations at U.S. nuclear power plants since 1990s. The models use the Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) code developed by the NRC and Idaho National Laboratory (INL). SAPHIRE, currently Version 8, is a powerful software with advanced features to perform separated or integrated Level 1, Level 2, internal events, external events, at-power, and low power shutdown PRA [1], One of its features is the availability of three different approaches to model the success branch of a top event in event tree: delete term, complement of system logic, and developed event. Improper choosing of the approach and modeling success branch might yield unexpected and incorrect results. This paper will discuss the two most often used success branch modeling approaches, delete term and developed event, and provide recommendations for using proper approaches in different models. A potential SAPHIRE code enhancement is also presented to efficiently address the impact brought by the developed event approach. JF - Transactions of the American Nuclear Society AU - Ma, Zhegang AU - Schroeder, John AD - Idaho National Laboratory, P.O. Box 1625, MS 3850, Idaho Falls, ID 83415 zhegang.ma@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 349 EP - 351 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power plants KW - Nuclear power generation KW - Computer programs KW - Regulatory agencies KW - Availability KW - Complement KW - Event tree analysis KW - Shutdowns UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567056192?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Event+Tree+Success+Branch+Modeling+Approaches+in+SAPHIRE%2FSPAR&rft.au=Ma%2C+Zhegang%3BSchroeder%2C+John&rft.aulast=Ma&rft.aufirst=Zhegang&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=349&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-10-03 ER - TY - JOUR T1 - Uranium Silicide Fabrication for use in LWR Accident Tolerant Fuel AN - 1566858479; 20432630 AB - Enhancement of the safety and performance of Light Water Reactors (LWR) remains an active research area. Several accident tolerant fuel concepts are currently being evaluated by industry lead teams in collaboration with national laboratories and universities. This work is part of one such collaboration. The primary uranium compound used in nuclear fuel worldwide is uranium dioxide (UO sub(2)) however alternative uranium compounds, such as uranium silicides, exists whose properties make them a potential alternative to UO sub(2) in nuclear fuel. In this work, samples of high density (>94% theoretical density) uranium silicide (U sub(3)Si sub(2)) have been fabricated by powder metallurgy techniques. The developed fabrication techniques will be used to create samples for irradiation testing in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR). Post irradiation examination of these samples will provide important information on the performance of U sub(3)Si sub(2) under typical LWR conditions. JF - Transactions of the American Nuclear Society AU - Harp, Jason M AU - Lessing, Paul A AU - Hoggan, Rita E AD - Idaho National Laboratory, PO Box 1625, MS 6188, Idaho Falls, ID 83415-6188, jason.harp@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 990 EP - 993 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts KW - Uranium compounds KW - USA, Idaho KW - Accidents KW - Nuclear reactors KW - Uranium KW - Fuels KW - Irradiation KW - Nuclear fuels KW - Occupational safety KW - Safety KW - Metallurgy KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1566858479?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Uranium+Silicide+Fabrication+for+use+in+LWR+Accident+Tolerant+Fuel&rft.au=Harp%2C+Jason+M%3BLessing%2C+Paul+A%3BHoggan%2C+Rita+E&rft.aulast=Harp&rft.aufirst=Jason&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=990&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Uranium compounds; Accidents; Nuclear reactors; Irradiation; Fuels; Uranium; Safety; Occupational safety; Nuclear fuels; Metallurgy; USA, Idaho ER - TY - JOUR T1 - Forward for special JNM issue on accident tolerant fuels for LWRs AN - 1562673699; 20433031 AB - For the U.S. nuclear industry, the safe, reliable and economic operation of the nation's nuclear power reactor fleet has always been a top priority. As a result, continual improvement of the technology, materials, and fuels used has remained central to the industry's success. Decades of research combined with continual operation have produced steady advancements in technology and yielded an extensive base of data, experience and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. Thanks to efforts by the U.S. government, private companies, national laboratories, and universities, a variety of different technologies to optimize economic operation have been developed and deployed over time. JF - Journal of Nuclear Materials AU - Carmack, Jon AU - Goldner, Frank AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, United States, jon.carmack@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 373 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 448 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Accidents KW - Nuclear reactors KW - Fuels KW - Nuclear fuels KW - Economics KW - Radioactive materials KW - Priorities KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562673699?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Forward+for+special+JNM+issue+on+accident+tolerant+fuels+for+LWRs&rft.au=Carmack%2C+Jon%3BGoldner%2C+Frank&rft.aulast=Carmack&rft.aufirst=Jon&rft.date=2014-01-01&rft.volume=448&rft.issue=1-3&rft.spage=373&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.03.030 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Accidents; Nuclear reactors; Fuels; Radioactive materials; Economics; Nuclear fuels; Priorities; Technology DO - http://dx.doi.org/10.1016/j.jnucmat.2014.03.030 ER - TY - JOUR T1 - Performance of U-Mo Fuel at Low Temperatures AN - 1562668723; 20432574 AB - The development of LEU (low-enriched uranium) fuels for high-performance research reactors is an important objective of the National Nuclear Security Administration's GTRI program (Global Threat Reduction Initiative). The development of these fuels requires that a suitable high uranium density fuel phase be identified, developed, and qualified for service. Conversion of reactors that currently use HEU (highenriched uranium) must occur without significant impact to reactor mission performance, safety, or operating cost. Deployment of these fuels results in a significant decrease in HEU commerce. Professor Olander was invited to serve as a technical reviewer in 2006 to help guide this challenging program. The fuels developed by this program with Professor Olander's participation provide a interesting technical narrative. JF - Transactions of the American Nuclear Society AU - Meyer, M K AU - Gan, J AU - Keiser, D D AU - Wachs, D M AD - Idaho National Laboratory, 2525 N. Fremont Avenue, Idaho Falls, Idaho, 83415, mitchell.meyer@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 823 EP - 826 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts KW - Security KW - Nuclear reactors KW - Low temperature KW - Fuels KW - Uranium KW - Nuclear fuels KW - Safety KW - Operating costs KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562668723?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Performance+of+U-Mo+Fuel+at+Low+Temperatures&rft.au=Meyer%2C+M+K%3BGan%2C+J%3BKeiser%2C+D+D%3BWachs%2C+D+M&rft.aulast=Meyer&rft.aufirst=M&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=823&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Security; Low temperature; Nuclear reactors; Uranium; Fuels; Operating costs; Safety; Nuclear fuels ER - TY - JOUR T1 - Branch-and-Bound Algorithm Applied to Discrete Dynamic Event Trees AN - 1562667328; 20432449 AB - Methods for developing Phenomenological Identification and Ranking Tables (PIRT) for nuclear power plants have been a useful tool in providing insight into modelling aspects that are important to safety. These methods have involved expert knowledge with regards to reactor plant transients and thermal-hydraulic codes to identify are of highest importance. A PIRT provides a rigorous method for quantifying the phenomena that can have the greatest impact. The transients that are evaluated and the timing of those events are typically developed in collaboration with the Probabilistic Risk Analysis. Though quite effective in evaluating risk, traditional PRA methods lack the capability to evaluate complex dynamic systems where end states may vary as a function of transition time from physical state to physical state. JF - Transactions of the American Nuclear Society AU - Nielsen, Joseph AU - Tokuhiro, Akira AU - Hiromoto, Robert E AD - Idaho National Laboratory, P.O. Box 1625 Idaho Falls, Idaho, 83415 USA Y1 - 2014 PY - 2014 DA - 2014 SP - 345 EP - 348 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Risk Abstracts; Health & Safety Science Abstracts KW - Nuclear power plants KW - Risk analysis KW - Nuclear reactors KW - Safety KW - R2 23020:Technological risks KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562667328?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Branch-and-Bound+Algorithm+Applied+to+Discrete+Dynamic+Event+Trees&rft.au=Nielsen%2C+Joseph%3BTokuhiro%2C+Akira%3BHiromoto%2C+Robert+E&rft.aulast=Nielsen&rft.aufirst=Joseph&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=345&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Nuclear power plants; Risk analysis; Nuclear reactors; Safety ER - TY - JOUR T1 - Introduction of Supervised Learning Capabilities of the RAVEN Code for Limit Surface Analysis AN - 1562666851; 20432452 AB - The development of the RAVEN code [1-9] started in 2012 to provide the needed capabilities to the Risk Informed Safety Margins Characterization (RISMC) pathway [2] with the capability to forecast safety margins for nuclear power plant accident scenarios. The goal was achieved by a three way approach providing: 1) A graphical user interface for the RELAP-7 code, 2) A control logic/scenario generator framework for RELAP-7, and 3) A statistical analysis framework to assess safety margins. JF - Transactions of the American Nuclear Society AU - Rabiti, Cristian AU - Mandelli, Diego AU - Alfonsi, Andrea AU - Cogliati, Joshua AU - Kinoshita, Robert AD - Idaho National Laboratory, 2525 North Fremont Street, Idaho Falls (ID), cristian.rabiti@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 355 EP - 358 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Risk Abstracts; Health & Safety Science Abstracts KW - Risk assessment KW - Nuclear power plants KW - Accidents KW - Safety KW - R2 23020:Technological risks KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562666851?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Introduction+of+Supervised+Learning+Capabilities+of+the+RAVEN+Code+for+Limit+Surface+Analysis&rft.au=Rabiti%2C+Cristian%3BMandelli%2C+Diego%3BAlfonsi%2C+Andrea%3BCogliati%2C+Joshua%3BKinoshita%2C+Robert&rft.aulast=Rabiti&rft.aufirst=Cristian&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=355&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Risk assessment; Nuclear power plants; Accidents; Safety ER - TY - JOUR T1 - Transient Testing Plan for Accident Tolerant Fuels Program AN - 1562666778; 20432374 AB - The US Department of Energy (DOE) has been engaged in an effort to develop and qualify next generation light water reactor (LWR) fuel with enhanced performance and safety as well as reduced waste generation since 2010. This program was refocused from enhanced performance to enhanced accident tolerance following the events at the Japanese Fukushima Daiichi nuclear power plant in 2011. Accident tolerant fuels have been specifically described as fuels that, in comparison with the standard uranium oxide (UO sub(2))-Zircaloy fuel design, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, as well as design-basis and beyond design-basis events. The program maintains an ambitious goal to insert a lead test assembly (LTA) of the new design into a commercial power reactor by 2022[i]. JF - Transactions of the American Nuclear Society AU - Wachs, D M AU - Woolstenhulme, N AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, Daniel.Wachs@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 42 EP - 46 PB - American Nuclear Society, Inc. VL - 110 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts KW - Nuclear power plants KW - Accidents KW - Nuclear reactors KW - Safety engineering KW - Fuels KW - Uranium KW - Energy KW - Nuclear fuels KW - Safety KW - Water wells KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562666778?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Transient+Testing+Plan+for+Accident+Tolerant+Fuels+Program&rft.au=Wachs%2C+D+M%3BWoolstenhulme%2C+N&rft.aulast=Wachs&rft.aufirst=D&rft.date=2014-01-01&rft.volume=110&rft.issue=&rft.spage=42&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Nuclear power plants; Accidents; Nuclear reactors; Safety engineering; Energy; Uranium; Fuels; Safety; Nuclear fuels; Water wells ER - TY - JOUR T1 - Microstructural characteristics of HIP-bonded monolithic nuclear fuels with a diffusion barrier AN - 1560102455; 20433017 AB - Due to the limitation of maximum uranium load achievable by dispersion fuel type, the Global Threat Reduction Initiative is developing an advanced monolithic fuel to convert US high-performance research reactors to low-enriched uranium, Hot-isostatic-press (HIP) bonding was the single process down-selected to bond monolithic U-Mo fuel meat to aluminum alloy cladding. A diffusion barrier was applied to the U-Mo fuel meat by roll-bonding process to prevent extensive interaction between fuel meat and aluminum-alloy cladding. Microstructural characterization was performed on fresh fuel plates fabricated at Idaho National Laboratory. There are several issues or concerns that warrant more detailed study, such as precipitation along the cladding-to-cladding bond line, chemical banding, uncovered fuel-zone edge, and the interaction layer between the U-Mo fuel meat and zirconium. Future post-irradiation examination results will focus, among other things, on identifying in-reactor failure mechanisms and, eventually, directing further fresh fuel characterization efforts. JF - Journal of Nuclear Materials AU - Jue, Jan-Fong AU - Keiser, Dennis D, Jr AU - Breckenridge, Cynthia R AU - Moore, Glenn A AU - Meyer, Mitchell K AD - Idaho National Laboratory, 2525 Fremont Street, Idaho Falls, ID 83402, United States, dennis.keiser@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 250 EP - 258 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 448 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Meat KW - USA, Idaho KW - Nuclear reactors KW - Fuels KW - Uranium KW - Nuclear fuels KW - Aluminum KW - Radioactive materials KW - Alloys KW - Diffusion KW - Zirconium KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1560102455?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Microstructural+characteristics+of+HIP-bonded+monolithic+nuclear+fuels+with+a+diffusion+barrier&rft.au=Jue%2C+Jan-Fong%3BKeiser%2C+Dennis+D%2C+Jr%3BBreckenridge%2C+Cynthia+R%3BMoore%2C+Glenn+A%3BMeyer%2C+Mitchell+K&rft.aulast=Jue&rft.aufirst=Jan-Fong&rft.date=2014-01-01&rft.volume=448&rft.issue=1-3&rft.spage=250&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2014.02.004 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Number of references - 28 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Meat; Nuclear reactors; Uranium; Fuels; Radioactive materials; Aluminum; Nuclear fuels; Alloys; Zirconium; Diffusion; USA, Idaho DO - http://dx.doi.org/10.1016/j.jnucmat.2014.02.004 ER - TY - JOUR T1 - Identification of silver and palladium in irradiated TRISO coated particles of the AGR-1 experiment AN - 1540236857; 20081658 AB - Evidence of the release of certain metallic fission products through intact tristructural isotropic (TRISO) particles has been seen for decades around the world, as well as in the recent AGR-1 experiment at the Idaho National Laboratory (INL). However, understanding the basic mechanism of transport is still lacking. This understanding is important because the TRISO coating is part of the high temperature gas-cooled reactor functional containment and critical for the safety strategy for licensing purposes. Our approach to identify fission products in irradiated AGR-1 TRISO fuel using scanning transmission electron microscopy (STEM), electron energy loss spectroscopy (EELS) and energy filtered TEM (EFTEM), has led to first-of-a-kind data at the nano-scale indicating the presence of silver at triple-points and grain boundaries of the SiC layer in the TRISO particle. The findings reported in this paper may support the postulations of recent research that Ag transport may be driven by grain boundary diffusion. Additionally, the usefulness of the advanced electron microscopic techniques for TRISO coated particle research is demonstrated in this paper. JF - Journal of Nuclear Materials AU - van Rooyen, I J AU - Lillo, T M AU - Wu, Y Q AD - Fuel Performance and Design Department, Idaho National Laboratory, Idaho Falls, ID 83415-6188, USA, Isabella.vanRooyen@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 178 EP - 186 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 446 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Laboratory testing KW - Particulates KW - Fission products KW - USA, Idaho KW - Nuclear reactors KW - High temperature KW - Energy KW - Microscopy KW - Radioactive materials KW - Diffusion KW - Containment KW - Grains KW - Silver KW - Palladium KW - Coatings KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1540236857?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Identification+of+silver+and+palladium+in+irradiated+TRISO+coated+particles+of+the+AGR-1+experiment&rft.au=van+Rooyen%2C+I+J%3BLillo%2C+T+M%3BWu%2C+Y+Q&rft.aulast=van+Rooyen&rft.aufirst=I&rft.date=2014-01-01&rft.volume=446&rft.issue=1-3&rft.spage=178&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2013.11.028 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-06-01 N1 - Number of references - 21 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Laboratory testing; Particulates; Fission products; Nuclear reactors; Energy; High temperature; Radioactive materials; Microscopy; Diffusion; Grains; Containment; Silver; Palladium; Coatings; USA, Idaho DO - http://dx.doi.org/10.1016/j.jnucmat.2013.11.028 ER - TY - JOUR T1 - Oxidation and hydrogen uptake in zirconium, Zircaloy-2 and Zircaloy-4: Computational thermodynamics and ab initio calculations AN - 1534825214; 19900662 AB - Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in nuclear industry as cladding materials for BWRs and PWRs, respectively. Over more than 60 years these materials displayed a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion, and/or oxidation, especially in the case of Zircaloy-4 [1-3]. However, over the last couple of years energetic efforts were undertaken to improve their oxidation resistance during off-normal temperature excursions, as well as to further improve upon the already achieved levels of mechanical behavior and reduced hydrogen uptake [1-3]. In order to facilitate the development of such novel materials, it is very important to achieve not only engineering control, but also scientific understanding of the underlying material degradation mechanisms, both in working conditions and in storage of spent nuclear fuel. This paper strives to contribute to these efforts by constructing the thermodynamic models of both alloys, constructing of the respective phase diagrams, and oxidation mechanisms. A special emphasis was placed upon the role of zirconium suboxides [4] in hydrogen uptake reduction and the atomic mechanisms of oxidation. To that end, computational thermodynamics calculations were conducted concurrently with first-principles atomistic modeling. JF - Journal of Nuclear Materials AU - Glazoff, Michael V AU - Tokuhiro, Akira AU - Rashkeev, Sergey N AU - Sabharwall, Piyush AD - Idaho National Laboratory, MS 3710, Idaho Falls, ID 83415-3710, United States, michael.glazoff@inl.gov Y1 - 2014 PY - 2014 DA - 2014 SP - 65 EP - 75 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 444 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Zirconium base alloys KW - Zircaloy-2 KW - Zircaloy-4 KW - Degradation KW - Thermodynamics KW - Temperature KW - Zirconium KW - Hydrogen KW - Working conditions KW - Creep KW - Radioactive materials KW - Nuclear fuels KW - Oxidation KW - Corrosion KW - Absorption KW - Alloys KW - Uptake KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1534825214?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Oxidation+and+hydrogen+uptake+in+zirconium%2C+Zircaloy-2+and+Zircaloy-4%3A+Computational+thermodynamics+and+ab+initio+calculations&rft.au=Glazoff%2C+Michael+V%3BTokuhiro%2C+Akira%3BRashkeev%2C+Sergey+N%3BSabharwall%2C+Piyush&rft.aulast=Glazoff&rft.aufirst=Michael&rft.date=2014-01-01&rft.volume=444&rft.issue=1-3&rft.spage=65&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2013.09.038 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-06-01 N1 - Number of references - 86 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Thermodynamics; Degradation; Temperature; Zirconium; Hydrogen; Working conditions; Creep; Oxidation; Nuclear fuels; Radioactive materials; Absorption; Corrosion; Uptake; Alloys DO - http://dx.doi.org/10.1016/j.jnucmat.2013.09.038 ER - TY - JOUR T1 - Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel AN - 1534824714; 19900673 AB - Predicting the thermal conductivity of oxide fuels as a function of bum-up and temperature is fundamental to the efficient and safe operation of nuclear reactors. However, modeling the thermal conductivity of fuel is greatly complicated by the radially inhomogeneous nature of irradiated fuel in both composition and microstructure. In this work, radially and temperature-dependent models for effective thermal conductivity were developed utilizing optical micrographs of high burn-up mixed oxide fuel. The micrographs were employed to create finite element meshes with the OOF2 software. The meshes were then used to calculate the effective thermal conductivity of the microstructures using the BISON [1] fuel performance code. The new thermal conductivity models were used to calculate thermal profiles at end of life for the fuel pellets. These results were compared to thermal conductivity models from the literature, and comparison between the new finite element-based thermal conductivity model and the Duriez-Lucuta model was favorable. JF - Journal of Nuclear Materials AU - Teague, Melissa AU - Tonks, Michael AU - Novascone, Stephen AU - Hayes, Steven AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, USA, melissacteague@gmail.com Y1 - 2014 PY - 2014 DA - 2014 SP - 161 EP - 169 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 444 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Computer programs KW - Nuclear reactors KW - Thermal conductivity KW - Fuels KW - Nuclear fuels KW - Radioactive materials KW - Temperature KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1534824714?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Microstructural+modeling+of+thermal+conductivity+of+high+burn-up+mixed+oxide+fuel&rft.au=Teague%2C+Melissa%3BTonks%2C+Michael%3BNovascone%2C+Stephen%3BHayes%2C+Steven&rft.aulast=Teague&rft.aufirst=Melissa&rft.date=2014-01-01&rft.volume=444&rft.issue=1-3&rft.spage=161&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2013.09.035 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-06-01 N1 - Number of references - 48 N1 - Last updated - 2015-04-02 N1 - SubjectsTermNotLitGenreText - Computer programs; Nuclear reactors; Thermal conductivity; Fuels; Radioactive materials; Nuclear fuels; Temperature DO - http://dx.doi.org/10.1016/j.jnucmat.2013.09.035 ER - TY - JOUR T1 - Controls of Wellbore Flow Regimes on Pump Effluent Composition AN - 1492622825; 18988065 AB - Where well water and formation water are compositionally different or heterogeneous, pump effluent composition will vary due to partial mixing and transport induced by pumping. Investigating influences of purging and sampling methodology on composition variability requires quantification of wellbore flow regimes and mixing. As a basis for this quantification, analytical models simulating Poiseuille flow were developed to calculate flow paths and travel times. Finite element modeling was used to incorporate influences of mixing. Parabolic velocity distributions within the screened interval accelerate with cumulative inflow approaching the pump intake while an annulus of inflowing formation water contracts uniformly to displace an axial cylinder of pre-pumping well water as pumping proceeds. Increased dispersive mixing forms a more diffuse formation water annulus and the contribution of formation water to pump effluent increases more rapidly. Models incorporating viscous flow and diffusion scale mixing show that initially pump effluent is predominantly pre-pumping well water and compositions vary most rapidly. After two screen volumes of pumping, 94% of pump effluent is inflowing formation water. Where the composition of formation water and pre-pumping well water are likely to be similar, pump effluent compositions will not vary significantly and may be collected during early purging or with passive sampling. However, where these compositions are expected to be considerably different or heterogeneous, compositions would be most variable during early pumping, that is, when samples are collected during low-flow sampling. Purging of two screen volumes would be required to stabilize the content and collect a sample consisting of 94% formation water. JF - Ground Water AU - Martin-Hayden, James M AU - Plummer, Mitchell AU - Britt, Sanford L AD - Idaho National Laboratories, Idaho Falls, ID 83415; (208) 526-2785, Mitchell.Plummer@INL.gov Y1 - 2014/01// PY - 2014 DA - Jan 2014 SP - 96 EP - 104 PB - Wiley-Blackwell, 111 River Street Hoboken NJ 07030-5774 United States VL - 52 IS - 1 SN - 0017-467X, 0017-467X KW - Environment Abstracts; Water Resources Abstracts; Aqualine Abstracts; ASFA 3: Aquatic Pollution & Environmental Quality; ASFA 2: Ocean Technology Policy & Non-Living Resources KW - Contracts KW - Mixing KW - Well Water KW - Diffusion KW - Sampling KW - Pumping KW - Finite element method KW - Cylinders KW - Inflow KW - Velocity KW - Effluents KW - Model Studies KW - Screens KW - Laminar flow KW - Water wells KW - Pumps KW - Groundwater KW - Q2 09422:Storage and transport KW - SW 5010:Network design KW - Q5 08502:Methods and instruments KW - AQ 00008:Effects of Pollution KW - ENA 19:Water Pollution UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1492622825?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aaqualine&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Ground+Water&rft.atitle=Controls+of+Wellbore+Flow+Regimes+on+Pump+Effluent+Composition&rft.au=Martin-Hayden%2C+James+M%3BPlummer%2C+Mitchell%3BBritt%2C+Sanford+L&rft.aulast=Martin-Hayden&rft.aufirst=James&rft.date=2014-01-01&rft.volume=52&rft.issue=1&rft.spage=96&rft.isbn=&rft.btitle=&rft.title=Ground+Water&rft.issn=0017467X&rft_id=info:doi/10.1111%2Fgwat.12036 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-01-01 N1 - Number of references - 14 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Laminar flow; Contracts; Cylinders; Pumping; Effluents; Well Water; Finite element method; Inflow; Velocity; Water wells; Diffusion; Pumps; Groundwater; Screens; Sampling; Mixing; Model Studies DO - http://dx.doi.org/10.1111/gwat.12036 ER - TY - JOUR T1 - A code intercomparison study for THMC simulators applied to enhanced geothermal systems AN - 1696872943; 2015-066385 AB - Numerical simulation codes have become critical tools for understanding complex geologic processes, as applied to technology assessment, system design, monitoring, and operational guidance. Recently the need for quantitatively evaluating coupled Thermodynamic, Hydrologic, geoMechanical, and geoChemical (THMC) processes has grown, driven by new applications such as geologic sequestration of greenhouse gases and development of unconventional energy sources. Here we focus on Enhanced Geothermal Systems (EGS), which are man-made geothermal reservoirs created where hot rock exists but there is insufficient natural permeability and/or pore fluids to allow efficient energy extraction. In an EGS, carefully controlled subsurface fluid injection is performed to enhance the permeability of pre-existing fractures, which facilitates fluid circulation and heat transport. EGS technologies are relatively new, and pose significant simulation challenges. To become a trusted analytical tool for EGS, numerical simulation codes must be tested to demonstrate that they adequately represent the coupled THMC processes of concern. This presentation describes the approach and status of a benchmarking and code intercomparison effort currently underway, supported by the U. S. Department of Energy's Geothermal Technologies Program. This study is being closely coordinated with a parallel international effort sponsored by the International Partnership for Geothermal Technology (IPGT). We have defined an extensive suite of benchmark problems, test cases, and challenge problems, ranging in complexity and difficulty, and a number of modeling teams are applying various simulation tools to these problems. The descriptions of the problems and modeling results are being compiled using the Velo framework, a scientific workflow and data management environment accessible through a simple web-based interface. JF - American Geophysical Union Fall Meeting AU - Scheibe, T D AU - White, M D AU - Wurstner White, S AU - Sivaramakrishnan, C AU - Purohit, S AU - Black, G AU - Podgorney, R K AU - Phillips, B R AU - Boyd, L AU - Anonymous Y1 - 2013/12// PY - 2013 DA - December 2013 SP - Abstract H32G EP - 06 PB - American Geophysical Union, Washington, DC VL - 2013 KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1696872943?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=A+code+intercomparison+study+for+THMC+simulators+applied+to+enhanced+geothermal+systems&rft.au=Scheibe%2C+T+D%3BWhite%2C+M+D%3BWurstner+White%2C+S%3BSivaramakrishnan%2C+C%3BPurohit%2C+S%3BBlack%2C+G%3BPodgorney%2C+R+K%3BPhillips%2C+B+R%3BBoyd%2C+L%3BAnonymous&rft.aulast=Scheibe&rft.aufirst=T&rft.date=2013-12-01&rft.volume=2013&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2013 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2015-07-17 N1 - CODEN - #07548 ER - TY - JOUR T1 - Numerical modeling of the Snowmass Creek paleoglacier, Colorado; implications for middle and late Pleistocene climate in the Rocky Mountains AN - 1664434287; 2015-023036 AB - Well-preserved moraines from the last two glaciations of the Snowmass Creek valley in the Elk Range of Colorado present an opportunity to examine the character of the high-altitude climate in the Rocky Mountains during marine isotope stages 6 and 2. This study employs a 2-D coupled energy/mass balance and flow model (Plummer and Phillips, 2003) to assess the magnitudes of temperature and precipitation change that could have sustained the glacier in mass-balance equilibrium at its maximum extents during the penultimate (MIS 6 or Bull Lake) glaciation and the last glacial maximum (MIS 2 or Pinedale). Variable substrate effects on glacier flow and ice thickness make the modeling somewhat more complex than in geologically simpler settings. Model results indicate that a temperature depression of about 6.4 degrees C compared to the modern (1971-2000AD) would have been necessary to sustain the 26 km-long Snowmass Creek glacier in mass balance equilibrium during the Bull Lake glaciation, assuming no change from the modern in precipitation amount or seasonality. Uncertainty in the modeling is about 1 degrees C. A 50 percent increase or decrease from modern precipitation would have been coupled with 4.8 degrees C and 8.8 degrees C Bull. Lake temperature depressions respectively. The maximum extent of the glacier during MIS 2 or Pinedale glaciation is somewhat less clear. Moraines confidently assigned to the Pinedale glaciation indicate a temperature depression of about 6.1 degrees C, assuming no change in precipitation. An intermediate set of moraines which may be Pinedale in age, would suggest a Pinedale temperature depression very close to that of the Bull Lake glaciation. These Pinedale temperature depression estimates are comparable to those obtained using the same model in three other Colorado ranges (5.5-6.8 degrees C with no change in precipitation) and slightly less than those previously obtained using a variety of other paleoglaciological methods (6.4 to 8.5 degrees C with no change in precipitation). The Bull Lake climate estimates are the first we are aware of for the Colorado Rocky Mountains. JF - American Geophysical Union Fall Meeting AU - Leonard, E M AU - Plummer, M A AU - Carrara, P E AU - Anonymous Y1 - 2013/12// PY - 2013 DA - December 2013 SP - Abstract C33A EP - 0687 PB - American Geophysical Union, Washington, DC VL - 2013 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1664434287?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Numerical+modeling+of+the+Snowmass+Creek+paleoglacier%2C+Colorado%3B+implications+for+middle+and+late+Pleistocene+climate+in+the+Rocky+Mountains&rft.au=Leonard%2C+E+M%3BPlummer%2C+M+A%3BCarrara%2C+P+E%3BAnonymous&rft.aulast=Leonard&rft.aufirst=E&rft.date=2013-12-01&rft.volume=2013&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2013 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2015-03-19 N1 - CODEN - #07548 ER - TY - JOUR T1 - Shale gas; opportunities and challenges AN - 1469627284; 2013-101119 AB - Shales are becoming the most important source of natural gas in North America, and replacement of coal by natural gas is reducing CO (sub 2) emissions and improving air quality. Nevertheless, shale gas is facing strong opposition from environmental nongovernmental organizations. Although these organizations have greatly exaggerated the potential negative environmental impacts of shale gas and shale oil, methane leakage and contamination of groundwater and surface water by flowback and produced waters are serious concerns. These contamination pathways are not unique to shale gas and shale oil, and they are manageable. JF - Environmental Geosciences AU - Meakin, Paul AU - Huang, Hai AU - Malthe-Sorenssen, Anders AU - Thogersen, Kjetil Y1 - 2013/12// PY - 2013 DA - December 2013 SP - 151 EP - 164 PB - American Association of Petroleum Geologists (AAPG), Division of Environmental Geosciences, Tulsa, OK VL - 20 IS - 4 SN - 1075-9565, 1075-9565 KW - shale gas KW - sedimentary basins KW - natural gas KW - source rocks KW - aliphatic hydrocarbons KW - petroleum KW - fluid dynamics KW - combustion KW - seepage KW - rock mechanics KW - ground water KW - carbon dioxide KW - mitigation KW - sedimentary rocks KW - energy sources KW - coal KW - basins KW - discharge KW - hydraulic fracturing KW - North America KW - methane KW - injection KW - pollution KW - mechanical properties KW - gas shale KW - alkanes KW - organic compounds KW - hydrocarbons KW - theoretical models KW - greenhouse gases KW - water resources KW - permeability KW - 29A:Economic geology, geology of energy sources KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1469627284?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Environmental+Geosciences&rft.atitle=Shale+gas%3B+opportunities+and+challenges&rft.au=Meakin%2C+Paul%3BHuang%2C+Hai%3BMalthe-Sorenssen%2C+Anders%3BThogersen%2C+Kjetil&rft.aulast=Meakin&rft.aufirst=Paul&rft.date=2013-12-01&rft.volume=20&rft.issue=4&rft.spage=151&rft.isbn=&rft.btitle=&rft.title=Environmental+Geosciences&rft.issn=10759565&rft_id=info:doi/10.1306%2Feg.05311313005 L2 - http://www.ingentaconnect.com/content/bsc/ege LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. Reference includes data from GeoScienceWorld, Alexandria, VA, United States | Reference includes data supplied by American Association of Petroleum Geologists, Tulsa, OK, United States N1 - Date revised - 2013-01-01 N1 - Number of references - 78 N1 - PubXState - OK N1 - Document feature - illus. N1 - Last updated - 2013-12-20 N1 - SubjectsTermNotLitGenreText - aliphatic hydrocarbons; alkanes; basins; carbon dioxide; coal; combustion; discharge; energy sources; fluid dynamics; gas shale; greenhouse gases; ground water; hydraulic fracturing; hydrocarbons; injection; mechanical properties; methane; mitigation; natural gas; North America; organic compounds; permeability; petroleum; pollution; rock mechanics; sedimentary basins; sedimentary rocks; seepage; shale gas; source rocks; theoretical models; water resources DO - http://dx.doi.org/10.1306/eg.05311313005 ER - TY - JOUR T1 - Defining Human Failure Events for Petroleum Risk Analysis AN - 1701074602; 20460511 AB - Human reliability analysis (HRA) methods have largely been developed in support of nuclear power control room operations. For example, the original HRA method, a Technique for Human Error Rate Prediction (THERP) [1], features a set of simplified scenarios that match key actions primarily performed by reactor operators. However, actions taken in a nuclear power plant control room do not in all cases generalize to the types of actions performed elsewhere. As such, it can be challenging to extrapolate these scenarios to other domains like the petroleum industry. Moreover, the data basis for these nuclear centric actions may not match other industries. This mismatch can lead to questions about the non-nuclear validity of the human error probabilities (HEPs) derived from the HRA methods. However, it's important to note that the data in THERP, which has also served as the foundation for many other methods, was originally collected from nuclear weapons assembly work and later generalized to nuclear power. It is therefore reasonable to assume that with careful consideration, existing HRA methods and their underlying quantitative bases could reasonably be extrapolated to match other industries like oil and gas. JF - Transactions of the American Nuclear Society AU - Boring, Ronald Laurids AU - Oien, Knut AD - Idaho National Laboratory, PO Box 1625, Idaho Falls, Idaho 83415-3605, USA ronald.boring@inl.gov Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 2096 EP - 2097 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power KW - Nuclear power generation KW - Risk analysis KW - Human error KW - Crude oil KW - Extrapolation KW - Human KW - Control rooms UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1701074602?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Defining+Human+Failure+Events+for+Petroleum+Risk+Analysis&rft.au=Boring%2C+Ronald+Laurids%3BOien%2C+Knut&rft.aulast=Boring&rft.aufirst=Ronald&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=2096&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2015-08-04 ER - TY - JOUR T1 - A Complex-Geometry Validation Experiment for Advanced Neutron Transport Codes AN - 1671612115; 20460337 AB - The Idaho National Laboratory (INL) has initiated a focused effort to upgrade legacy computational reactor physics software tools and protocols used for support of core fuel management and experiment management in the Advanced Test Reactor (ATR) and its companion critical facility (ATRC) at the ML.. This will be accomplished through the introduction of modern high-fidelity computational software and protocols, with appropriate new Verification and Validation (V&V) protocols, over the next 12-18 months. Stochastic and deterministic transport theory based reactor physics codes and nuclear data packages that support this effort include MCNP5[1], SCALE/KEN06[2], HELIOS[3], SCALE/NEWT[2], and ATTILA[4]. Furthermore, a capability for sensitivity analysis and uncertainty quantification based on the TSUNAMI[5] system has also been implemented. Finally, we are also evaluating the Serpent[6] and MC21[7] codes, as additional verification tools in the near term as well as for possible applications to full threedimensional Monte Carlo based fuel management modeling in the longer term. JF - Transactions of the American Nuclear Society AU - Nigg, David W AU - LaPorta, Anthony AU - Nielsen, Joseph W AU - Parry, James AU - DeHart, Mark D AU - Bays, Samuel E AU - Skerjanc, William F AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls ID 83415 USA Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 1490 EP - 1493 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Software KW - Computer programs KW - Computation KW - Management KW - Sensitivity analysis KW - Monte Carlo methods KW - Fuels KW - Reactor physics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1671612115?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=A+Complex-Geometry+Validation+Experiment+for+Advanced+Neutron+Transport+Codes&rft.au=Nigg%2C+David+W%3BLaPorta%2C+Anthony%3BNielsen%2C+Joseph+W%3BParry%2C+James%3BDeHart%2C+Mark+D%3BBays%2C+Samuel+E%3BSkerjanc%2C+William+F&rft.aulast=Nigg&rft.aufirst=David&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=1490&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2015-04-09 ER - TY - JOUR T1 - EVALUATION OF HEAT EXCHANGER DESIGNS FOR SMALL MODULAR HIGH TEMPERATURE REACTORS AN - 1671578924; 20460547 AB - Developmental work for advanced reactors includes preliminary designs for various small size reactors, such as PRISM, EM super(2), G4M, 4S, GT-MHR, PBMR, MHTGR and SC-HTGR. The most important feature of SC-HTGR and MHTGR design, which is the name sake of the reactor, is a high outlet temperature. The high outlet temperature lends this design of reactor to special applications outside the scope of current reactor designs, namely high temperature process heat for industrial uses. The key to this design is to find a suitable heat exchanger to provide the required heat transfer while exhibiting the necessary performance required for use with a nuclear reactor. This paper presents and compares many of the current and advanced designs of heat exchangers to determine its feasibility in the application of a Rankine cycle plant. JF - Transactions of the American Nuclear Society AU - Robison, Caleb AU - Aydogan, Fatih AD - Center for Advanced Energy Studies (CAES), 995 University Blvd., Idaho Falls, ID 8340 Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 2225 EP - 2227 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Outlets KW - Nuclear reactors KW - Preliminary designs KW - Process heat KW - Heat exchangers KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1671578924?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=EVALUATION+OF+HEAT+EXCHANGER+DESIGNS+FOR+SMALL+MODULAR+HIGH+TEMPERATURE+REACTORS&rft.au=Robison%2C+Caleb%3BAydogan%2C+Fatih&rft.aulast=Robison&rft.aufirst=Caleb&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=2225&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2015-04-09 ER - TY - JOUR T1 - Options Development for Comprehensive Fuel Cycle Analysis, invited AN - 1567094468; 20460326 AB - The U.S. Department of Energy has chartered a study on the relative performance of nuclear fuel cycles as compared to the current U.S nuclear fuel cycles using a number of high-level evaluation criteria [1]. As part of this study, specific fuel cycle options are being analyzed in order to provide data that can be used in assessing the performance of alternative fuel cycles. One of the requirements of the study is that the fuel cycle options considered in the study must comprehensively represent the entire range of potential fuel cycle performance. To meet this goal for conducting this study, a set of fundamental guiding principles were developed that have the capability to distinguish the performance between various fuel cycle options. JF - Transactions of the American Nuclear Society AU - Wigelanda, R A AU - Taiwo, T A AU - Kim, T K AU - Todosow, M AD - Idaho National Laboratory, 2525 N Fremont Avenue, P. O. Box 1625, Idaho Falls, ID 83415 U.S.A Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 1451 EP - 1452 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Energy use KW - Energy (nuclear) KW - Fuel cycles KW - Nuclear fuels KW - Alternative fuels KW - Criteria KW - Conduction UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567094468?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Options+Development+for+Comprehensive+Fuel+Cycle+Analysis%2C+invited&rft.au=Wigelanda%2C+R+A%3BTaiwo%2C+T+A%3BKim%2C+T+K%3BTodosow%2C+M&rft.aulast=Wigelanda&rft.aufirst=R&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=1451&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Utility of the KUCA-Er Benchmark to Address Erbium Sensitivities in the NRAD Reactor AN - 1567091793; 20460345 AB - The benchmark evaluation of the Neutron Radiography (NRAD) Reactor located at the Idaho National Laboratory identified a large computational bias when sample calculations of the well-characterized models were performed. The current eigenvalue calculation bias for the 60-fuel-element critical configuration is approximately 1% above the benchmark value [1]. As the NRAD benchmark was the first, and only, benchmark to include a significant quantity of erbium, it was initially thought that additional evaluations of experiments containing erbium might facilitate the identification of any potential errors in erbium cross section data. JF - Transactions of the American Nuclear Society AU - Bess, John D AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 John.Bess@inl.gov Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 1515 EP - 1518 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Mathematical models KW - Nuclear reactor components KW - Benchmarking KW - Bias KW - Nuclear engineering KW - Erbium UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567091793?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Utility+of+the+KUCA-Er+Benchmark+to+Address+Erbium+Sensitivities+in+the+NRAD+Reactor&rft.au=Bess%2C+John+D&rft.aulast=Bess&rft.aufirst=John&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=1515&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Numerical Study on the Crossflow Printed Circuit Heat Exchanger for Advanced Small Modular Reactors AN - 1567090249; 20460389 AB - Printed-circuit heat exchanger (PCHE) is a promising compact heat exchanger for advanced small modular reactors (SMR) because it is not only applicable to high pressure and temperature conditions, but also has high surface area density and efficiency that result in the reduced size, weight and cost. Contrary to the parallel or countercurrent flow PCHE, the temperature profile of crossflow PCHE is two-dimensional, thus, is not simple to analyze. The crossflow PCHE analysis code is being developed by applying analytical solution of single-pass, both unmixed fluids crossflow heat exchanger [1]. However, the experimental data for the code validation is not available. Instead of experimental data, the CFD simulation result would be used for the code validation. In this respect, the objective of this paper is to generate the CFD simulation results for the crossflow PCHE which will be used to validate the crossflow PCHE analysis code. Numerical study using commercial CFD code, CFX-13 [2], was performed to investigate the temperature profile of crossflow PCHE for advanced SMRs. Water-cooled, helium-cooled, sodium-cooled and molten salt-cooled SMRs were taken into account in the simulation. Typical operating conditions of SMRs are summarized in Table I. JF - Transactions of the American Nuclear Society AU - Yoon, Su-Jong AU - Kim, Eung-Soo AU - Sabharwall, Piyush AD - Idaho National Laboratory: 2525 Fremont Avenue, Idaho Falls, ID 83415, USA sujong.yoon@inl.gov Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 1660 EP - 1662 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); Computer and Information Systems Abstracts (CI); CSA / ASCE Civil Engineering Abstracts (CE) KW - Modular KW - Nuclear power generation KW - Computational fluid dynamics KW - Nuclear reactors KW - Mathematical models KW - Computer simulation KW - Heat exchangers KW - Nuclear reactor components UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567090249?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Numerical+Study+on+the+Crossflow+Printed+Circuit+Heat+Exchanger+for+Advanced+Small+Modular+Reactors&rft.au=Yoon%2C+Su-Jong%3BKim%2C+Eung-Soo%3BSabharwall%2C+Piyush&rft.aulast=Yoon&rft.aufirst=Su-Jong&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=1660&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Advanced Test Reactor National Scientific User Facility "New User" Experiment AN - 1567089967; 20459998 AB - The Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) is one of the world's premier test reactors for studying the effects of intense neutron radiation on reactor materials and fuels. The ATR began operation in 1967, and has operated continuously since then, averaging approximately 250 operating days per year. The combination of high flux, large test volumes, and multiple experiment configuration options provide unique testing opportunities for nuclear fuels and material researchers. The ATR is a pressurized, light-water moderated and cooled, beryllium-reflected highly-enriched uranium fueled, reactor with a maximum operating power of 250 MWt. The ATR peak thermal flux can reach 1.0 x10 super(15) n/cm super(2)-sec, and the core configuration creates five main reactor power lobes (regions) that can be operated at different powers during the same operating cycle. There are nine large high-flux irradiation positions in direct contact with the fuel and 68 irradiation positions in the reactor core reflector tank. The test positions range from 1.25-12.5 cm diameter and are all 1.2 m in length. There are four primary experiment configurations that can be used in ATR. These are the static capsule, instrumented lead, pressurized water loop, and the hydraulic shuttle irradiation system (HSIS). Also at the INL are several facilities used for experiment preparation and postirradiation examination (PIE). JF - Transactions of the American Nuclear Society AU - Marshall, Frances M AU - Palmer, A Joe AD - Advanced Test Reactor National Scientific User Facility Idaho National Laboratory, P. O. Box 1625-3553, Idaho Falls, ID, 83415, USA frances.marshall@inl.gov Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 235 EP - 236 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Advanced test reactors KW - Irradiation KW - Fuels KW - Tanks KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567089967?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Advanced+Test+Reactor+National+Scientific+User+Facility+%22New+User%22+Experiment&rft.au=Marshall%2C+Frances+M%3BPalmer%2C+A+Joe&rft.aulast=Marshall&rft.aufirst=Frances&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=235&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Chemical Detection in Flowing Molten LiCl-KCl Salt via Laser-Induced Breakdown Spectroscopy AN - 1567087938; 20460007 AB - Pyroprocessing technology has shown to have great potential for used nuclear fuel treatment. At the heart of pyroprocessing lies the electrorefiner (ER), which electrochemically dissolves uranium from the used fuel at an anode and deposits it on a cathode. Through normal operation of the ER, transuranics elements (such as plutonium and uranium), fission product chlorides and rare earth chlorides accumulate in the molten salt electrolyte over time. These contaminants change the physical properties of the salt, which influences the overall efficiency of the separation process. Thus, from an operational perspective, it is paramount that exact compositional information is available on the salt in order to adjust and ensure a proper operation. In addition, buildup of transuranic elements in the salt presents criticality and safeguarding concerns; this only increases the need for precise concentration data from the salt. JF - Transactions of the American Nuclear Society AU - Williams, Ammon N AU - Phongikaroon, Supathorn AD - Center for Advanced Energy Studies, University of Idaho, 995 University Blvd. Idaho Falls, ID 83402 Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 265 EP - 266 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Solid State and Superconductivity Abstracts (SO); Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Plutonium KW - Transuranic elements KW - Construction KW - Uranium KW - Nuclear fuels KW - Chlorides KW - Dissolution KW - Rare earth metals UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567087938?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Chemical+Detection+in+Flowing+Molten+LiCl-KCl+Salt+via+Laser-Induced+Breakdown+Spectroscopy&rft.au=Williams%2C+Ammon+N%3BPhongikaroon%2C+Supathorn&rft.aulast=Williams&rft.aufirst=Ammon&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=265&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Special Nuclear Material Resources at INL to Support Nuclear Nonproliferation R & D AN - 1567070213; 20460583 AB - With over sixty years of experience in the field of nuclear energy and technology research and development, Idaho National Laboratory (INL) has accumulated a diverse and unique inventory of special nuclear materials (SNM). Access to these materials is critical for work related to material protection control and accountancy, safeguards, nonproliferation, arms control, treaty verification, and nuclear forensics. Unfortunately, recent SNM consolidation activities in the United States and around the world have reduced the ability of scientists and engineers to access these materials and perform realistic research and development experiments in support of nuclear nonproliferation. Lack of access has also negatively impacted emergency responder organizations, reducing or in some cases eliminating their ability to perform field training exercises using their equipment and practicing their techniques under realistic scenarios. Further, the inaccessibility of these materials has slowed the development of new commercial instrumentation intended to serve these missions. JF - Transactions of the American Nuclear Society AU - Chichester, D L AU - Sanders, J AU - Turnage, J A AU - West, J D AU - Willmore, M A AU - Wise, C K AD - Idaho National Laboratory, 2525 North Fremont Avenue, Idaho Falls, Idaho 83415, USA Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 2318 EP - 2319 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Inventories KW - Stockpiling KW - Instrumentation KW - Research and development KW - Access control KW - Nuclear reactor components KW - Consolidation KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567070213?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Special+Nuclear+Material+Resources+at+INL+to+Support+Nuclear+Nonproliferation+R+%26amp%3B+D&rft.au=Chichester%2C+D+L%3BSanders%2C+J%3BTurnage%2C+J+A%3BWest%2C+J+D%3BWillmore%2C+M+A%3BWise%2C+C+K&rft.aulast=Chichester&rft.aufirst=D&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=2318&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Fuel Element Design and Analysis for Advanced Test Reactor Conversion to LEU Fuel AN - 1567062059; 20460299 AB - The Advanced Test Reactor (ATR), located at the Idaho National Laboratory (INL), is one of only a few high-power research reactors of its general type in the world. Its capabilities support a variety of missions involving accelerated testing of nuclear fuel and other materials in a very high neutron flux environment, medical and industrial isotope production, and several other specialized applications. Along with its companion critical mockup, the ATR Critical Facility (ATRC), the ATR is one of the key nuclear engineering research and testing facilities within the US Department of Energy (DOE) National Laboratory Complex. The ATR and ATRC also serve as the centerpieces of the ATR National Scientific User Facility (NSUF), whose purpose is to facilitate the current trend toward broadening application of the ATR beyond its traditional base. JF - Transactions of the American Nuclear Society AU - DeHart, Mark D AU - Pope, Michael A AU - Nigg, David W AU - Jamison, R Kirt AU - Morrell, Sean R AD - Idaho National Laboratory, 2525 Fremont, Idaho Falls, ID 83415-3870 Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 1343 EP - 1347 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear reactors KW - Energy (nuclear) KW - Advanced test reactors KW - Missions KW - Medical KW - Nuclear fuel elements KW - Nuclear reactor components KW - Mockups UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567062059?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Fuel+Element+Design+and+Analysis+for+Advanced+Test+Reactor+Conversion+to+LEU+Fuel&rft.au=DeHart%2C+Mark+D%3BPope%2C+Michael+A%3BNigg%2C+David+W%3BJamison%2C+R+Kirt%3BMorrell%2C+Sean+R&rft.aulast=DeHart&rft.aufirst=Mark&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=1343&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - BLOW-DOWN ANALYSIS USING OFF-SET FIN HEAT EXCHANGER WITH RELAP5-3D AN - 1567061373; 20460385 AB - The offset fin heat exchanger (HX) is a subcategory of plate and fin heat exchangers. This particular design is being discussed separately as its design leads to higher heat transfer coefficients than several of its competitors. The hot and cold legs may both have fins, or only one side may have fins. In the case of the High Temperature Gas Cooled Reactor (HTGR), since the helium hot side has a lower heat transfer coefficient than does the water side there is no need to have fins on the water secondary side. Because of the benefits of this design, the offset fin HX warrants further investigation. JF - Transactions of the American Nuclear Society AU - Robison, Caleb AU - Aydogan, Fatih AD - Center for Advanced Energy Studies (CAES), 995 University Blvd., Idaho Falls, ID 83401 Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 1646 EP - 1648 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Fins KW - Design engineering KW - Heat exchangers KW - Helium KW - Offsets KW - Legs KW - Heat transfer coefficients KW - High temperature gas cooled reactors UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567061373?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=BLOW-DOWN+ANALYSIS+USING+OFF-SET+FIN+HEAT+EXCHANGER+WITH+RELAP5-3D&rft.au=Robison%2C+Caleb%3BAydogan%2C+Fatih&rft.aulast=Robison&rft.aufirst=Caleb&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=1646&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Uncertainty Quantification of Calculated Temperatures for AGR Experiments AN - 1567061262; 20460108 AB - The Advanced Gas Reactor (AGR) fuel irradiation experiments were conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory in support of the Very High Temperature Reactor (VHTR) Research and Development (R&D) program. Substantial efforts on modeling and simulation have been performed to assist in the test design, experiment control, qualification of measured data, and quantification of test conditions [1,2]. The predicted temperatures at thermocouple locations are used in combination with statistical analysis methods for both improving calibration of the thermal model and qualification of the measured data. The calculated fuel temperatures are used for validation of the fission product transport and fuel performance simulation models. Because of the crucial roles of the simulation results in ensuring achievement of the program objectives, accurate determination of the model uncertainties is required. This paper focuses on uncertainty quantification of calculated temperature for the first experiment, AGR-1. JF - Transactions of the American Nuclear Society AU - Pham, Binh T AU - Einerson, Jeffrey J AD - Nuclear Science and Technology, Idaho National Laboratory, Idaho Falls, ID 83415 Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 629 EP - 630 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Uncertainty KW - Mathematical models KW - Computer simulation KW - Thermocouples KW - AGR KW - Research and development KW - Fuels KW - Nuclear reactor components UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567061262?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Uncertainty+Quantification+of+Calculated+Temperatures+for+AGR+Experiments&rft.au=Pham%2C+Binh+T%3BEinerson%2C+Jeffrey+J&rft.aulast=Pham&rft.aufirst=Binh&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=629&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Human Reliability Analysis for Digital Human-Machine Interfaces AN - 1567061060; 20460510 AB - This paper addresses the fact that many existing human reliability analysis (HRA) methods do not provide guidance on digital human-machine interfaces (HMIs). Digital HMIs are becoming ubiquitous in nuclear power operations, whether through control room modernization or new-build control rooms. Legacy analog technologies like analog instrumentation and control (I&C) systems are costly to support, and most vendors no longer develop or support such technology, which is considered technologically obsolete. JF - Transactions of the American Nuclear Society AU - Boring, Ronald Laurids AD - Idaho National Laboratory, PO Box 1625, Idaho Falls, Idaho 83415-3605 ronald.boring@inl.gov Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 2094 EP - 2095 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Man machine interfaces KW - Instrumentation KW - Legacy KW - Human KW - Modernization KW - Control rooms KW - Digital KW - Reliability analysis UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567061060?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Human+Reliability+Analysis+for+Digital+Human-Machine+Interfaces&rft.au=Boring%2C+Ronald+Laurids&rft.aulast=Boring&rft.aufirst=Ronald&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=2094&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - Cogeneration of Liquid Fuels and Electricity on Oahu AN - 1567059512; 20460546 AB - This paper summarizes the results of heat transport and economic models of a high temperature gas-cooled reactor (HTGR) cogenerating liquid transport fuels and electricity on the island of Oahu in the State of Hawaii. The technical and economic feasibility of cogeneration is evaluated, as well as the impact on emissions, Hawaiian energy security and job creation. It was determined that an HTGR, built and operated on the island of Oahu to cogenerate electricity and liquid transportation fuels from local crops, will generate lucrative returns on investment. JF - Transactions of the American Nuclear Society AU - Patterson, Michael W AD - Idaho National Laboratory: P.O. Box 1625, Idaho Falls, ID, 83415 mw.patterson@inl.gov Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 2221 EP - 2224 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Islands KW - Transport KW - Fuels KW - Economics KW - Nuclear reactor components KW - Electricity KW - Liquids KW - Cogeneration UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1567059512?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Cogeneration+of+Liquid+Fuels+and+Electricity+on+Oahu&rft.au=Patterson%2C+Michael+W&rft.aulast=Patterson&rft.aufirst=Michael&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=2221&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-10-01 N1 - Last updated - 2014-11-05 ER - TY - JOUR T1 - New Methods and Tools to Perform Safety Analysis within RISMC, invited AN - 1562672368; 20460049 AB - The Risk Informed Safety Margins Characterization (RISMC) Pathway under the U.S. Department of Energy Light Water Sustainability Program uses a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. What differentiates the RISMC approach from traditional probabilistic risk assessment (PRA) is the concept of a safety margin. In PRA, a safety metric such as core damage frequency (CDF) is generally estimated using static fault-tree and event-tree models. However, it is not possible to estimate how close we are to physical safety limits (say peak clad temperature) for most accident sequences described in the PRA. JF - Transactions of the American Nuclear Society AU - Mandelli, D AU - Smith, C AU - Rabiti, C AU - Alfonsi, A AU - Cogliati, j AU - Kinoshita, R AD - Idaho National Laboratory, 2525 North Fremont Street, Idaho Falls (ID) Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 411 EP - 414 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Risk Abstracts; Sustainability Science Abstracts KW - Risk assessment KW - Nuclear power plants KW - Accidents KW - Safety KW - Temperature KW - Nuclear energy KW - Sustainability KW - R2 23020:Technological risks KW - M3 1010:Issues in Sustainable Development UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562672368?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=New+Methods+and+Tools+to+Perform+Safety+Analysis+within+RISMC%2C+invited&rft.au=Mandelli%2C+D%3BSmith%2C+C%3BRabiti%2C+C%3BAlfonsi%2C+A%3BCogliati%2C+j%3BKinoshita%2C+R&rft.aulast=Mandelli&rft.aufirst=D&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=411&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Risk assessment; Nuclear power plants; Accidents; Safety; Temperature; Nuclear energy; Sustainability ER - TY - JOUR T1 - Automation, Cyber Security and Risk Assessment: HRA Where Art Thou? AN - 1562668301; 20460507 AB - Modern nuclear power plant design constitutes an interdependent set of complex systems operating upon a balance of automation and human-system interaction, and in the case of advanced multi-modular design the degree of automation proposed is greater still. Fleet sustainability is possible, in part, because of the large gains in I&C and fuel technologies made over the last 20 years. JF - Transactions of the American Nuclear Society AU - Gertman, David I AD - Human Factors, Statistics and Controls Dept. Idaho National Laboratory, Idaho Falls, ID 83404, david.gertman@inl.gov.208.526.1756 Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 2030 EP - 2033 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Risk Abstracts; Sustainability Science Abstracts KW - Risk assessment KW - Fuel technology KW - Nuclear power plants KW - Security KW - Automation KW - Sustainability KW - R2 23020:Technological risks KW - M3 1010:Issues in Sustainable Development UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562668301?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Automation%2C+Cyber+Security+and+Risk+Assessment%3A+HRA+Where+Art+Thou%3F&rft.au=Gertman%2C+David+I&rft.aulast=Gertman&rft.aufirst=David&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=2030&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Risk assessment; Security; Nuclear power plants; Fuel technology; Automation; Sustainability ER - TY - JOUR T1 - Station Blackout: A case study in the interaction of mechanistic and probabilistic safety analysis AN - 1562667923; 20460050 AB - The ability to better characterize and quantify safety margins is important to improved decision making about nuclear power plant design, operation, and plant life extension. As research and development (R&D) in the light-water reactor (LWR) Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. JF - Transactions of the American Nuclear Society AU - Smith, Curtis AU - Mandelli, Diego AU - Rabiti, Cristian AD - Idaho National Laboratory, PO Box 1625, MS 3850, Idaho Falls, ID 83415 Y1 - 2013/11/14/ PY - 2013 DA - 2013 Nov 14 SP - 415 EP - 418 PB - American Nuclear Society, Inc. VL - 109 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts; Sustainability Science Abstracts KW - Nuclear power plants KW - Decision making KW - Case studies KW - Nuclear reactors KW - Safety engineering KW - Sensors KW - Degradation KW - Safety KW - Aging KW - Sustainability KW - Research programs KW - H 8000:Radiation Safety/Electrical Safety KW - M3 1010:Issues in Sustainable Development UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1562667923?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Assamodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Station+Blackout%3A+A+case+study+in+the+interaction+of+mechanistic+and+probabilistic+safety+analysis&rft.au=Smith%2C+Curtis%3BMandelli%2C+Diego%3BRabiti%2C+Cristian&rft.aulast=Smith&rft.aufirst=Curtis&rft.date=2013-11-14&rft.volume=109&rft.issue=&rft.spage=415&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-09-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Decision making; Nuclear power plants; Nuclear reactors; Case studies; Degradation; Sensors; Safety engineering; Aging; Safety; Research programs; Sustainability ER - TY - CPAPER T1 - Algae Derived Bio-Oil Separation By Supercritical Fluid Fractionation T2 - 2013 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2013) AN - 1490503891; 6252368 JF - 2013 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2013) AU - Ginosar, Daniel AU - Agblevor, Foster AU - Petkovic, Lucia AU - Newby, Deborah AU - Moses, John Y1 - 2013/11/03/ PY - 2013 DA - 2013 Nov 03 KW - Fractionation KW - Algae UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1490503891?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2013+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2013%29&rft.atitle=Algae+Derived+Bio-Oil+Separation+By+Supercritical+Fluid+Fractionation&rft.au=Ginosar%2C+Daniel%3BAgblevor%2C+Foster%3BPetkovic%2C+Lucia%3BNewby%2C+Deborah%3BMoses%2C+John&rft.aulast=Ginosar&rft.aufirst=Daniel&rft.date=2013-11-03&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2013+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2013%29&rft.issn=&rft_id=info:doi/ L2 - https://aiche.confex.com/aiche/2013/webprogram/meeting2013-11-03.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-11-30 N1 - Last updated - 2014-02-10 ER - TY - JOUR T1 - Challenges in the development of high temperature reactors AN - 1458535534; 18724842 AB - Advanced reactor designs offer potentially significant improvements over currently operating light water reactors including improved fuel utilization, increased efficiency, higher temperature operation (enabling a new suite of non-electric industrial process heat applications), and increased safety. As with most technologies, these potential performance improvements come with a variety of challenges to bringing advanced designs to the marketplace. There are technical challenges in material selection and thermal hydraulic and power conversion design that arise particularly for higher temperature, long life operation (possibly >60 years). The process of licensing a new reactor design is also daunting, requiring significant data collection for model verification and validation to provide confidence in safety margins associated with operating a new reactor design under normal and off-normal conditions. This paper focuses on the key technical challenges associated with two proposed advanced reactor concepts: the helium gas cooled Very High Temperature Reactor (VHTR) and the molten salt cooled Advanced High Temperature Reactor (AHTR). JF - Energy Conversion & Management AU - Sabharwall, P AU - Bragg-Sitton, S M AU - Stoots, C AD - Idaho National Laboratory, P.O. Box 3860, Idaho Falls, ID 83415-38608, USA, Piyush.Sabharwall@inl.gov Y1 - 2013/10// PY - 2013 DA - Oct 2013 SP - 574 EP - 581 PB - Elsevier B.V., The Boulevard Langford Lane Kidlington Oxford OX5 1GB United Kingdom VL - 74 SN - 0196-8904, 0196-8904 KW - ASFA 2: Ocean Technology Policy & Non-Living Resources; Environment Abstracts KW - Hydraulics KW - Data collection KW - Fuels KW - Licensing KW - Temperature KW - Data collections KW - Salts KW - Nuclear reactors KW - Safety engineering KW - High temperature KW - Energy KW - Helium KW - Technology KW - ENA 03:Energy KW - Q2 09406:Energy from the sea UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1458535534?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Energy+Conversion+%26+Management&rft.atitle=Challenges+in+the+development+of+high+temperature+reactors&rft.au=Sabharwall%2C+P%3BBragg-Sitton%2C+S+M%3BStoots%2C+C&rft.aulast=Sabharwall&rft.aufirst=P&rft.date=2013-10-01&rft.volume=74&rft.issue=&rft.spage=574&rft.isbn=&rft.btitle=&rft.title=Energy+Conversion+%26+Management&rft.issn=01968904&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-11-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Fuels; Licensing; Helium; Data collections; Hydraulics; Salts; Data collection; Nuclear reactors; Safety engineering; Energy; High temperature; Temperature; Technology ER - TY - JOUR T1 - Thermophysical properties of Alloy 617 from 25 degree C to 1000 degree C AN - 1464603633; 18783559 AB - Key thermophysical properties needed for the successful design and use of Alloy 617 in steam generator and heat exchanger applications have been measured experimentally, and results are compared with literature values and results obtained from some other commercial Ni-Cr alloys and model materials. Specifically, the thermal diffusivity, thermal expansion coefficient, and specific heat capacity have been measured for Alloy 617 over a range of temperatures, allowing calculation of thermal conductivity up to 1000 degree C. It has been found that the thermal conductivity of Alloy 617 exhibits significant deviation from monotonic behavior in the temperature range from 600 degree C to 850 degree C, the temperatures of interest for most heat transfer applications. The non-linear behavior appears to result primarily from short-range order/disorder phenomena known to occur in the Ni-Cr system. Similar deviation from monotonic behavior was observed in the solid solution Ni-Cr-W Alloy 230, and lesser deviations were observed in iron based Alloy 800H and an austenitic stainless steel. Measured thermophysical property data are provided for four different heats of Alloy 617, and it is shown that property variations between the four different heats are not significant. Measurements were also obtained from Alloy 617 that was aged for up to 2000 h at 750 degree C, and it was found that this aging treatment does not significantly influence the thermophysical properties. JF - Nuclear Engineering and Design AU - Rabin, B H AU - Swank, W D AU - Wright, R N AD - Idaho National Laboratory, P.O. Box 1625. Idaho Falls. ID 83415-2211. United States barry.rabin@inl.gov Y1 - 2013/09// PY - 2013 DA - Sep 2013 SP - 72 EP - 80 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 262 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); METADEX (MD); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Ferrous alloys KW - Superalloys KW - Nickel base alloys KW - Intermetallic compounds KW - 800H KW - Alloy 230 KW - Alloy 617 KW - Alloy 800H KW - NiCr KW - Thermophysical properties KW - Thermal expansion KW - Thermal conductivity KW - Design engineering KW - Deviation KW - Heat transfer KW - Alloy steels UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1464603633?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Thermophysical+properties+of+Alloy+617+from+25+degree+C+to+1000+degree+C&rft.au=Rabin%2C+B+H%3BSwank%2C+W+D%3BWright%2C+R+N&rft.aulast=Rabin&rft.aufirst=B&rft.date=2013-09-01&rft.volume=262&rft.issue=&rft.spage=72&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-12-01 N1 - Number of references - 18 N1 - Last updated - 2014-04-08 ER - TY - JOUR T1 - Three dimensional calculations of the effective Kapitza resistance of UO(2) grain boundaries containing intergranular bubbles AN - 1475531699; 18796799 AB - A parametric study has been performed that quantifies the effective change in grain boundary Kapitza resistance due to the presence of intergranular bubbles. The steady-state heat conduction equation was solved in three-dimensional space using INL's MOOSE finite element software, with which spacial mesh adaptivity was used to resolve interfacial widths down to several nanometers while investigating bubble sizes up to a micrometer. Three critical parameters were systematically varied: the intergranular bubble radius, the fractional grain boundary bubble coverage, and the Kapitza resistance of the intact grain boundary. Using the simulation results, a mathematical model dependent on each of these parameters was developed to describe the effective Kapitza resistance. Furthermore, we illustrate how this model can be implemented in a fuel performance code to predict the temperature profile of a cylindrical fuel pellet. JF - Journal of Nuclear Materials AU - Millett, Paul C AU - Tonks, Michael R AU - Chockalingam, K AU - Zhang, Yongfeng AU - Biner, S B AD - Nuclear Fuels and Materials, Idaho National Laboratory, Idaho Falls, ID 83415, USA, Paul.Millett@inl.gov Y1 - 2013/08// PY - 2013 DA - Aug 2013 SP - 117 EP - 122 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 439 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Finite element method KW - Mathematical models KW - Fuels KW - Nuclear fuels KW - Radioactive materials KW - Temperature KW - Simulation KW - Grains KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1475531699?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Three+dimensional+calculations+of+the+effective+Kapitza+resistance+of+UO%282%29+grain+boundaries+containing+intergranular+bubbles&rft.au=Millett%2C+Paul+C%3BTonks%2C+Michael+R%3BChockalingam%2C+K%3BZhang%2C+Yongfeng%3BBiner%2C+S+B&rft.aulast=Millett&rft.aufirst=Paul&rft.date=2013-08-01&rft.volume=439&rft.issue=1-3&rft.spage=117&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Number of references - 20 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Finite element method; Mathematical models; Fuels; Radioactive materials; Nuclear fuels; Temperature; Simulation; Grains ER - TY - JOUR T1 - Organic maturity, elastic properties, and textural characteristics of self resourcing reservoirs AN - 1477831838; 2014-004271 AB - Organic-rich rocks have long been recognized as source rocks for clastic reservoirs, but more recently they have gained importance as reservoirs. However, the processes of kerogen maturation and hydrocarbon transport and storage are still poorly understood. Some empirical relations have been developed to relate the increase in elastic modulus with increasing maturity. A systematic study of the cause for this increase in elastic modulus is still lacking, and information about seismic and mechanical properties of kerogen and its alteration products is scarce. Consequently, any rock models must rely on anecdotal or extrapolated data about various types of kerogen. Our experiments address this paucity of data by grain-scale modulus measurements coupled with careful field emission scanning electron microscopy (FESEM) microstructural assessments on organic rich Bakken formation shale samples with a range of maturities. Carefully acquired and detailed FESEM images help to understand the microstructural controls on the reduced (nanoindentation) Young's modulus of minerals, clay particles, and kerogen matter with maturity in naturally matured shales. Using hydrous pyrolysis, we further investigate the cause for change in modulus with maturity and the mobility of the pyrolized organic matter. In naturally matured shale samples, we find a direct relationship between the reduced Young's modulus and the total organic content or hydrogen index. Significant lowering of Young's modulus is observed after hydrous pyrolysis due to bitumen generation. We measured modulus of the extruded bitumen to be less than 2 GPa. The presence of bitumen comingled with the organic matter also reduces its modulus, in excess of 30%. These results are critical to help understand how organic-rich sediments evolve with burial and maturation. The modulus measurements can be used for modeling modulus variations during maturation. JF - Geophysics AU - Zargari, Saeed AU - Prasad, Manika AU - Mba, Kenechukwu C AU - Mattson, Earl D Y1 - 2013/07// PY - 2013 DA - July 2013 SP - D223 EP - D235 PB - Society of Exploration Geophysicists, Tulsa, OK VL - 78 IS - 4 SN - 0016-8033, 0016-8033 KW - United States KW - Poisson's ratio KW - maturity KW - elastic properties KW - microstructure KW - techniques KW - elastic constants KW - reservoir rocks KW - sedimentary rocks KW - upper Paleozoic KW - pyrolysis KW - thermal maturity KW - Bakken Formation KW - textures KW - shale KW - Paleozoic KW - petroleum accumulation KW - bitumens KW - physical properties KW - organic compounds KW - testing KW - kerogen KW - clastic rocks KW - SEM data KW - instruments KW - Young's modulus KW - 29A:Economic geology, geology of energy sources KW - 06A:Sedimentary petrology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1477831838?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Geophysics&rft.atitle=Organic+maturity%2C+elastic+properties%2C+and+textural+characteristics+of+self+resourcing+reservoirs&rft.au=Zargari%2C+Saeed%3BPrasad%2C+Manika%3BMba%2C+Kenechukwu+C%3BMattson%2C+Earl+D&rft.aulast=Zargari&rft.aufirst=Saeed&rft.date=2013-07-01&rft.volume=78&rft.issue=4&rft.spage=D223&rft.isbn=&rft.btitle=&rft.title=Geophysics&rft.issn=00168033&rft_id=info:doi/10.1190%2Fgeo2012-0431.1 L2 - http://library.seg.org/journal/gpysa7 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data from GeoScienceWorld, Alexandria, VA, United States | Reference includes data supplied by Society of Exploration Geophysicists, Tulsa, OK, United States N1 - Date revised - 2014-01-01 N1 - Number of references - 26 N1 - PubXState - OK N1 - Document feature - illus. incl. 3 tables N1 - Last updated - 2014-01-16 N1 - CODEN - GPYSA7 N1 - SubjectsTermNotLitGenreText - Bakken Formation; bitumens; clastic rocks; elastic constants; elastic properties; instruments; kerogen; maturity; microstructure; organic compounds; Paleozoic; petroleum accumulation; physical properties; Poisson's ratio; pyrolysis; reservoir rocks; sedimentary rocks; SEM data; shale; techniques; testing; textures; thermal maturity; United States; upper Paleozoic; Young's modulus DO - http://dx.doi.org/10.1190/geo2012-0431.1 ER - TY - JOUR T1 - Scenario clustering and dynamic probabilistic risk assessment AN - 1464503214; 18726571 AB - A challenging aspect of dynamic methodologies for probabilistic risk assessment (PRA), such as the Dynamic Event Tree (DET) methodology, is the large number of scenarios generated for a single initiating event. Such large amounts of information can be difficult to organize for extracting useful information. Furthermore, it is not often sufficient to merely calculate a quantitative value for the risk and its associated uncertainties. The development of risk insights that can increase system safety and improve system performance requires the interpretation of scenario evolutions and the principal characteristics of the events that contribute to the risk. For a given scenario dataset, it can be useful to identify the scenarios that have similar behaviors (i.e., identify the most evident classes), and decide for each event sequence, to which class it belongs (i.e., classification). It is shown how it is possible to accomplish these two objectives using the Mean-Shift Methodology (MSM). The MSM is a kernel-based, non-parametric density estimation technique that is used to find the modes of an unknown data distribution. The algorithm developed finds the modes of the data distribution in the state space corresponding to regions with highest data density as well as grouping the scenarios generated into clusters based on scenario temporal similarities. The MSM is illustrated using the data generated by a DET algorithm for the analysis of a simple level/temperature controller and reactor vessel auxiliary cooling system. JF - Reliability Engineering & System Safety AU - Mandelli, D AU - Yilmaz, A AU - Aldemir, T AU - Metzroth, K AU - Denning, R AD - Nuclear Engineering Program, The Ohio State University, Columbus, OH, United States, diego.mandelli@inl.gov Y1 - 2013/07// PY - 2013 DA - Jul 2013 SP - 146 EP - 160 PB - Elsevier B.V., The Boulevard Langford Lane Kidlington Oxford OX5 1GB United Kingdom VL - 115 SN - 0951-8320, 0951-8320 KW - Risk Abstracts; Health & Safety Science Abstracts KW - Risk assessment KW - Safety engineering KW - Classification KW - Temperature KW - Cooling systems KW - R2 23020:Technological risks KW - H 0500:General UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1464503214?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Reliability+Engineering+%26+System+Safety&rft.atitle=Scenario+clustering+and+dynamic+probabilistic+risk+assessment&rft.au=Mandelli%2C+D%3BYilmaz%2C+A%3BAldemir%2C+T%3BMetzroth%2C+K%3BDenning%2C+R&rft.aulast=Mandelli&rft.aufirst=D&rft.date=2013-07-01&rft.volume=115&rft.issue=&rft.spage=146&rft.isbn=&rft.btitle=&rft.title=Reliability+Engineering+%26+System+Safety&rft.issn=09518320&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-11-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Risk assessment; Classification; Safety engineering; Temperature; Cooling systems ER - TY - JOUR T1 - Extension-driven right-lateral shear in the Centennial shear zone adjacent to the eastern Snake River plain, Idaho AN - 1400616331; 2013-054285 AB - We evaluate global positioning system (GPS) surface velocities and gravitational potential energy (GPE) variations to assess the causes of right-lateral shear in the Centennial shear zone, a NE-trending accommodation zone between the extensional Centennial tectonic belt (Montana-Idaho) and volcanic terrain of the eastern Snake River Plain (Idaho). We test the hypothesized "bookshelf" faulting model and find that the normal faults in the Centennial tectonic belt do not accommodate distributed dextral shear. Instead, GPS data reveal that rapid extension in the Centennial tectonic belt adjacent to the much more slowly deforming region of the Snake River Plain drives right-lateral shear between them at rates of 0.3-1.5 mm yr (super -1) . GPE variations support gravitational collapse at a higher rate in the Centennial tectonic belt due to higher topography than in eastern Snake River Plain, which has lower GPE variations due to its low-relief, flat topography and a denser crustal composition. Surface velocity gradients observed in GPS data across the 40-45-km-wide Centennial shear zone reveal distributed deformation due to strike-slip faulting, distributed simple shear, regional-scale rotation, or some combination thereof. In the Centennial shear zone, the fastest lateral shearing is closest to the Yellowstone Plateau, where fault plane solutions with components of right-lateral strike slip are documented within a NE-trending zone of seismicity. Here, two Basin and Range normal faults have Holocene and late Pleistocene slip along their segments that suggest they each may have linked under right-lateral shear. We also propose that right-lateral strike-slip motion may be accommodated on existing NE-trending faults. JF - Lithosphere AU - Payne, S J AU - McCaffrey, R AU - Kattenhorn, S A Y1 - 2013/06/03/ PY - 2013 DA - 2013 Jun 03 SP - 407 EP - 419 PB - Geological Society of America, Boulder, CO VL - 5 IS - 4 SN - 1941-8264, 1941-8264 KW - Basin and Range Province KW - right-lateral faults KW - lateral faults KW - mechanism KW - strike-slip faults KW - Madison County Montana KW - Beaverhead Mountains KW - rotation KW - Centennial Mountains KW - active faults KW - seismotectonics KW - faults KW - bookshelf faulting KW - systems KW - Fremont County Idaho KW - North America KW - Idaho KW - shear zones KW - Quaternary KW - lithosphere KW - Centennial shear zone KW - paleomagnetism KW - Lemhi Range KW - southwestern Montana KW - Pleistocene KW - accommodation zones KW - Snake River plain KW - causes KW - United States KW - Global Positioning System KW - density KW - strain KW - oblique-slip faults KW - shear stress KW - block structures KW - Holocene KW - extension tectonics KW - Bitterroot Range KW - eastern Idaho KW - upper Pleistocene KW - Clark County Idaho KW - Cenozoic KW - neotectonics KW - seismicity KW - normal faults KW - velocity KW - probability KW - tectonics KW - gravitational potential energy KW - variance analysis KW - statistical analysis KW - U. S. Rocky Mountains KW - deformation KW - Montana KW - Lost River Range KW - Beaverhead County Montana KW - Rocky Mountains KW - energy KW - 16:Structural geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1400616331?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Lithosphere&rft.atitle=Extension-driven+right-lateral+shear+in+the+Centennial+shear+zone+adjacent+to+the+eastern+Snake+River+plain%2C+Idaho&rft.au=Payne%2C+S+J%3BMcCaffrey%2C+R%3BKattenhorn%2C+S+A&rft.aulast=Payne&rft.aufirst=S&rft.date=2013-06-03&rft.volume=5&rft.issue=4&rft.spage=407&rft.isbn=&rft.btitle=&rft.title=Lithosphere&rft.issn=19418264&rft_id=info:doi/10.1130%2FL200.1 L2 - http://lithosphere.gsapubs.org/ LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. Reference includes data from GeoScienceWorld, Alexandria, VA, United States | Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2013-01-01 N1 - Number of references - 64 N1 - PubXState - CO N1 - Document feature - illus. incl. 3 tables, geol. sketch maps N1 - Last updated - 2013-08-15 N1 - SubjectsTermNotLitGenreText - accommodation zones; active faults; Basin and Range Province; Beaverhead County Montana; Beaverhead Mountains; Bitterroot Range; block structures; bookshelf faulting; causes; Cenozoic; Centennial Mountains; Centennial shear zone; Clark County Idaho; deformation; density; eastern Idaho; energy; extension tectonics; faults; Fremont County Idaho; Global Positioning System; gravitational potential energy; Holocene; Idaho; lateral faults; Lemhi Range; lithosphere; Lost River Range; Madison County Montana; mechanism; Montana; neotectonics; normal faults; North America; oblique-slip faults; paleomagnetism; Pleistocene; probability; Quaternary; right-lateral faults; Rocky Mountains; rotation; seismicity; seismotectonics; shear stress; shear zones; Snake River plain; southwestern Montana; statistical analysis; strain; strike-slip faults; systems; tectonics; U. S. Rocky Mountains; United States; upper Pleistocene; variance analysis; velocity DO - http://dx.doi.org/10.1130/L200.1 ER - TY - JOUR T1 - Strength loss in MA-MOX green pellets from radiation damage to binders AN - 1475532713; 18796720 AB - The fracture strength of green Minor Actinides (MA)-MOX pellets containing 75 wt.% DUO(2), 20 wt.% PuO(2), 3 wt.% AmO(2) and 2 wt.% NpO(2) was studied as a function of storage time, after mixing with the binder and before sintering, to test the effect of radiation damage on binders. Fracture strength degraded continuously over the 10 days of the study for all three binders studied: PEG binder (Carbowax 8000), microcrystalline wax (Mobilcer X) and styrene-acrylic copolymer (Duramax B1022) but the fracture strength of Duramax B1022 degraded the least. For instance, for several hours after mixing Carbowax 8000 with MA-MOX, the fracture strength of a pellet was reasonably high and pellets were easily handled without breaking but the pellets were too weak to handle after 10 days. Strength measured using diametral compression test showed that strength degradation was more rapid in pellets containing 1.0 wt.% Carbowax PEG 8000 compared to those containing only 0.2 wt.%, suggesting that irradiation not only left the binder less effective but also reduced the pellet strength. In contrast the strength of pellets containing Duramax B1022 degraded very little over the 10 days period. It was suggested that the styrene portion present in the Duramax B1022 copolymer provided the radiation resistance. JF - Journal of Nuclear Materials AU - Lessing, Paul A AU - Roger Cannon, W AU - Egeland, Gerald W AU - Zuck, Larry D AU - Jewell, James K AU - Akers, Douglas W AU - Groenewold, Gary S AD - Idaho National Laboratory, Idaho Falls, ID 83415, United States, wrogercannon@gmail.com Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 229 EP - 234 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 437 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Storage KW - Styrene KW - Degradation KW - Irradiation KW - Radioactive materials KW - Actinides KW - ENA 14:Radiological Contamination UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1475532713?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Strength+loss+in+MA-MOX+green+pellets+from+radiation+damage+to+binders&rft.au=Lessing%2C+Paul+A%3BRoger+Cannon%2C+W%3BEgeland%2C+Gerald+W%3BZuck%2C+Larry+D%3BJewell%2C+James+K%3BAkers%2C+Douglas+W%3BGroenewold%2C+Gary+S&rft.aulast=Lessing&rft.aufirst=Paul&rft.date=2013-06-01&rft.volume=437&rft.issue=1-3&rft.spage=229&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Number of references - 17 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Styrene; Storage; Degradation; Irradiation; Radioactive materials; Actinides ER - TY - JOUR T1 - Simulation of Flow-Induced Vibration on a Multi-Plate Experiment in Water AN - 1429876807; 18278357 AB - The qualification and characterization of flat-plate nuclear fuels involves in-reactor experimentation at representative flow velocities and channel dimensions. It is known that flat-plates are susceptible to mechanical excitation under periodic loadings. In the presence of leading edge effects or bluff-body wakes that impart energy of a periodic nature, the vibrational modes of the plates may be matched, inducing resonance and amplification of the deflections and stresses. In the worst case, these stresses may lead to high-cycle fatigue failure of either the fuel plates or other components. Due to the complex nature of the flows, empirical formulae do not have the fidelity to capture the interaction between components or the exacerbation of the vibration due to resonance effects. To accurately capture this level of interaction, the computation of the comprehensive flow field must be directly coupled to the computation of the mechanical domain. In the past, this type of analysis was too complex to perform on a meaningful scale. This paper describes a computational analysis of a complex, multi-plate, multi-channel experiment that exhibits vortex shedding and fluid/structure interaction, and explores the sensitivity of the computations to various computational and mechanical parameters. JF - Transactions of the American Nuclear Society AU - Jones, W F AU - Snow, S D AU - Marcum, W D AU - Howard, T AD - Idaho National Laboratory, Idaho Falls, ID, 83415 Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 1046 EP - 1049 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Channels KW - Computational fluid dynamics KW - Computation KW - Plates KW - Fatigue failure KW - Vibration KW - Deflection KW - Stresses UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1429876807?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Simulation+of+Flow-Induced+Vibration+on+a+Multi-Plate+Experiment+in+Water&rft.au=Jones%2C+W+F%3BSnow%2C+S+D%3BMarcum%2C+W+D%3BHoward%2C+T&rft.aulast=Jones&rft.aufirst=W&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=1046&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-09-01 N1 - Number of references - 3 N1 - Last updated - 2014-04-08 ER - TY - JOUR T1 - Benchmark Evaluation of HTR-PROTEUS Pebble Bed Experimental Program Critical Core Loadings AN - 1429867997; 18278264 AB - PROTEUS was a zero-power research reactor made up of a graphite annulus with central cylindrical cavity at the Paul Scherrer Institute (PSI) in Switzerland. The graphite annulus remained basically the same for all experimental programs while the contents of the central cavity were adjusted according to the type of reactor being investigated. From 1992 to 1996, PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PROTEUS. Seventeen critical configurations were assembled and various reactor physics experiments were performed, including criticality, differential and integral control rod and safety rod worths, kinetics, reaction rates, water ingress effects, and small sample reactivity effects. JF - Transactions of the American Nuclear Society AU - Bess John, D AU - Montierth Leland, M AU - Hanlon, David AD - Idaho National Laboratory, P O Box 1625, Idaho Falls, ID 83415 Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 693 EP - 696 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Nuclear reactors KW - Graphite KW - Proteus KW - Pebble bed KW - Nuclear reactor components KW - Nuclear engineering KW - Holes UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1429867997?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Benchmark+Evaluation+of+HTR-PROTEUS+Pebble+Bed+Experimental+Program+Critical+Core+Loadings&rft.au=Bess+John%2C+D%3BMontierth+Leland%2C+M%3BHanlon%2C+David&rft.aulast=Bess+John&rft.aufirst=D&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=693&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-09-01 N1 - Number of references - 12 N1 - Last updated - 2013-09-05 ER - TY - JOUR T1 - Introduction to the Advanced Fuel Cycle Cost Basis for Economic Analysis of Proposed Nuclear Fuel Cycles AN - 1429867140; 18278107 AB - "Level Playing Field" economic analysis of proposed nuclear fuel cycles requires the use of consistent and vetted unit cost values for the various fuel cycle steps along with the necessary material balance data. For the last eight years the USDOE Office of Nuclear Energy and Technology (NE) has funded the development of a Fuel Cycle Cost Basis Report and Data Base for use by fuel cycle analysts. The last such document was published in December of 2009 as INL/EXT-07-12107 and is available on the Web at URL: www.inl.gov/technicalpublications/Documents/453 6700.pdf. This abstract describes a new document which updates the above-cited 2009 report for those fuel cycle steps and reactor types for which the economics has changed or that did not appear in the 2009 version. A comprehensive table at the beginning of the report lists the 30+ fuel cycle modules and the selected ranges for their unit costs. When combined with reactor characteristics and fuel cycle material balance information, the levelized unit cost of electricity (LCOE) can be calculated for candidate fuel cycles. This unit cost information for fuel cycle steps and reactor/transmuter systems will be used in the ongoing evaluation of fuel cycle options selected by DOE-NE for future research and development funding. The same data should also prove useful to nuclear industry and academic economic analysts and to non-proliferation policy analysts in the National Nuclear Security Administration (NNSA). JF - Transactions of the American Nuclear Society AU - Dixon, Brent AU - Williams, Kent AD - Idaho National Laboratory, PO Box 1625, Idaho Falls ID 83415 Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 97 EP - 98 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Cost engineering KW - Nuclear reactors KW - Fuel cycles KW - Cost analysis KW - Economic analysis KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1429867140?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Introduction+to+the+Advanced+Fuel+Cycle+Cost+Basis+for+Economic+Analysis+of+Proposed+Nuclear+Fuel+Cycles&rft.au=Dixon%2C+Brent%3BWilliams%2C+Kent&rft.aulast=Dixon&rft.aufirst=Brent&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=97&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-09-01 N1 - Number of references - 2 N1 - Last updated - 2014-04-08 ER - TY - JOUR T1 - DEVELOPMENT OF UNCERTAINTY MODULES FOR A SUB-CHANNEL CODE AN - 1429866934; 18278339 AB - New developed uncertainty modules are embedded into the UCT which is capable of providing uncertainty margins and comparisons. These uncertainty modules show the best estimate code results with uncertainty bounds, code to data comparisons (bias), code to data uncertainty comparisons (coverage ratio) and precision of code predictions (standard deviation). They are flexible to use various probability distributions (flat, binominal, triangle, etc), sampling functions (such as Wilks and Guba) and log files for tracking the computer runs. These modules are tested with the NUPEC's BFBT database, including critical power data (Table II). The results of new uncertainty modules are promising for using various applications and further development. JF - Transactions of the American Nuclear Society AU - Aydogan, Fatih AD - University of Idaho, Center for Advanced Energy Studies (CAES), 995 University Blvd , Idaho Falls, ID 83401 fatih@uidaho.edu Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 984 EP - 987 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Uncertainty KW - Databases KW - Standard deviation KW - Modules KW - Tables (data) KW - Sampling KW - Tracking KW - Mathematical analysis UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1429866934?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=DEVELOPMENT+OF+UNCERTAINTY+MODULES+FOR+A+SUB-CHANNEL+CODE&rft.au=Aydogan%2C+Fatih&rft.aulast=Aydogan&rft.aufirst=Fatih&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=984&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-09-01 N1 - Number of references - 6 N1 - Last updated - 2014-04-08 ER - TY - JOUR T1 - Development of Fuel Shuffling Module for PHISICS AN - 1429866835; 18278301 AB - The main purpose of this paper is to present the new module in the PHISICS toolkit, SHUFFLE. The functionality of the module has been tested simulating the previously explained benchmark. Since the goal of this paper focuses on me new tool only, the convergence of the code has not been pushed to exactly match the benchmark results. A previous publication has already demonstrated the convergence trend for this particular benchmark. The reported case shows that all the modules in PHISICS work with a multi-cycle simulation. SHUFFLE was designed to give PHISICS the ability to simulate fuel management and perform multi-cycle simulations. Since this capability had been unavailable before, it is an important development step for PHISICS to become a valuable tool also for fuel cycle studies and optimization. Currently it is possible to perform multi cycle full core analysis including accounting for the thermal-hydraulic feedback by the coupling with RELAP-5. PHISICS and RELAP5-3D are moving toward becoming a full nuclear reactor design and analysis tool. JF - Transactions of the American Nuclear Society AU - Mabe, Allan AU - Alfonsi, Andrea AU - Rabiti, Cristian AU - Epiney, Aaron AU - Lineberry, Michael AD - Idaho State University, Dept Of Nuclear Engineering: 921 S 8th Ave, Pocatello, ID 83209-8060 Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 837 EP - 840 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Convergence KW - Modules KW - Fuels KW - Simulation KW - Benchmarking KW - Accounting KW - Tools KW - Optimization UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1429866835?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Development+of+Fuel+Shuffling+Module+for+PHISICS&rft.au=Mabe%2C+Allan%3BAlfonsi%2C+Andrea%3BRabiti%2C+Cristian%3BEpiney%2C+Aaron%3BLineberry%2C+Michael&rft.aulast=Mabe&rft.aufirst=Allan&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=837&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-09-01 N1 - Number of references - 5 N1 - Last updated - 2013-09-05 ER - TY - JOUR T1 - Extensible Framework for Illustrative Visualization of Time-Varying Flows AN - 1429865622; 18278336 AB - A generalized framework was developed for illustrative visualization of time varying datasets on unstructured meshes. The framework was implemented in MarmotViz, a Para View plug-in, and supports the use of generalized ROI identification algorithms, feature matching and tracking algorithms, and illustrative effects. This implementation incorporated a gradient-based ROI identification routine, and a novel, adaptive, volume-based feature matching algorithm. Several illustrative visualization effects were implemented to demonstrate the use and utility of this framework, including feature coloring, selective visibility, feature smoothing, tube outlines, feature halos, speedlines, and strobe silhouettes. Future work will expand upon the basic algorithms developed here to improve functionality and robustness over a wider range of flow situations. In particular, an event detection scheme would provide the flexibility to better address the complex behavior of features found in modern flow simulations. JF - Transactions of the American Nuclear Society AU - Guillen, D P AU - Rattner, A S AU - Joshi, A AU - Garimella, S AD - Idaho National Laboratory, Idaho Falls, ID, 83415 Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 974 EP - 976 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Halos KW - Flexibility KW - Algorithms KW - Visualization KW - Robustness KW - Tracking KW - Matching KW - Adaptive algorithms UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1429865622?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Extensible+Framework+for+Illustrative+Visualization+of+Time-Varying+Flows&rft.au=Guillen%2C+D+P%3BRattner%2C+A+S%3BJoshi%2C+A%3BGarimella%2C+S&rft.aulast=Guillen&rft.aufirst=D&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=974&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-09-01 N1 - Number of references - 13 N1 - Last updated - 2014-04-08 ER - TY - JOUR T1 - RAVEN: a GUI and an Artificial Intelligence Engine in a Dynamic PRA Framework AN - 1419368083; 18278226 AB - We have presented the advancements in the design and implementation of the RAVEN-Peacock GUI meant to ease the analyst work necessary to generate complex plant models and also to enhance the understanding of plant behavior in accident scenarios. This is realized via a graphical tool that both assists the user generating the plant layout and allows performing an online monitoring of the simulation results. Another step forward in the development of the RAVEN project has been presented here. The preliminary analysis of SVM has revealed a great potentiality in reducing of computational time and increasing the accuracy of failure probability estimation. The implementation of this technique is currently ongoing, and we are planning to illustrate preliminary results during the ANS meeting. JF - Transactions of the American Nuclear Society AU - Rabiti, C AU - Mandelli, D AU - Alfonsi, A AU - Cogliati, J AU - Kinoshita, R AU - Gaston, D AU - Martineau, R AU - Smith, C AD - Idaho National Laboratory, 2525 North Fremont Street, Idaho Falls (ID), Robert.Kinoshita@inl.gov Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 533 EP - 536 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts KW - Artificial intelligence KW - Accidents KW - Occupational safety KW - Simulation KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1419368083?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=RAVEN%3A+a+GUI+and+an+Artificial+Intelligence+Engine+in+a+Dynamic+PRA+Framework&rft.au=Rabiti%2C+C%3BMandelli%2C+D%3BAlfonsi%2C+A%3BCogliati%2C+J%3BKinoshita%2C+R%3BGaston%2C+D%3BMartineau%2C+R%3BSmith%2C+C&rft.aulast=Rabiti&rft.aufirst=C&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=533&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-08-01 N1 - Number of references - 5 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Artificial intelligence; Accidents; Occupational safety; Simulation ER - TY - JOUR T1 - PERFORMING PROBABILISTIC RISK ASSESSMENT THROUGH RAVEN AN - 1419365505; 18278231 AB - In this paper it has been presented RAVEN as a tool to perform dynamic PRA through Monte-Carlo sampling. In particular, the software structure and all the components that are involved in the computation have been presented, including system simulator (i.e., RELAP-7) and the control logic, characterized by a monitoring system and on-line control of selected parameters. An example of PRA analysis has been also presented for a SBO-like case for a simplified PWR loop. The description of the implementation for such case demonstrates how the flexibility of the software framework provides the basic tools to perform Dynamic PRA, uncertainty quantification and plant control. Next capabilities, to be implemented to RAVEN and that are currently under development, include dynamic event tree generation, adaptive sampling and more advanced data mining algorithms. JF - Transactions of the American Nuclear Society AU - Alfonsi, A AU - Rabiti, C AU - Mandelli, D AU - Cogliati, J J AU - Kinoshita, R A AD - Idaho National Laboratory, robert.kinoshita@inl.gov Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 555 EP - 558 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Risk Abstracts KW - Risk assessment KW - Computer programs KW - R2 23010:General: Models, forecasting UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1419365505?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=PERFORMING+PROBABILISTIC+RISK+ASSESSMENT+THROUGH+RAVEN&rft.au=Alfonsi%2C+A%3BRabiti%2C+C%3BMandelli%2C+D%3BCogliati%2C+J+J%3BKinoshita%2C+R+A&rft.aulast=Alfonsi&rft.aufirst=A&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=555&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-08-01 N1 - Number of references - 8 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Risk assessment; Computer programs ER - TY - JOUR T1 - Coupling of RELAP-7 with the Three-Dimensional Kinetics Code RattleSnake AN - 1419358860; 18278308 AB - Steady-state calculation results for coupled calculation of the next generation system safety analysis code, RELAP-7, and the three-dimensional spatial kinetics code, RattleSnake, are presented. The results are compared with those calculated from the RELAP-5 code. The basic framework to perform the coupled calculations has been developed with the Mammoth code. The future work includes extending the framework to perform transient calculations such as reactivity initiated accident calculations. The future work also includes realizing fully coupled calculations of RELAP-7/RattleSnake by integrating all of the physics into one system for better convergence. The thermal-hydraulics calculations can be enhanced through the sub-channel model with mixing or the completely three-dimensional computational fluid dynamics model. Correspondingly, the capability of RattleSnake can be fully explored with the fuel-resolved transport calculation. JF - Transactions of the American Nuclear Society AU - Zhang, Hongbin AU - Wang, Yaqi AU - Zou, Ling AU - Andrs, David AU - Zhao, Haihua AU - Martineau, Richard AD - Idaho National Laboratory, 2525 N Freemont Ave , Idaho Falls, ID 83415, Yaqi.Wang@inl.gov Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 863 EP - 865 PB - American Nuclear Society, Inc. VL - 108 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts KW - Accidents KW - Kinetics KW - Occupational safety KW - Fluid dynamics KW - H 2000:Transportation UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1419358860?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Coupling+of+RELAP-7+with+the+Three-Dimensional+Kinetics+Code+RattleSnake&rft.au=Zhang%2C+Hongbin%3BWang%2C+Yaqi%3BZou%2C+Ling%3BAndrs%2C+David%3BZhao%2C+Haihua%3BMartineau%2C+Richard&rft.aulast=Zhang&rft.aufirst=Hongbin&rft.date=2013-06-01&rft.volume=108&rft.issue=&rft.spage=863&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-08-01 N1 - Number of references - 8 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Accidents; Kinetics; Occupational safety; Fluid dynamics ER - TY - JOUR T1 - A risk-informed approach to safety margins analysis AN - 1372686739; 18197576 AB - What differentiates the RISMC approach from traditional probabilistic risk assessment (PRA) is the concept of a safety margin. In PRA, a safety metric such as core damage frequency (CDF) is generally estimated using static fault-tree and event-tree models. However, it is not possible to estimate how close we are to physical safety limits (say peak clad temperature) for most accident sequences described in the PRA. JF - Nuclear Engineering International AU - Smith, C AU - Mandelli, D AD - Idaho National Laboratory (INL), 2525 Freemont Ave., Idaho Falls (ID), 83415, USA, curtis.smith@inl.gov Y1 - 2013/06// PY - 2013 DA - Jun 2013 SP - 38 EP - 40 PB - Wilmington Publishing Ltd., Wilmington House, Church Hill, Wilmington Dartford Kent DA2 7EF United Kingdom VL - 58 IS - 707 SN - 0029-5507, 0029-5507 KW - Risk Abstracts; Health & Safety Science Abstracts; Environment Abstracts KW - Risk assessment KW - Accidents KW - Safety engineering KW - Temperature KW - H 8000:Radiation Safety/Electrical Safety KW - R2 23010:General: Models, forecasting KW - ENA 02:Toxicology & Environmental Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372686739?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+International&rft.atitle=A+risk-informed+approach+to+safety+margins+analysis&rft.au=Smith%2C+C%3BMandelli%2C+D&rft.aulast=Smith&rft.aufirst=C&rft.date=2013-06-01&rft.volume=58&rft.issue=707&rft.spage=38&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+International&rft.issn=00295507&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-07-01 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Risk assessment; Accidents; Safety engineering; Temperature ER - TY - JOUR T1 - A parallel, fully coupled, fully implicit solution to reactive transport in porous media using the preconditioned Jacobian-free Newton-Krylov method AN - 1739085291; 2015-116191 AB - Modeling large multicomponent reactive transport systems in porous media is particularly challenging when the governing partial differential algebraic equations (PDAEs) are highly nonlinear and tightly coupled due to complex nonlinear reactions and strong solution-media interactions. Here we present a preconditioned Jacobian-Free Newton-Krylov (JFNK) solution approach to solve the governing PDAEs in a fully coupled and fully implicit manner. A well-known advantage of the JFNK method is that it does not require explicitly computing and storing the Jacobian matrix during Newton nonlinear iterations. Our approach further enhances the JFNK method by utilizing physics-based, block preconditioning and a multigrid algorithm for efficient inversion of the preconditioner. This preconditioning strategy accounts for self- and optionally, cross-coupling between primary variables using diagonal and off-diagonal blocks of an approximate Jacobian, respectively. Numerical results are presented demonstrating the efficiency and massive scalability of the solution strategy for reactive transport problems involving strong solution-mineral interactions and fast kinetics. We found that the physics-based, block preconditioner significantly decreases the number of linear iterations, directly reducing computational cost; and the strongly scalable algebraic multigrid algorithm for approximate inversion of the preconditioner leads to excellent parallel scaling performance. Abstract Copyright (2013) Elsevier, B.V. JF - Advances in Water Resources AU - Guo, Luanjing AU - Huang, Hai AU - Gaston, Derek R AU - Permann, Cody J AU - Andrs, David AU - Redden, George D AU - Lu, Chuan AU - Fox, Don T AU - Fujita, Yoshiko Y1 - 2013/03// PY - 2013 DA - March 2013 SP - 101 EP - 108 PB - Elsevier, Oxford VL - 53 SN - 0309-1708, 0309-1708 KW - bedrock KW - data processing KW - coupling KW - porous materials KW - equations KW - solution KW - simulation KW - chemical reactions KW - water-rock interaction KW - transport KW - parallel processing KW - reactive transport KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1739085291?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Advances+in+Water+Resources&rft.atitle=A+parallel%2C+fully+coupled%2C+fully+implicit+solution+to+reactive+transport+in+porous+media+using+the+preconditioned+Jacobian-free+Newton-Krylov+method&rft.au=Guo%2C+Luanjing%3BHuang%2C+Hai%3BGaston%2C+Derek+R%3BPermann%2C+Cody+J%3BAndrs%2C+David%3BRedden%2C+George+D%3BLu%2C+Chuan%3BFox%2C+Don+T%3BFujita%2C+Yoshiko&rft.aulast=Guo&rft.aufirst=Luanjing&rft.date=2013-03-01&rft.volume=53&rft.issue=&rft.spage=101&rft.isbn=&rft.btitle=&rft.title=Advances+in+Water+Resources&rft.issn=03091708&rft_id=info:doi/10.1016%2Fj.advwatres.2012.10.010 L2 - http://www.sciencedirect.com/science/journal/03091708 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2015-01-01 N1 - Number of references - 33 N1 - Document feature - illus. incl. 3 tables N1 - Last updated - 2015-12-04 N1 - SubjectsTermNotLitGenreText - bedrock; chemical reactions; coupling; data processing; equations; parallel processing; porous materials; reactive transport; simulation; solution; transport; water-rock interaction DO - http://dx.doi.org/10.1016/j.advwatres.2012.10.010 ER - TY - JOUR T1 - Switchable polarity solvents as draw solutes for forward osmosis AN - 1291599360; 17640140 AB - Switchable polarity solvents (SPS), mixtures of carbon dioxide, water, and tertiary amines, are presented as viable forward osmosis (FO) draw solutes allowing a novel SPS FO process. In this study substantial osmotic strengths of SPS are measured with freezing point osmometry and were demonstrated to induce competitive fluxes at high salt concentrations on a laboratory-scale FO unit utilizing a flat sheet cellulose triacetate (CTA) membrane. Under the experimental conditions the SPS degrades the CTA membrane; however experiments with polyamide reverse osmosis (RO) membranes display stability towards SPS. Once the draw is diluted the major fraction of the switchable polarity solvent can be mechanically separated from the purified water after polar to nonpolar phase shift induced by introduction of 1atm carbon dioxide to 1atm of air or nitrogen with mild heating. Trace amounts of SPS can be removed from the separated water with RO in a process that avoids solution concentration polarization. The separated nonpolar phase can be regenerated to a full strength draw and recycled with the re-addition of 1atm of carbon dioxide. JF - Desalination AU - Stone, Mark L AU - Rae, Cathy AU - Stewart, Frederick F AU - Wilson, Aaron D AD - Idaho National Laboratory, P.O. Box 1625 MS 2208, Idaho Falls, ID 83415-2208, USA, aaron.wilson@inl.gov Y1 - 2013/03/01/ PY - 2013 DA - 2013 Mar 01 SP - 124 EP - 129 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 312 SN - 0011-9164, 0011-9164 KW - Environment Abstracts; Oceanic Abstracts; ASFA 2: Ocean Technology Policy & Non-Living Resources; Water Resources Abstracts KW - Reverse osmosis KW - Cellulose KW - Solutes KW - Membranes KW - Solvents KW - Reverse Osmosis KW - Polarization KW - Amines KW - Osmosis KW - Salts KW - Strength KW - Freezing point KW - Polarity KW - Carbon dioxide KW - Carbon Dioxide KW - Nitrogen KW - SW 5010:Network design KW - Q2 09148:Palaeo-studies KW - O 2050:Chemical Oceanography KW - ENA 01:Air Pollution UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1291599360?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Awaterresources&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Desalination&rft.atitle=Switchable+polarity+solvents+as+draw+solutes+for+forward+osmosis&rft.au=Stone%2C+Mark+L%3BRae%2C+Cathy%3BStewart%2C+Frederick+F%3BWilson%2C+Aaron+D&rft.aulast=Stone&rft.aufirst=Mark&rft.date=2013-03-01&rft.volume=312&rft.issue=&rft.spage=124&rft.isbn=&rft.btitle=&rft.title=Desalination&rft.issn=00119164&rft_id=info:doi/10.1016%2Fj.desal.2012.07.034 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Solutes; Reverse osmosis; Freezing point; Cellulose; Solvents; Amines; Polarization; Carbon dioxide; Osmosis; Salts; Membranes; Nitrogen; Strength; Polarity; Reverse Osmosis; Carbon Dioxide DO - http://dx.doi.org/10.1016/j.desal.2012.07.034 ER - TY - JOUR T1 - An initial study of hexavalent phosphazene salts as draw solutes in forward osmosis AN - 1291599356; 17640139 AB - Two novel multi-valent salts based on phosphazene chemistry have been synthesized and characterized as forward osmosis (FO) draw solutes. Commercially obtained hexachlorocyclotriphosphazene was reacted with the sodium salt of 4-ethylhydroxybenzoate to yield hexa(4-ethylcarboxylatophenoxy)phosphazene. Hydrolysis, followed by neutralization with NaOH or LiOH of the resulting acidic moieties yielded water soluble sodium and lithium phosphazene salts, respectively. Degrees of dissociation were determined through osmometry over the range of 0.05-0.5m, giving degrees of 3.08-4.95 per mole, suggesting a high osmotic potential. The Li salt was found to be more ionized in solution than the sodium salt, and this was reflected in FO experiments where the Li salt gave higher initial fluxes (7l/m2h) as compared to the sodium salt (6l/m2h) at identical 0.067m draw solution concentrations at 30 degree C. Longer term experiments revealed no detectable degradation of the salts; however some hydrolysis of the cellulose acetate membrane was observed, presumably due to the pH of the phosphazene salt draw solution (pH=8). JF - Desalination AU - Stone, Mark L AU - Wilson, Aaron D AU - Harrup, Mason K AU - Stewart, Frederick F AD - Idaho National Laboratory, Idaho Falls, ID 83425-2208, USA, Frederick.Stewart@INL.gov Y1 - 2013/03/01/ PY - 2013 DA - 2013 Mar 01 SP - 130 EP - 136 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 312 SN - 0011-9164, 0011-9164 KW - Environment Abstracts; Oceanic Abstracts; ASFA 2: Ocean Technology Policy & Non-Living Resources; Water Resources Abstracts KW - Degradation KW - Cellulose KW - Solutes KW - Neutralization KW - pH KW - Lithium KW - Membranes KW - Cellulose Acetate Membranes KW - Hydrogen Ion Concentration KW - Hydrolysis KW - Osmosis KW - Sodium KW - Salts KW - Dissociation KW - Acetate KW - SW 5010:Network design KW - Q2 09181:General KW - ENA 16:Renewable Resources-Water KW - O 2050:Chemical Oceanography UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1291599356?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Awaterresources&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Desalination&rft.atitle=An+initial+study+of+hexavalent+phosphazene+salts+as+draw+solutes+in+forward+osmosis&rft.au=Stone%2C+Mark+L%3BWilson%2C+Aaron+D%3BHarrup%2C+Mason+K%3BStewart%2C+Frederick+F&rft.aulast=Stone&rft.aufirst=Mark&rft.date=2013-03-01&rft.volume=312&rft.issue=&rft.spage=130&rft.isbn=&rft.btitle=&rft.title=Desalination&rft.issn=00119164&rft_id=info:doi/10.1016%2Fj.desal.2012.09.030 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-01 N1 - Number of references - 1 N1 - Last updated - 2016-02-04 N1 - SubjectsTermNotLitGenreText - Solutes; Acetate; Dissociation; Cellulose; Hydrolysis; Lithium; Osmosis; Sodium; Salts; Membranes; Degradation; Neutralization; pH; Cellulose Acetate Membranes; Hydrogen Ion Concentration DO - http://dx.doi.org/10.1016/j.desal.2012.09.030 ER - TY - JOUR T1 - Geologic CO (sub 2) input into ground water and the atmosphere, Soda Springs, ID, USA AN - 1316374677; 2013-026806 AB - A set of CO (sub 2) flux, geochemical, and hydrologic measurement techniques was used to characterize the source of and quantify gaseous and dissolved CO (sub 2) discharges from the area of Soda Springs, southeastern Idaho. An eddy covariance system was deployed for approximately one month near a bubbling spring and measured net CO (sub 2) fluxes from -74 to 1147gm (super -2) d (super -1) . An inversion of measured eddy covariance CO (sub 2) fluxes and corresponding modeled source weight functions mapped the surface CO (sub 2) flux distribution within and quantified CO (sub 2) emission rate (24.9t d (super -1) ) from a 0.05km (super 2) area surrounding the spring. Soil CO (sub 2) fluxes (<1 to 52,178gm (super -2) d (super -1) ) were measured within a 0.05km (super 2) area of diffuse degassing using the accumulation chamber method. The estimated CO (sub 2) emission rate from this area was 49t d (super -1) . A carbon mass balance approach was used to estimate dissolved CO (sub 2) discharges from contributing sources at nine springs and the Soda Springs geyser. Total dissolved inorganic carbon (as CO (sub 2) ) discharge for all sampled groundwater features was 57.1t d (super -1) . Of this quantity, approximately 3% was derived from biogenic carbon dissolved in infiltrating groundwater, 35% was derived from carbonate mineral dissolution within the aquifer(s), and 62% was derived from deep source(s). Isotopic compositions of helium (1.74-2.37 R (sub a) ) and deeply derived carbon (delta (super 13) C nearly equal 3 ppm) suggested contribution of volatiles from mantle and carbonate sources. Assuming that the deeply derived CO (sub 2) discharge estimated for sampled groundwater features ( approximately 35t d (super -1) ) is representative of springs throughout the study area, the total rate of deeply derived CO (sub 2) input into the groundwater system within this area could be approximately 350t d (super -1) , similar to CO (sub 2) emission rates from a number of quiescent volcanoes. Abstract Copyright (2013) Elsevier, B.V. JF - Chemical Geology AU - Lewicki, J L AU - Hilley, G E AU - Dobeck, L AU - McLing, T L AU - Kennedy, B M AU - Bill, M AU - Marino, B D V Y1 - 2013/02/15/ PY - 2013 DA - 2013 Feb 15 SP - 61 EP - 70 PB - Elsevier, Amsterdam VL - 339 SN - 0009-2541, 0009-2541 KW - United States KW - hydrogeology KW - Caribou County Idaho KW - ground water KW - carbon dioxide KW - volatilization KW - mass balance KW - carbon KW - springs KW - discharge KW - chemical composition KW - geochemistry KW - degassing KW - covariance analysis KW - Idaho KW - decarbonation KW - Soda Springs Idaho KW - statistical analysis KW - emissivity KW - thermal waters KW - gases KW - models KW - mathematical methods KW - volcanoes KW - hot springs KW - soil gases KW - 21:Hydrogeology KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1316374677?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Chemical+Geology&rft.atitle=Geologic+CO+%28sub+2%29+input+into+ground+water+and+the+atmosphere%2C+Soda+Springs%2C+ID%2C+USA&rft.au=Lewicki%2C+J+L%3BHilley%2C+G+E%3BDobeck%2C+L%3BMcLing%2C+T+L%3BKennedy%2C+B+M%3BBill%2C+M%3BMarino%2C+B+D+V&rft.aulast=Lewicki&rft.aufirst=J&rft.date=2013-02-15&rft.volume=339&rft.issue=&rft.spage=61&rft.isbn=&rft.btitle=&rft.title=Chemical+Geology&rft.issn=00092541&rft_id=info:doi/10.1016%2Fj.chemgeo.2012.06.013 L2 - http://www.sciencedirect.com/science/journal/00092541 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2013-01-01 N1 - Number of references - 82 N1 - Document feature - illus. incl. 3 tables, geol. sketch map N1 - Last updated - 2013-03-14 N1 - CODEN - CHGEAD N1 - SubjectsTermNotLitGenreText - carbon; carbon dioxide; Caribou County Idaho; chemical composition; covariance analysis; decarbonation; degassing; discharge; emissivity; gases; geochemistry; ground water; hot springs; hydrogeology; Idaho; mass balance; mathematical methods; models; Soda Springs Idaho; soil gases; springs; statistical analysis; thermal waters; United States; volatilization; volcanoes DO - http://dx.doi.org/10.1016/j.chemgeo.2012.06.013 ER - TY - JOUR T1 - Active tectonics of northwestern U.S. inferred from GPS-derived surface velocities AN - 1416686852; 2013-061301 AB - Surface velocities derived from GPS observations from 1993 to 2011 at several hundred sites across the deforming northwestern United States are used to further elucidate the region's active tectonics. The new velocities reveal that the clockwise rotations, relative to North America, seen in Oregon and western Washington from earlier GPS observations, continue to the east to include the Snake River Plain of Idaho and south into the Basin and Range of northern Nevada. Regional-scale rotation is attributed to gravitationally driven extension in the Basin and Range and Pacific-North America shear transferred through the Walker Lane belt aided by potentially strong pinning below the Idaho Batholith. The large rotating section comprising eastern Oregon displays very low internal deformation rates despite seismological evidence for a thin crust, warm mantle, organized mantle flow, and elevated topography. The observed disparity between mantle and surface kinematics suggests that either little stress acts between them (low basal shear) or that the crust is strong relative to the mantle. The rotation of the Oregon block impinges on Washington across the Yakima fold-thrust belt where shortening occurs in a closing-fan style. Elastic fault locking at the Cascadia subduction zone is reevaluated using the GPS velocities and recently published uplift rates. The 18 year GPS and 80 year leveling data can both be matched with a common locking model suggesting that the locking has been stable over many decades. The rate of strain accumulation is consistent with hundreds of years between great subduction events. Abstract Copyright (2012), . American Geophysical Union. All Rights Reserved. JF - Journal of Geophysical Research AU - McCaffrey, Robert AU - King, Robert W AU - Payne, Suzette J AU - Lancaster, Matthew Y1 - 2013/02// PY - 2013 DA - February 2013 SP - 709 EP - 723 PB - American Geophysical Union, Washington, DC VL - 118 IS - 2 SN - 0148-0227, 0148-0227 KW - United States KW - North America KW - Idaho KW - Global Positioning System KW - Washington KW - Basin and Range Province KW - lithosphere KW - continental crust KW - deformation KW - Oregon KW - continental lithosphere KW - neotectonics KW - seismicity KW - Western U.S. KW - tectonics KW - active faults KW - Snake River plain KW - seismotectonics KW - faults KW - crust KW - 16:Structural geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1416686852?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Geophysical+Research&rft.atitle=Active+tectonics+of+northwestern+U.S.+inferred+from+GPS-derived+surface+velocities&rft.au=McCaffrey%2C+Robert%3BKing%2C+Robert+W%3BPayne%2C+Suzette+J%3BLancaster%2C+Matthew&rft.aulast=McCaffrey&rft.aufirst=Robert&rft.date=2013-02-01&rft.volume=118&rft.issue=2&rft.spage=709&rft.isbn=&rft.btitle=&rft.title=Journal+of+Geophysical+Research&rft.issn=01480227&rft_id=info:doi/10.1029%2F2012JB009473 L2 - http://www.agu.org/journals/jgr/ LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data from John Wiley & Sons, Chichester, United Kingdom N1 - Date revised - 2013-01-01 N1 - Number of references - 22 N1 - PubXState - DC N1 - Document feature - illus. incl. sketch maps N1 - Last updated - 2015-02-19 N1 - SubjectsTermNotLitGenreText - active faults; Basin and Range Province; continental crust; continental lithosphere; crust; deformation; faults; Global Positioning System; Idaho; lithosphere; neotectonics; North America; Oregon; seismicity; seismotectonics; Snake River plain; tectonics; United States; Washington; Western U.S. DO - http://dx.doi.org/10.1029/2012JB009473 ER - TY - JOUR T1 - INVESTIGATION OF FISSION PRODUCT TRANSPORT INTO ZEOLITE-A FOR PYROPROCESSING WASTE MINIMIZATION AN - 1323252119; 17791743 AB - Methods to improve fission product salt sorption into zeolite-A have been investigated in an effort to reduce waste associated with the electrochemical treatment of spent nuclear fuel. It was demonstrated that individual fission product chloride salts were absorbed by zeolite-A in a solid-state process. As a result, recycling of LiCl-KCl appears feasible via adding a zone-freezing technique to the current treatment process. Ternary salt molten-state experiments showed the limiting kinetics of CsCl and SrCl(2) sorption into the zeolite. CsCl sorption occurred rapidly relative to SrCl(2) with no observed dependence on zeolite particle size, while SrCl(2) sorption was highly dependent on particle size. The application of experimental data to a developed reaction-diffusion-based sorption model yielded diffusivities of 8.04 X 10(-6) and 4.04 X 10(-7) cm(2)/s for CsCl and SrCl(2), respectively. Additionally, the chemical reaction term in the developed model was found to be insignificant compared to the diffusion term. JF - Nuclear Technology AU - Allensworth, James R AU - Simpson, Michael F AU - Yim, Man-Sung AU - Phongikaroon, Supathorn AD - North Carolina State University, Department of Nuclear Engineering CBox 7909, Raleigh, North Carolina, michael.simpson@inl.gov Y1 - 2013/02// PY - 2013 DA - Feb 2013 SP - 337 EP - 348 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 181 IS - 2 SN - 0029-5450, 0029-5450 KW - Pollution Abstracts KW - Fission products KW - Particle size KW - Sorption KW - Salts KW - Chemical reactions KW - Nuclear fuels KW - Chlorides KW - Zeolites KW - Waste management KW - P 4000:WASTE MANAGEMENT UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1323252119?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Apollution&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Technology&rft.atitle=INVESTIGATION+OF+FISSION+PRODUCT+TRANSPORT+INTO+ZEOLITE-A+FOR+PYROPROCESSING+WASTE+MINIMIZATION&rft.au=Allensworth%2C+James+R%3BSimpson%2C+Michael+F%3BYim%2C+Man-Sung%3BPhongikaroon%2C+Supathorn&rft.aulast=Allensworth&rft.aufirst=James&rft.date=2013-02-01&rft.volume=181&rft.issue=2&rft.spage=337&rft.isbn=&rft.btitle=&rft.title=Nuclear+Technology&rft.issn=00295450&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-04-01 N1 - Number of references - 13 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Particle size; Fission products; Salts; Sorption; Chemical reactions; Nuclear fuels; Chlorides; Zeolites; Waste management ER - TY - JOUR T1 - Cold water injection effects in fractured reservoirs AN - 1553084939; 2014-064162 AB - Cold water injection in a geothermal reservoir can increase injectivity through dilation of preexisting fracture flow paths or by inducing growth of fractures. To elucidate how cold water injection may affect a fractured rock reservoir, we show results of calculations of fluid flow, heat transport and geomechanical deformation for thermal stimulation of simplified models of fractured rock reservoirs. When fractures are assumed dilate freely, results demonstrate that many fold increases in injectivity can occur. For realistic flow and heat transport parameters, where the number of interconnected fractures that conduct flow away from a well is on the order of 10 to 100, a 30-day cold water injection causes increases in injectivity of a factor of 2 to 4, with larger increases associated with fewer fractures. Changes of similar magnitude were observed in the cold water injection tests at the Hellisheidi field, SW-Iceland. The large changes in fractured rock transmissivity that can be produced by contraction of cooled rock can easily dominate the effect of increasing fluid viscosity, and dramatically decrease the pressure gradient required to accommodate a specified flow. The region of dramatically increased transmissivity effectively reproduces the effect of a very large well bore, with a flat spot in the pressure vs. distance curve that extends through the cooled region. The change in the wellhead pressure with time is thus a function of (1) the shape of the initial fluid potential drawdown curve and (2) the rate of propagation of the cooling front along that curve. As with well tests in fractured rock, the injectivity changes associated with thermal stimulation can therefore be diagnostic of those conditions. The assumption that reservoir fractures may dilate freely is most likely to hold when propagation of the thermal front is slow and the duration of the thermal stimulation is short. In that case, the stress formerly supported by the contracting region may be entirely supported by the surrounding rock. Where that stress is transmitted to a more distal region of the fractured rock reservoir, however, permeability may decline. 2-D and 3-D simulations of coupled fluid flow, heat transport and geomechanical deformation are presented to illustrate how injectivity may be affected when such stresses are considered. JF - Abstracts with Programs - Geological Society of America AU - Plummer, Mitchell AU - Smith, Katherine AU - Podgorney, Robert K AU - Anonymous Y1 - 2013 PY - 2013 DA - 2013 SP - 859 PB - Geological Society of America (GSA), Boulder, CO VL - 45 IS - 7 SN - 0016-7592, 0016-7592 KW - 29A:Economic geology, geology of energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1553084939?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Cold+water+injection+effects+in+fractured+reservoirs&rft.au=Plummer%2C+Mitchell%3BSmith%2C+Katherine%3BPodgorney%2C+Robert+K%3BAnonymous&rft.aulast=Plummer&rft.aufirst=Mitchell&rft.date=2013-01-01&rft.volume=45&rft.issue=7&rft.spage=859&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ L2 - https://gsa.confex.com/gsa/2013AM/webprogram/Paper234057.html LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2013 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2014-01-01 N1 - PubXState - CO N1 - Last updated - 2014-08-14 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Theoretical fracturing and power production from low permeability tuffs in the Snake River plain, southern Idaho AN - 1549618443; 2014-059947 AB - The potential for using geothermal reservoirs as a contribution to base-load energy is becoming increasingly feasible economically and technologically with the continuing development of enhanced, or engineered, geothermal systems (EGS). EGS augments natural thermal reservoirs within the crust that lack either the permeability or hydrothermal water necessary for power production using traditional geothermal power plants. Typically, high-temperature systems are found in regions of high strain rates and geothermal gradients, such as the basin and range province. EGS has the potential to access the stored heat in regions with lower strain rates and non-ideal primary or secondary permeability. Recent boreholes drilled to a depth of 2 km in the hotspot project have reached massive welded ashflow tuffs that potentially represent one flow unit. Borehole scans reveal very little fracturing, supporting the use of the tuff unit as an EGS test site. We present an analytical solution using production targets of approximately 63 l/s (1000 gpm) for 20 years that provides theoretical fracture spacing, apertures, flow path lengths, and production rates that an EGS system would need to produce power in the snake river plain (SRP) in southern Idaho. The solution does not consider the thermomechanical properties of the reservoir that control the propagation of fractures through the unit at a given depth, thus we consider prior testing performed on tuffs. Together, the model and tuff properties allow us to give a range of possible reservoir geometries to be expected when fracturing the unit, as well as an estimate of potential power output. The work presented here provides a low-cost and quick exploratory method of testing regions for their potential as enhanced geothermal fields using basic geologic information of the site. JF - Abstracts with Programs - Geological Society of America AU - Moody, Alex C AU - Fairley, Jerry P AU - Plummer, Mitchell A AU - Anonymous Y1 - 2013 PY - 2013 DA - 2013 SP - 774 PB - Geological Society of America (GSA), Boulder, CO VL - 45 IS - 7 SN - 0016-7592, 0016-7592 KW - 05A:Igneous and metamorphic petrology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1549618443?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Theoretical+fracturing+and+power+production+from+low+permeability+tuffs+in+the+Snake+River+plain%2C+southern+Idaho&rft.au=Moody%2C+Alex+C%3BFairley%2C+Jerry+P%3BPlummer%2C+Mitchell+A%3BAnonymous&rft.aulast=Moody&rft.aufirst=Alex&rft.date=2013-01-01&rft.volume=45&rft.issue=7&rft.spage=774&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ L2 - https://gsa.confex.com/gsa/2013AM/webprogram/Paper233453.html LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2013 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2014-01-01 N1 - PubXState - CO N1 - Last updated - 2014-07-31 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Constraining multicomponent equilibrium geothermometer temperature estimates using laboratory experiments; preliminary results AN - 1549617592; 2014-059946 AB - More accurate chemical geothermometers can potentially decrease economic risk associated with geothermal prospecting by providing more reliable temperature estimates. However, when applying the suite of traditional geothermometers, diverse temperature estimates result because 1) each geothermometer utilize only a subset of the available water chemical composition data, and 2) they do not explicitly account for many composition altering physicochemical processes along its flow path. Multicomponent equilibrium geothermometry (MEG) has an advantage over traditional geothermometers in its ability to use a complete chemical analysis of a water sample for temperature prediction. Nevertheless, the uncertainty associated with MEG estimated temperature relies in part on a correct understanding of mineral-water interactions occurring at depth in reservoir and proper quantification of composition altering processes along its flow path. Laboratory experiments simulating reservoir conditions (e.g., T and P) is one approach for understanding mineral-water interactions and quantifying composition altering processes occurring during fluid migration. As part of project to develop approaches for MEG, we are conducting a series of water-rock interaction experiments at 200-250 degrees C using 1-liter stirred Parr bench-top reactors. Representative reservoir rock samples from Raft River Geothermal area in Idaho were crushed to different grain-sized fractions and reacted separately with synthetic geothermal fluids for >2 months. Fluid samples were extracted at different times to evaluate the chemical evolution of system and to test the accuracy and uncertainty in temperature estimates with MEG. Preliminary results based on water compositions in association with likely mineral assemblage in these experiments demonstrate that with the increasing extent of reaction over time, the temperatures estimated with MEG approach the experimental temperature with decreasing uncertainty. Additional experiments with the goal of simulating some of the composition altering chemical and physical processes are planned. We expect that these water-rock interaction experiments simulating reservoir and flow path processes will allow us to constrain MEG temperature estimates with reduced and quantifiable uncertainty. JF - Abstracts with Programs - Geological Society of America AU - Neupane, Ghanashyam AU - Smith, Robert W AU - McLing, Travis L AU - Palmer, Carl D AU - Smith, William W AU - Anonymous Y1 - 2013 PY - 2013 DA - 2013 SP - 774 PB - Geological Society of America (GSA), Boulder, CO VL - 45 IS - 7 SN - 0016-7592, 0016-7592 KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1549617592?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Constraining+multicomponent+equilibrium+geothermometer+temperature+estimates+using+laboratory+experiments%3B+preliminary+results&rft.au=Neupane%2C+Ghanashyam%3BSmith%2C+Robert+W%3BMcLing%2C+Travis+L%3BPalmer%2C+Carl+D%3BSmith%2C+William+W%3BAnonymous&rft.aulast=Neupane&rft.aufirst=Ghanashyam&rft.date=2013-01-01&rft.volume=45&rft.issue=7&rft.spage=774&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ L2 - https://gsa.confex.com/gsa/2013AM/webprogram/Paper229946.html LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2013 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2014-01-01 N1 - PubXState - CO N1 - Last updated - 2014-07-31 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Two distinct estimates of last flacial maximum climate on the Pikes Peak Massif, Front Range, central Colorado, using numerically modeled 2D paleoglacier reconstructions AN - 1545409503; 2014-054929 AB - The Pikes Peak Massif, located at the southern end of the Colorado Front Range, contains extensive geomorphic evidence of Pleistocene glaciation. Down valley ice limits are recorded by well-preserved moraines in valleys radiating from the 4000 m-high summit ridge of the massif. Valleys on NW-to-NE aspects of the massif hosted five individual valley glaciers up to 3.7 km long. On the SW- and S-facing slopes there is evidence for a more extensive Pleistocene transection glacier system terminating in three valleys, with a maximum glacier length of 8.6 km. To better understand the chronology of glaciation of the massif, and investigate the climate responsible, we used a dual component 2-D energy/mass balance and ice flow model developed by Phillips and Plummer (2003). Initial modeling was undertaken varying only year-round temperatures from the modern, not changing precipitation or seasonality. We were unable to fit the best-preserved and most conspicuous moraines in each valley with a single temperature depression, but were able to match all of these moraines and less conspicuous moraine sets in several valleys with one-of-two temperature depressions. A temperature depression of 5.5 degrees C from modern fits the distinct terminal moraines in North French Creek on the NE side of the massif and in the East and West Forks of Beaver Creek on the SW side. A temperature depression of 4.25 degrees C fits the most distinct moraine in the Bottomless Pit immediately N of the summit of Pike Peak as well a smaller unnamed glacial valley on the NW side of the massif, as well as smaller moraine complexes up valley from the main moraines in the French and Beaver Creek valleys. We have found no clear evidence of moraines that might have been associated with a 5.5 degrees C temperature depression in the three valleys where the main moraines were well fit by the lesser temperature depression. It appears, then, that there is moraine evidence for two distinct advances or standstills of ice on the massif associated with different temperature depressions. No numerical data is available for the moraines and as a result, we are uncertain whether the two represent separate glaciations (Bull Lake and Pinedale) or whether they date from a single glacial period (Pinedale). JF - Abstracts with Programs - Geological Society of America AU - Crawford, Edward E AU - Leonard, Eric M AU - Plummer, Mitchell A AU - Anonymous Y1 - 2013 PY - 2013 DA - 2013 SP - 346 PB - Geological Society of America (GSA), Boulder, CO VL - 45 IS - 7 SN - 0016-7592, 0016-7592 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1545409503?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Two+distinct+estimates+of+last+flacial+maximum+climate+on+the+Pikes+Peak+Massif%2C+Front+Range%2C+central+Colorado%2C+using+numerically+modeled+2D+paleoglacier+reconstructions&rft.au=Crawford%2C+Edward+E%3BLeonard%2C+Eric+M%3BPlummer%2C+Mitchell+A%3BAnonymous&rft.aulast=Crawford&rft.aufirst=Edward&rft.date=2013-01-01&rft.volume=45&rft.issue=7&rft.spage=346&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ L2 - https://gsa.confex.com/gsa/2013AM/finalprogram/abstract_232204.htm LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2013 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2014-01-01 N1 - PubXState - CO N1 - Last updated - 2014-07-17 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Cosmogenic exposure dating and numerical modeling of the Pleistocene South Fork Deep Creek Valley Glacier, northern Absaroka Mountains, Montana AN - 1545409260; 2014-054932 AB - During the last Pleistocene glaciation, several ranges in the Northern Rocky Mountains were occupied by valley glaciers. Geologic dating of the record of these glaciers provides new insight on the timing of glaciation, and provides the chronological framework for comparisons of paleoclimate across the Northern Rocky Mountains. Boulder samples along the left lateral sector of the terminal moraine in South Fork Deep Creek Canyon were collected for cosmogenic (super 10) Be exposure dating and yielded an error-weighted mean exposure age of 16.7+ or -0.7 ka. This exposure age is consistent with others from terminal moraines elsewhere in the northern Absaroka Range, and consistent with previous suggestions that mountain glaciers in this region began retreating as many as 3 kyr after the onset of global deglaciation. To infer climate conditions that accompanied the last glaciation in the northern Absaroka Range, a 2-D, numerical glacier model was applied to three glacial valleys. Modeling experiments indicate that, if precipitation was at or near modern, then a temperature depression of approximately 8 degrees C accompanied the time of moraine deposition. These model results along with others from ranges elsewhere in the Rocky Mountains reveal a trend of greater temperature depressions with latitude during the last glaciation, consistent with regional-scale climate models. JF - Abstracts with Programs - Geological Society of America AU - Spears, Alec J AU - Laabs, Benjamin J C AU - Leonard, Eric M AU - Plummer, Mitchell A AU - Caffee, Marc W AU - Anonymous Y1 - 2013 PY - 2013 DA - 2013 SP - 346 PB - Geological Society of America (GSA), Boulder, CO VL - 45 IS - 7 SN - 0016-7592, 0016-7592 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1545409260?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Cosmogenic+exposure+dating+and+numerical+modeling+of+the+Pleistocene+South+Fork+Deep+Creek+Valley+Glacier%2C+northern+Absaroka+Mountains%2C+Montana&rft.au=Spears%2C+Alec+J%3BLaabs%2C+Benjamin+J+C%3BLeonard%2C+Eric+M%3BPlummer%2C+Mitchell+A%3BCaffee%2C+Marc+W%3BAnonymous&rft.aulast=Spears&rft.aufirst=Alec&rft.date=2013-01-01&rft.volume=45&rft.issue=7&rft.spage=346&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ L2 - https://gsa.confex.com/gsa/2013AM/finalprogram/abstract_228592.htm LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2013 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2014-01-01 N1 - PubXState - CO N1 - Last updated - 2014-07-17 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - A cosmogenic (super 10) Be chronology of the last Pleistocene glaciation in the northernmost U.S. Rocky Mountains and inferences of climate change AN - 1535205662; 2014-041228 AB - The northern sector of the U.S. Rocky Mountains hosted numerous mountain glacier systems during the last Pleistocene glaciation. Although many glaciers in the northernmost ranges of this region interacted with southern lobes of the North American ice sheets, some formed discrete valley and piedmont glaciers. The records of these glaciers provide an opportunity to understand climate change during the culmination of the last glaciation and subsequent deglaciation, especially in places where the timing of mountain glaciation can be precisely limited. In the Lewis Range of northwestern Montana, a discrete glacier occupied the east flowing Cut Bank Creek valley and deposited a broad, hummocky terminal moraine on the piedmont. Cosmogenic (super 10) Be exposure ages of this moraine indicate that the glacier was at or near its maximum extent for as many as 4000 yr after the start of global deglaciation, similar to glaciers in other ranges of the northern Rocky Mountains. Temperature and precipitation at the time of terminal-moraine deposition were assessed using a 2-d, numerical model of steady state mass balance and ice flow. Model results indicate that, if precipitation was near modern at the time of moraine deposition, then a temperature depression of ca. 9 degrees C sustained the glacier at its maximum extent. This result is in contrast to the >10 degrees C temperature depression and strong reduction in precipitation during the Last Glacial Maximum yielded by regional and global-scale climate models. However, the regional signal of a late onset of deglaciation in the northern Rocky Mountains relative to North American ice sheets has been explained by increased precipitation in the region after the Last Glacial Maximum. We propose that moderate cooling compared to the Last Glacial Maximum and near-modern precipitation were sufficient to sustain mountain glaciers at their maximum extent until as late as 15 ka, and that retreat of mountain glaciers was initiated by regional warming. JF - Abstracts with Programs - Geological Society of America AU - Laabs, Benjamin J C AU - Leonard, Eric AU - Plummer, Mitchell A AU - Quirk, Brendon J AU - Wistort, Zackery P AU - Caffee, M W AU - Anonymous Y1 - 2013 PY - 2013 DA - 2013 SP - 259 PB - Geological Society of America (GSA), Boulder, CO VL - 45 IS - 7 SN - 0016-7592, 0016-7592 KW - 24:Quaternary geology KW - 03:Geochronology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1535205662?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=A+cosmogenic+%28super+10%29+Be+chronology+of+the+last+Pleistocene+glaciation+in+the+northernmost+U.S.+Rocky+Mountains+and+inferences+of+climate+change&rft.au=Laabs%2C+Benjamin+J+C%3BLeonard%2C+Eric%3BPlummer%2C+Mitchell+A%3BQuirk%2C+Brendon+J%3BWistort%2C+Zackery+P%3BCaffee%2C+M+W%3BAnonymous&rft.aulast=Laabs&rft.aufirst=Benjamin+J&rft.date=2013-01-01&rft.volume=45&rft.issue=7&rft.spage=259&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ L2 - https://gsa.confex.com/gsa/2013AM/webprogram/Paper230885.html LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2013 annual meeting & exposition N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2014-01-01 N1 - PubXState - CO N1 - Last updated - 2014-06-13 N1 - CODEN - GAAPBC ER - TY - JOUR T1 - Multidimensional multiphysics simulation of TRISO particle fuel AN - 1524419947; 19562534 AB - Multidimensional multiphysics analysis of TRISO-coated particle fuel using the BISON finite element nuclear fuels code is described. The governing equations and material models applicable to particle fuel and implemented in BISON are outlined. Code verification based on a recent IAEA benchmarking exercise is described, and excellent comparisons are reported. Multiple TRISO-coated particles of increasing geometric complexity are considered. The code's ability to use the same algorithms and models to solve problems of varying dimensionality from 1 D through 3D is demonstrated. The code provides rapid solutions of 1 D spherically symmetric and 2D axially symmetric models, and its scalable parallel processing capability allows for solutions of large, complex 3D models. Additionally, the flexibility to easily include new physical and material models and straightforward ability to couple to lower length scale simulations makes BISON a powerful tool for simulation of coated-particle fuel. Future code development activities and potential applications are identified. JF - Journal of Nuclear Materials AU - Hales, J D AU - Williamson, R L AU - Novascone, S R AU - Perez, D M AU - Spencer, B W AU - Pastore, G AD - Fuel Modeling and Simulation, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3840, United States, Richard.Williamson@inl.gov Y1 - 2013 PY - 2013 DA - 2013 SP - 531 EP - 543 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 443 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Fuels KW - Nuclear fuels KW - Radioactive materials KW - Simulation KW - Particulates KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1524419947?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Multidimensional+multiphysics+simulation+of+TRISO+particle+fuel&rft.au=Hales%2C+J+D%3BWilliamson%2C+R+L%3BNovascone%2C+S+R%3BPerez%2C+D+M%3BSpencer%2C+B+W%3BPastore%2C+G&rft.aulast=Hales&rft.aufirst=J&rft.date=2013-01-01&rft.volume=443&rft.issue=1-3&rft.spage=531&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2013.07.070 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-05-01 N1 - Number of references - 44 N1 - Last updated - 2015-04-02 N1 - SubjectsTermNotLitGenreText - Fuels; Radioactive materials; Nuclear fuels; Simulation; Particulates DO - http://dx.doi.org/10.1016/j.jnucmat.2013.07.070 ER - TY - JOUR T1 - Assessment of structures and stabilities of defect clusters and surface energies predicted by nine interatomic potentials for UO sub(2) AN - 1524415971; 19562479 AB - The irradiation in nuclear reactors creates many point defects and defect clusters in uranium dioxide (UO sub(2)) and their evolution severely degrades the thermal and mechanical properties of the nuclear fuels. Previously many empirical interatomic potentials have been developed for modeling defect production and evolution in UO sub(2). However, the properties of defect clusters and extended defects are usually not fitted into these potentials. In this work nine interatomic potentials for UO sub(2) are examined by using molecular statics and molecular dynamics to assess their applicability in predicting the properties of various types of defect clusters in UO sub(2). The binding energies and structures for these defect clusters have been evaluated for each potential. In addition, the surface energies of voids of different radii and (110) flat surfaces predicted by these potentials are also evaluated. It is found that both good agreement and significant discrepancies exist for these potentials in predicting these properties. For oxygen interstitial clusters, these potentials predict significantly different defect cluster structures and stabilities; For defect clusters consisting of both uranium and oxygen defects, the prediction is in better agreement; The surface energies predicted by these potentials have significant discrepancies, and some of them are much higher than the experimentally measured values. The results from this work can provide insight on interpreting the outcome of atomistic modeling of defect production using these potentials and may provide guidelines for choosing appropriate potential models to study problems of interest in UO sub(2). JF - Journal of Nuclear Materials AU - Taller, Stephen A AU - Bai, Xian-Ming AD - School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907, United States, xianming.bai@inl.gov Y1 - 2013 PY - 2013 DA - 2013 SP - 84 EP - 98 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 443 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Prediction KW - Oxygen KW - Nuclear reactors KW - Energy KW - Uranium KW - Irradiation KW - Guidelines KW - Nuclear fuels KW - Radioactive materials KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1524415971?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Assessment+of+structures+and+stabilities+of+defect+clusters+and+surface+energies+predicted+by+nine+interatomic+potentials+for+UO+sub%282%29&rft.au=Taller%2C+Stephen+A%3BBai%2C+Xian-Ming&rft.aulast=Taller&rft.aufirst=Stephen&rft.date=2013-01-01&rft.volume=443&rft.issue=1-3&rft.spage=84&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2013.06.038 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-05-01 N1 - Number of references - 55 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Prediction; Oxygen; Nuclear reactors; Irradiation; Uranium; Energy; Radioactive materials; Nuclear fuels; Guidelines DO - http://dx.doi.org/10.1016/j.jnucmat.2013.06.038 ER - TY - JOUR T1 - Prediction of effects of acetogens on hot spring biogeochemistry AN - 1492586337; 2014-005816 AB - Acetogens are a broad category of obligately anaerobic bacteria that are found in a variety of ecosystems and are able to use diverse electron donors and acceptors. Activity of acetogens has been studied in many terrestrial environments, but the activity of acetogens in hot spring environments is not well understood. For this reason, acetogens in hot spring may have a wider impact on hot spring geochemical cycles and microbial populations, beyond just acetogenic activity. One method to predict the impacts of versatile metabolisms on the flow of energy and material through microbial systems is metabolic stoichiometric modeling, which extracts systemic information from molecular-level network structure and conservation relationships, depending on electron donors and acceptors in the growth environment. To test this hypothesis, an initial model has been constructed from the annotated genome of the well-studied acetogen, Moorella thermoacetica, and the output data have been sorted against various cellular strategies, including maximal efficiency of biomass yield per substrate, and substrate consumption in the presence of high exogenous concentrations of produced metabolites. Output from such models has successfully predicted substrate concentrations that yield elevated ethanol production, as opposed to acetate, when M. thermoacetica was grown on CO (sub 2) and H (sub 2.) This research has shown the utility of metabolic modeling in predicting electron donor and acceptor use and production of organic acids and alcohol in the M. thermoacetica. These types of models will help to predict the effects of acetogenic activity on the overall biogeochemistry in hot spring environments. JF - Mineralogical Magazine AU - Lee, Brady D AU - Aston, John E AU - Lee, Michelle H AU - Apel, William A AU - Anonymous Y1 - 2013 PY - 2013 DA - 2013 SP - 1564 PB - Mineralogical Society, London VL - 77 IS - 5 SN - 0026-461X, 0026-461X KW - biomass KW - metabolism KW - biochemistry KW - ecosystems KW - hydrochemistry KW - thermal waters KW - ground water KW - anaerobic taxa KW - bacteria KW - Moorella thermoacetica KW - springs KW - hot springs KW - acetogens KW - geochemistry KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1492586337?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Mineralogical+Magazine&rft.atitle=Prediction+of+effects+of+acetogens+on+hot+spring+biogeochemistry&rft.au=Lee%2C+Brady+D%3BAston%2C+John+E%3BLee%2C+Michelle+H%3BApel%2C+William+A%3BAnonymous&rft.aulast=Lee&rft.aufirst=Brady&rft.date=2013-01-01&rft.volume=77&rft.issue=5&rft.spage=1564&rft.isbn=&rft.btitle=&rft.title=Mineralogical+Magazine&rft.issn=0026461X&rft_id=info:doi/10.1180%2Fminmag.2013.077.5.12 L2 - http://www.minersoc.org/pages/e_journals/minmag.html LA - English DB - GeoRef N1 - Conference title - Goldschmidt 2013 N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Abstract, Copyright, Mineralogical Society of Great Britain and Ireland N1 - Date revised - 2014-01-01 N1 - Last updated - 2014-01-30 N1 - SubjectsTermNotLitGenreText - acetogens; anaerobic taxa; bacteria; biochemistry; biomass; ecosystems; geochemistry; ground water; hot springs; hydrochemistry; metabolism; Moorella thermoacetica; springs; thermal waters DO - http://dx.doi.org/10.1180/minmag.2013.077.5.12 ER - TY - JOUR T1 - Multiscale development of a fission gas thermal conductivity model: Coupling atomic, meso and continuum level simulations AN - 1475534469; 18796845 AB - Fission gas production and evolution significantly impact the fuel performance, causing swelling, a reduction in the thermal conductivity and fission gas release. However, typical empirical models of fuel properties treat each of these effects separately and uncoupled. Here, we couple a fission gas release model to a model of the impact of fission gas on the fuel thermal conductivity. To quantify the specific impact of grain boundary (GB) bubbles on the thermal conductivity, we use atomistic and mesoscale simulations. Atomistic molecular dynamic simulations were employed to determine the GB thermal resistance. These values were then used in mesoscale heat conduction simulations to develop a mechanistic expression for the effective GB thermal resistance of a GB containing gas bubbles, as a function of the percentage of the GB covered by fission gas. The coupled fission gas release and thermal conductivity model was implemented in Idaho National Laboratory's BISON fuel performance code to model the behavior of a 10-pellet LWR fuel rodlet, showing how the fission gas impacts the UO(2) thermal conductivity. Furthermore, additional BISON simulations were conducted to demonstrate the impact of average grain size on both the fuel thermal conductivity and the fission gas release. JF - Journal of Nuclear Materials AU - Tonks, Michael R AU - Millett, Paul C AU - Nerikar, Pankaj AU - Du, Shiyu AU - Andersson, David AU - Stanek, Christopher R AU - Gaston, Derek AU - Andrs, David AU - Williamson, Richard AD - Fuel Modeling and Simulation, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, United States, Michael.Tonks@inl.gov Y1 - 2013 PY - 2013 DA - 2013 SP - 193 EP - 200 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 440 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Particle size KW - USA, Idaho KW - Thermal conductivity KW - Fuels KW - Nuclear fuels KW - Radioactive materials KW - Simulation KW - Grains KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1475534469?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Multiscale+development+of+a+fission+gas+thermal+conductivity+model%3A+Coupling+atomic%2C+meso+and+continuum+level+simulations&rft.au=Tonks%2C+Michael+R%3BMillett%2C+Paul+C%3BNerikar%2C+Pankaj%3BDu%2C+Shiyu%3BAndersson%2C+David%3BStanek%2C+Christopher+R%3BGaston%2C+Derek%3BAndrs%2C+David%3BWilliamson%2C+Richard&rft.aulast=Tonks&rft.aufirst=Michael&rft.date=2013-01-01&rft.volume=440&rft.issue=1-3&rft.spage=193&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Number of references - 38 N1 - Last updated - 2015-04-02 N1 - SubjectsTermNotLitGenreText - Particle size; Thermal conductivity; Fuels; Radioactive materials; Nuclear fuels; Simulation; Grains; USA, Idaho ER - TY - JOUR T1 - Phase development in a U-7 wt.% Mo vs. Al-7 wt.% Ge diffusion couple AN - 1475531351; 18796923 AB - Fuel development for the Reduced Enrichment for Research and Test Reactors (RERTR) program has demonstrated that U-Mo alloys in contact with Al develop interaction regions with phases that have poor irradiation behavior. The addition of Si to the Al has been considered with positive results. In this study, compositional modification is considered by replacing Si with Ge to determine the effect on the phase development in the system. The microstructural and phase development of a diffusion couple of U-7 wt.% Mo in contact with Al-7 wt.% Ge was examined by transmission electron microscopy, scanning electron microscopy and energy dispersive spectroscopy. The interdif-fusion zone developed a microstructure that included the cubic-UGe(3) phase and amorphous phases. The UGe(3) phase was observed with and without Mo and Al solid solution developing a (U,Mo)(Al,Ge)(3) phase. JF - Journal of Nuclear Materials AU - Perez, E AU - Keiser, D D, Jr AU - Sohn, Y H AD - Nuclear Fuels and Materials Development, Idaho National Laboratory, Box 1625, Idaho Falls, ID 83415, United States, Emmanuel.Perez@inl.gov Y1 - 2013 PY - 2013 DA - 2013 SP - 159 EP - 167 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 441 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Aluminum base alloys KW - Uranium base alloys KW - Al-7Ge KW - U-7Mo KW - Nuclear reactors KW - Energy KW - Fuels KW - Irradiation KW - Microscopy KW - Nuclear fuels KW - Radioactive materials KW - Alloys KW - Diffusion KW - Spectroscopy KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1475531351?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Phase+development+in+a+U-7+wt.%25+Mo+vs.+Al-7+wt.%25+Ge+diffusion+couple&rft.au=Perez%2C+E%3BKeiser%2C+D+D%2C+Jr%3BSohn%2C+Y+H&rft.aulast=Perez&rft.aufirst=E&rft.date=2013-01-01&rft.volume=441&rft.issue=1-3&rft.spage=159&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Number of references - 71 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Irradiation; Fuels; Energy; Radioactive materials; Nuclear fuels; Microscopy; Alloys; Diffusion; Spectroscopy ER - TY - JOUR T1 - The statistical analysis techniques to support the NGNP fuel performance experiments AN - 1475531339; 18796974 AB - This paper describes the development and application of statistical analysis techniques to support the Advanced Gas Reactor (AGR) experimental program on Next Generation Nuclear Plant (NGNP) fuel performance. The experiments conducted in the Idaho National Laboratory's Advanced Test Reactor employ fuel compacts placed in a graphite cylinder shrouded by a steel capsule. The tests are instrumented with thermocouples embedded in graphite blocks and the target quantity (fuel temperature) is regulated by the He-Ne gas mixture that fills the gap volume. Three techniques for statistical analysis, namely control charting, correlation analysis, and regression analysis, are implemented in the NGNP Data Management and Analysis System for automated processing and qualification of the AGR measured data. The neutronic and thermal code simulation results are used for comparative scrutiny. The ultimate objective of this work includes (a) a multi-faceted system for data monitoring and data accuracy testing, (b) identification of possible modes of diagnostics deterioration and changes in experimental conditions, (c) qualification of data for use in code validation, and (d) identification and use of data trends to support effective control of test conditions with respect to the test target. Analysis results and examples given in the paper show the three statistical analysis techniques providing a complementary capability to warn of thermocouple failures. It also suggests that the regression analysis models relating calculated fuel temperatures and thermocouple readings can enable online regulation of experimental parameters (i.e. gas mixture content), to effectively maintain the fuel temperature within a given range. JF - Journal of Nuclear Materials AU - Pham, Binh T AU - Einerson, Jeffrey J AD - Human Factor, Controls and Statistics Department, Nuclear Science and Technology, Idaho National Laboratory, Idaho Falls, ID 83415, United States, Binh.Pham@inl.gov Y1 - 2013 PY - 2013 DA - 2013 SP - 563 EP - 573 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 441 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - USA, Idaho KW - Nuclear reactors KW - Fuels KW - Nuclear fuels KW - Radioactive materials KW - Temperature KW - Simulation KW - Steel KW - Data management KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1475531339?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=The+statistical+analysis+techniques+to+support+the+NGNP+fuel+performance+experiments&rft.au=Pham%2C+Binh+T%3BEinerson%2C+Jeffrey+J&rft.aulast=Pham&rft.aufirst=Binh&rft.date=2013-01-01&rft.volume=441&rft.issue=1-3&rft.spage=563&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Number of references - 20 N1 - Last updated - 2015-04-09 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Fuels; Radioactive materials; Nuclear fuels; Temperature; Simulation; Steel; Data management; USA, Idaho ER - TY - JOUR T1 - Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities AN - 1448219620; 18683169 AB - The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for super(85) Kr and super(129) I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 10 super(5) , iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ) and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs), have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures. JF - Science and Technology of Nucear Installations AU - Soelberg, Nick R AU - Garn, Troy G AU - Greenhalgh, Mitchell R AU - Law, Jack D AU - Jubin, Robert AU - Strachan, Denis M AU - Thallapally, Praveen K AD - Idaho National Laboratory, Idaho Falls, ID 83415, USA, nick.soelberg@inl.gov Y1 - 2013/01// PY - 2013 DA - Jan 2013 PB - Hindawi Publishing Corporation, P.O. Box 3079 Cuyahoga Falls OH 44223 United States VL - 2013 SN - 1687-6075, 1687-6075 KW - Pollution Abstracts KW - Metals KW - Nuclear fuels KW - Radioisotopes KW - Adsorption KW - Emissions KW - Iodine KW - Krypton KW - Zeolites KW - Technology KW - P 0000:AIR POLLUTION UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1448219620?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Apollution&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Science+and+Technology+of+Nucear+Installations&rft.atitle=Radioactive+Iodine+and+Krypton+Control+for+Nuclear+Fuel+Reprocessing+Facilities&rft.au=Soelberg%2C+Nick+R%3BGarn%2C+Troy+G%3BGreenhalgh%2C+Mitchell+R%3BLaw%2C+Jack+D%3BJubin%2C+Robert%3BStrachan%2C+Denis+M%3BThallapally%2C+Praveen+K&rft.aulast=Soelberg&rft.aufirst=Nick&rft.date=2013-01-01&rft.volume=2013&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Science+and+Technology+of+Nucear+Installations&rft.issn=16876075&rft_id=info:doi/10.1155%2F2013%2F702496 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-10-01 N1 - Number of references - 2 N1 - Last updated - 2015-03-20 N1 - SubjectsTermNotLitGenreText - Metals; Nuclear fuels; Emissions; Adsorption; Radioisotopes; Iodine; Krypton; Zeolites; Technology DO - http://dx.doi.org/10.1155/2013/702496 ER - TY - JOUR T1 - When Is the Simple Radiotoxicity Approach Useful for Advanced Fuel Cycle System Assessments Given the Existence of Complex Performance Dose Assessments? AN - 1315705529; 17630479 AB - Engineers often face the general question of which approximations are appropriate for a given analytical task. In particular, when is a simpler model useful if a more complex model also exists? This paper explores this question in the domain of radiotoxicity relative to geologic disposal performance dose assessments. Criterion 1 requires that the simpler approach, radiotoxicity, must be calculated correctly. The concept of ingestion radiotoxic inventories is analogous to the inventory of toxic chemicals in other industries. From a decision analysis perspective, it is also somewhat analogous to the nuclear reactor safety concept of "passive safety. " This paper explains some of the issues in calculating radiotoxicity, motivated by the author's observations of errors in the literature: not accounting for radioactive progeny, misunderstanding natural "ore," and focusing on transuranic (TRU) isotopes without adequate attention to actinide decay products. For example, Th/(233)U fuel cycles do have lower amounts of TRU isotopes than U/(239)Pu fuel cycles, but that does not necessarily mean lower long-term hazard. Criterion 2 requires that the uncertainties in the more complex approach, performance dose assessments, must raise issues for the assessments' intended purposes - in which case, radiotoxic inventory may be of assistance until those issues are resolved. Performance dose assessments were developed for, and are legally the way to show, compliance with regulations, but the uncertainties are large. Less obvious is the degree to which dose assessments are applicable to other purposes - comparing fuel cycle options prior to site selection and showing the safety of a fuel cycle and waste management approach to the public. In the last sense especially, performance dose assessments are analogous to probabilistic risk assessments for nuclear reactor safety. The United States lacks a selected consensus site, selected fuel cycle approach (direct disposal versus recycling), and selected waste form. Thus, the paper does not intend to discuss all the issues with performance dose assessments but rather intends to focus on only those performance dose uncertainties that raise issues when comparing fuel cycles. Uncertainties associated with whether a generic geological environment is attractive or a specific location meets requirements are beyond the scope of this paper. Ingestion radiotoxicity correlates with heat, gamma, and inhalation radiotoxicity. Thus, options that are relatively high in ingestion radiotoxicity tend to be high in other parameters. Therefore, reduction in ingestion radiotoxicity means both that the potential source term for release is lower but also that one driving force for release (heat) is also lower. However, the most important time frames differ as heat is mainly an issue in decades and centuries after reactor discharge, but ingestion radiotoxicity is mainly an issue during longer time periods. Ingestion radiotoxicity points to the importance of actinides in long-term waste management, followed by specific fission products such as (99)Tc, (129)I, (93)Zr, (135)Cs, and (79)Se. TRU isotopes were important in four of five generic geologic environments recently studied independently with used fuel disposal experts as were the same fission products as noted from radiotoxicity - in part because waste assessments must include multiple exposure pathways including human intrusion and drilling into the waste. Dose calculations that were made for used fuel disposal may be misleading if extrapolated to disposal of only the remnants of used fuel separation because the chemistry of waste will differ. Radiotoxicity can be misleading if used to strictly rank order among individual isotopes if a specific disposal option is well known. Hybrid approaches that incorporate radiotoxicity and features of full performance assessments may have value. JF - Nuclear Science and Engineering AU - Piet, Steven J AD - Idaho National Laboratory, Mail Stop 3870, 2525 North Fremont, Idaho Falls, Idaho 83415, pietsteven@hotmail.com Y1 - 2013/01// PY - 2013 DA - Jan 2013 SP - 58 EP - 81 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 173 IS - 1 SN - 0029-5639, 0029-5639 KW - Risk Abstracts KW - USA KW - Isotopes KW - Nuclear reactors KW - Fuels KW - Nuclear fuels KW - Geology KW - Waste disposal KW - Ingestion KW - Waste management KW - Actinides KW - R2 23020:Technological risks UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1315705529?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=When+Is+the+Simple+Radiotoxicity+Approach+Useful+for+Advanced+Fuel+Cycle+System+Assessments+Given+the+Existence+of+Complex+Performance+Dose+Assessments%3F&rft.au=Piet%2C+Steven+J&rft.aulast=Piet&rft.aufirst=Steven&rft.date=2013-01-01&rft.volume=173&rft.issue=1&rft.spage=58&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-10-01 N1 - Number of references - 66 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Isotopes; Nuclear reactors; Fuels; Nuclear fuels; Geology; Waste disposal; Ingestion; Actinides; Waste management; USA ER - TY - JOUR T1 - Linking humans and systems in nuclear power AN - 1291613687; 17650470 AB - For new and upgraded power plants to operate safely and effectively, they must be designed to support the abilities and limitations of systems as well as the people who operate them. While it is increasingly recognized in most industries that the human must be considered a central part of system development, it is not as readily recognized that human factors issues vary widely according to the type of system being developed, and across different parts of the system. For example, the issues involved in developing a highly manual process plant are different than those that require the operator to interface with a plant's automation system. Experience has shown that it is ineffective, risky and expensive to address this part of the design as an afterthought--a common example of bad practice. The risks associated with poor human factors can best be avoided by starting to consider humans as early as possible in the design process, and continuing them throughout. A good management process is needed to address human factors comprehensively and consistently. In most cases, concerted action is needed between different disciplines in the development team and also between teams. JF - Nuclear Engineering International AU - Hugo, J AD - Idaho National Laboratory, USA, jacques.hugo@inl.gov Y1 - 2013/01// PY - 2013 DA - Jan 2013 SP - 20 EP - 23 PB - Wilmington Publishing, Wilmington House Sidcup Kent DA14 5HZ United Kingdom VL - 58 IS - 702 SN - 0029-5507, 0029-5507 KW - Risk Abstracts; Environment Abstracts KW - Power plants KW - Automation KW - Human factors KW - R2 23020:Technological risks KW - ENA 08:International UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1291613687?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ariskabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+International&rft.atitle=Linking+humans+and+systems+in+nuclear+power&rft.au=Hugo%2C+J&rft.aulast=Hugo&rft.aufirst=J&rft.date=2013-01-01&rft.volume=58&rft.issue=702&rft.spage=20&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+International&rft.issn=00295507&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Power plants; Automation; Human factors ER - TY - JOUR T1 - Dynamic analysis of policy drivers for bioenergy commodity markets AN - 1272076193; 4388289 AB - Biomass is increasingly being considered as a feedstock to provide a clean and renewable source of energy in the form of both liquid fuels and electric power. In the United States, the biofuels and biopower industries are regulated by different policies and have different drivers, which impact the maximum price the industries are willing to pay for biomass. This article describes a dynamic computer simulation model that analyzes future behavior of bioenergy feedstock markets given policy and technical options. The model simulates the long-term dynamics of these markets by treating advanced biomass feedstocks as a commodity and projecting the total demand of each industry, as well as the market price over time. The model is used for an analysis of the United States bioenergy feedstock market that projects supply, demand, and market price given three independent buyers: domestic biopower, domestic biofuels, and foreign exports. With base-case assumptions, the biofuels industry is able to dominate the market and meet the federal Renewable Fuel Standard (RFS) targets for advanced biofuels. Further analyses suggest that United States bioenergy studies should include estimates of export demand in their projections, and that GHG-limiting policy would partially shield both industries from export dominance. All rights reserved, Elsevier JF - Energy policy AU - Jeffers, R F AU - Jacobson, J J AU - Searcy, E M AD - Idaho National Laboratory Y1 - 2013/01// PY - 2013 DA - Jan 2013 SP - 249 EP - 263 VL - 52 SN - 0301-4215, 0301-4215 KW - Economics KW - Energy economics KW - Exports KW - Demand KW - Economic models KW - U.S.A. KW - Biofuels KW - Renewable energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1272076193?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aibss&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Energy+policy&rft.atitle=Dynamic+analysis+of+policy+drivers+for+bioenergy+commodity+markets&rft.au=Jeffers%2C+R+F%3BJacobson%2C+J+J%3BSearcy%2C+E+M&rft.aulast=Jeffers&rft.aufirst=R&rft.date=2013-01-01&rft.volume=52&rft.issue=&rft.spage=249&rft.isbn=&rft.btitle=&rft.title=Energy+policy&rft.issn=03014215&rft_id=info:doi/10.1016%2Fj.enpol.2012.08.072 LA - English DB - International Bibliography of the Social Sciences (IBSS) N1 - Date revised - 2013-06-12 N1 - Last updated - 2013-09-16 N1 - SubjectsTermNotLitGenreText - 4254 4025 4246; Biofuels; 3371 3934; 3969 8163; 10876 4271; 4679 6802 12812 6725 4025; 433 293 14 DO - http://dx.doi.org/10.1016/j.enpol.2012.08.072 ER - TY - CPAPER T1 - Approaches for Multicomponent Equilibrium Geothermometry as a Tool for Geothermal Resource Exploration T2 - 2012 American Geophysical Union Fall Meeting (AGU 2012) AN - 1313113767; 6193150 JF - 2012 American Geophysical Union Fall Meeting (AGU 2012) AU - Smith, Robert AU - Palmer, Carl AU - Cooper, D Y1 - 2012/12/03/ PY - 2012 DA - 2012 Dec 03 KW - Geothermal resources KW - Resource exploration KW - Exploration UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313113767?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+American+Geophysical+Union+Fall+Meeting+%28AGU+2012%29&rft.atitle=Approaches+for+Multicomponent+Equilibrium+Geothermometry+as+a+Tool+for+Geothermal+Resource+Exploration&rft.au=Smith%2C+Robert%3BPalmer%2C+Carl%3BCooper%2C+D&rft.aulast=Smith&rft.aufirst=Robert&rft.date=2012-12-03&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+American+Geophysical+Union+Fall+Meeting+%28AGU+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://fallmeeting.agu.org/2012/scientific-program/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - An integrated experimental and modeling study of episodic air-water two-phase flow in fractures and fracture networks T2 - 2012 American Geophysical Union Fall Meeting (AGU 2012) AN - 1313113117; 6190133 JF - 2012 American Geophysical Union Fall Meeting (AGU 2012) AU - Huang, Hai AU - Wood, Thomas Y1 - 2012/12/03/ PY - 2012 DA - 2012 Dec 03 KW - Fractures KW - Air-water interface UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313113117?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+American+Geophysical+Union+Fall+Meeting+%28AGU+2012%29&rft.atitle=An+integrated+experimental+and+modeling+study+of+episodic+air-water+two-phase+flow+in+fractures+and+fracture+networks&rft.au=Huang%2C+Hai%3BWood%2C+Thomas&rft.aulast=Huang&rft.aufirst=Hai&rft.date=2012-12-03&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+American+Geophysical+Union+Fall+Meeting+%28AGU+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://fallmeeting.agu.org/2012/scientific-program/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Interaction of Parallel Flow Mixing Zones and Calcium Carbonate Precipitation with High and Low Permeability Inclusions in Porous Media T2 - 2012 American Geophysical Union Fall Meeting (AGU 2012) AN - 1313093014; 6185125 JF - 2012 American Geophysical Union Fall Meeting (AGU 2012) AU - Redden, George AU - Fox, Don AU - Zundel, M AU - Guo, Luanjing AU - Lu, Chuan AU - Huang, Hai AU - Fujita, Yoshiko Y1 - 2012/12/03/ PY - 2012 DA - 2012 Dec 03 KW - Permeability KW - Calcium carbonate KW - Calcium permeability KW - Precipitation UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313093014?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+American+Geophysical+Union+Fall+Meeting+%28AGU+2012%29&rft.atitle=Interaction+of+Parallel+Flow+Mixing+Zones+and+Calcium+Carbonate+Precipitation+with+High+and+Low+Permeability+Inclusions+in+Porous+Media&rft.au=Redden%2C+George%3BFox%2C+Don%3BZundel%2C+M%3BGuo%2C+Luanjing%3BLu%2C+Chuan%3BHuang%2C+Hai%3BFujita%2C+Yoshiko&rft.aulast=Redden&rft.aufirst=George&rft.date=2012-12-03&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+American+Geophysical+Union+Fall+Meeting+%28AGU+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://fallmeeting.agu.org/2012/scientific-program/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Monitoring CO2 sequestration into deep saline aquifer and associated salt intrusion using coupled multiphase flow modeling and time-lapse electrical resistivity tomography T2 - 2012 American Geophysical Union Fall Meeting (AGU 2012) AN - 1313070703; 6193906 JF - 2012 American Geophysical Union Fall Meeting (AGU 2012) AU - Lu, Chuan AU - Zhang, Chi AU - Huang, Hai AU - Johnson, Timothy Y1 - 2012/12/03/ PY - 2012 DA - 2012 Dec 03 KW - Salts KW - Aquifers KW - Electrical resistivity KW - Carbon dioxide KW - Aquifer KW - Multiphase flow KW - Tomography UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313070703?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+American+Geophysical+Union+Fall+Meeting+%28AGU+2012%29&rft.atitle=Monitoring+CO2+sequestration+into+deep+saline+aquifer+and+associated+salt+intrusion+using+coupled+multiphase+flow+modeling+and+time-lapse+electrical+resistivity+tomography&rft.au=Lu%2C+Chuan%3BZhang%2C+Chi%3BHuang%2C+Hai%3BJohnson%2C+Timothy&rft.aulast=Lu&rft.aufirst=Chuan&rft.date=2012-12-03&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+American+Geophysical+Union+Fall+Meeting+%28AGU+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://fallmeeting.agu.org/2012/scientific-program/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - JOUR T1 - Interaction of parallel flow mixing zones and calcium carbonate precipitation with high and low permeability inclusions in porous media AN - 1637526997; 2014-101062 AB - Engineered precipitation in porous media involves tight, non-linear coupling between reactant transport, mixing and reaction front propagation. We conducted an experimental campaign to investigate this coupling in homogenous and heterogeneous media where reactant mixing occurs across the interface between two solutions and a mineral precipitate (CaCO (sub 3) ) is formed. Two solutions containing the components for precipitation of calcium carbonate (Ca (super 2+) and HCO (super -) (sub 3) ) were injected side-by-side into intermediate-scale flow cells packed with silica sand. Both of the individual influent solutions were undersaturated with respect to calcite. At the interface between the solutions, reactants mix by a combination of dispersive and diffusive transport, and calcium carbonate precipitation results. In homogeneous media we observed that transport across the interface decreased with time, as expected, and the volume-averaged rate of reaction decreased. When high and low permeability inclusions were placed in the path of the original mixing interface, the spatial and temporal evolution of the calcium carbonate precipitation zone showed more complicated coupling between transport and reaction kinetics. Low permeability inclusions (permeability nearly equal 25X lower than the surrounding media) caused deflection of the mixing zone. Precipitate initially forms in the center of the mixing zone. Subsequently, lateral migration of the mixing/precipitation zone was observed that resulted in the inclusion being encapsulated by carbonate mineral. Precipitate that is subsequently exposed to the undersaturated calcium containing solution persists. For a high permeability inclusion (permeability nearly equal 17X greater than the surrounding media) placed in the path of the mixing zone, the flow and mixing zone was initially focused and passed through the inclusion. Interestingly, enhanced dispersion was observed downstream of the inclusion, and the spatial extent of calcium carbonate precipitation was greater than for homogeneous media in spite of flow focusing. A fully coupled, fully implicit reactive transport model was applied to reproduce experimental observations and to gain better fundamental understanding of the complex interplay between fluid flow, transport of reactants, and reaction-induced permeability/porosity changes. JF - American Geophysical Union Fall Meeting AU - Redden, G D AU - Fox, D T AU - Zundel, M AU - Guo, L AU - Lu, C AU - Huang, H AU - Fujita, Y AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract H33M EP - 06 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 02C:Geochemistry of rocks, soils, and sediments UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1637526997?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Interaction+of+parallel+flow+mixing+zones+and+calcium+carbonate+precipitation+with+high+and+low+permeability+inclusions+in+porous+media&rft.au=Redden%2C+G+D%3BFox%2C+D+T%3BZundel%2C+M%3BGuo%2C+L%3BLu%2C+C%3BHuang%2C+H%3BFujita%2C+Y%3BAnonymous&rft.aulast=Redden&rft.aufirst=G&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-18 N1 - CODEN - #07548 ER - TY - JOUR T1 - Hybrid multiscale simulation of mixing-controlled biogeochemical reactions AN - 1637526602; 2014-101092 AB - Most in situ remediation methods rely strongly on mixing of contaminants and other chemical species to promote targeted reactions that degrade or immobilize contaminants. It is now well known that the conventional approach to Darcy-scale solute transport simulation tends to overestimate in situ reaction rates because the dispersion process conceptualization combines advective spreading (due to heterogeneity) and diffusive mixing in a single lumped representation. Hybrid multiscale simulation methods, which combine microscale (pore-scale) and macroscale (Darcy-scale) simulations within a single unified framework, offers the potential to address this problem by explicitly resolving local diffusive mixing as impacted by large-scale advective spreading in a computationally tractable manner. In this talk we present methods and results of a multiscale hybrid simulation approach applied to a mixing-controlled reaction at the laboratory scale. Our approach couples a Smoothed Particle Hydrodynamics (SPH) pore-scale simulator with the STOMP Darcy-scale simulator using a custom workflow management system that adaptively selects SPH sub-domains and provides the coupling between SPH and STOMP simulations seamlessly on a scalable parallel computational platform. JF - American Geophysical Union Fall Meeting AU - Scheibe, T D AU - Schuchardt, K L AU - Agarwal, K AU - Chase, J AU - Palmer, B J AU - Tartakovsky, A M AU - Elsethagen, T AU - Redden, G D AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract H34C EP - 08 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 02C:Geochemistry of rocks, soils, and sediments UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1637526602?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Hybrid+multiscale+simulation+of+mixing-controlled+biogeochemical+reactions&rft.au=Scheibe%2C+T+D%3BSchuchardt%2C+K+L%3BAgarwal%2C+K%3BChase%2C+J%3BPalmer%2C+B+J%3BTartakovsky%2C+A+M%3BElsethagen%2C+T%3BRedden%2C+G+D%3BAnonymous&rft.aulast=Scheibe&rft.aufirst=T&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-18 N1 - CODEN - #07548 ER - TY - JOUR T1 - Monitoring CO (sub 2) sequestration into deep saline aquifer and associated salt intrusion using coupled multiphase flow modeling and time-lapse electrical resistivity tomography AN - 1629941655; 2014-098317 AB - Geological sequestration of carbon dioxide (CO (sub 2) ) into the subsurface has been considered as one solution to reduce greenhouse emission to the atmosphere. Successful sequestration process requires efficient and adequate monitoring of injected fluids as they migrate into the aquifer to evaluate flow path, leakage, and geochemical interactions between CO (sub 2) and geologic media. In this synthetic field scale study, we have integrated 3D multiphase flow modeling code PFLOTRAN with 3D time-laps electrical resistivity tomography (ERT) to gain insight into the supercritical (SC) CO (sub 2) plumes movement in the deep saline aquifer and associated brine intrusion into shallower fresh water aquifer. A parallel ERT forward and inverse modeling package was introduced, and related algorithms are briefly described. The capabilities and limitations of ERT in monitoring CO (sub 2) migration are assessed by comparing the results from PFLOTRAN simulations with the ERT inversion results. In general, our study shows the ERT inversion results compare well with PFLOTRAN with reasonable discrepancies, indicating that the ERT can capture the actual CO (sub 2) plume dynamics and brine intrusion. Detailed comparisons on the location, size and volume of CO (sub 2) plume show the ERT method underestimated area review and overestimated total plume volume in the predictions of SC CO (sub 2) movements. These comparisons also show the ERT method constantly overestimate salt intrusion area and underestimated total solute amount in the predictions of brine filtration. Our study shows that together with other geochemical and geophysical methods, ERT is a potentially useful monitoring tool in detecting the SC CO (sub 2) and formation fluid migrations. JF - American Geophysical Union Fall Meeting AU - Lu, C AU - Zhang, C AU - Huang, H AU - Johnson, T AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract H31J EP - 03 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1629941655?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Monitoring+CO+%28sub+2%29+sequestration+into+deep+saline+aquifer+and+associated+salt+intrusion+using+coupled+multiphase+flow+modeling+and+time-lapse+electrical+resistivity+tomography&rft.au=Lu%2C+C%3BZhang%2C+C%3BHuang%2C+H%3BJohnson%2C+T%3BAnonymous&rft.aulast=Lu&rft.aufirst=C&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-04 N1 - CODEN - #07548 ER - TY - JOUR T1 - Pace of glacial retreat and limits on paleoclimate conditions for the Pine Creek Glacier, Montana, during the Pinedale Glaciation AN - 1629941611; 2014-098019 AB - The timing of glaciation and the changes in climate that occurred both during and after the Last Glacial Maximum (LGM) in the Rocky Mountains are not well defined. Given the sensitivity of mountain glaciers to factors such as temperature, precipitation, and solar radiation, reconstructions of the history and extent of paleo-glaciers can be used to infer paleoclimate. Pine Creek Valley, located in the Absaroka Mountains in southwestern Montana, is an ideal setting for this type of research because it was occupied by a discrete valley glacier, the extent of which is precisely known during the LGM. To determine the pace and timing of ice retreat in this valley, glacially polished bedrock surfaces along the path of deglaciation were sampled at several points for cosmogenic (super 10) Be surface exposure dating. The ages obtained range from 17.9 + or - 0.8 to 13.2 + or - 0.5 ka. When combined with the reconstructed ice extent during the LGM and subsequent deglaciation, these ages yield maximum and minimum retreat rates of 3.1 m/yr and 1.1 m/yr, respectively. These values constrain how long it took the glacier to retreat into a well-defined cirque from the terminal moraines. Paleoclimate conditions for the LGM were estimated using a two-dimensional, numerical, combined energy and mass balance and ice flow model. Previous qualitative inferences of paleoclimate in southern Montana indicate climate during the local LGM was colder and drier than modern values. If precipitation values were held constant or reduced for the Pine Creek glacier, the model suggests a temperature depression of at least 8 degrees C. JF - American Geophysical Union Fall Meeting AU - Huss, E AU - Laabs, B J AU - Leonard, E M AU - Licciardi, J M AU - Plummer, Mitchell A AU - Caffee, M W AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract C53A EP - 0823 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1629941611?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Pace+of+glacial+retreat+and+limits+on+paleoclimate+conditions+for+the+Pine+Creek+Glacier%2C+Montana%2C+during+the+Pinedale+Glaciation&rft.au=Huss%2C+E%3BLaabs%2C+B+J%3BLeonard%2C+E+M%3BLicciardi%2C+J+M%3BPlummer%2C+Mitchell+A%3BCaffee%2C+M+W%3BAnonymous&rft.aulast=Huss&rft.aufirst=E&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-04 N1 - CODEN - #07548 ER - TY - JOUR T1 - Geochemical simulations on CO (sub 2) -fluid-rock interactions in EGS reservoirs AN - 1629940411; 2014-095843 AB - Supercritical CO2 has been suggested as a heat transmission fluid in Enhanced Geothermal Systems (EGS) reservoirs to improve energy extraction. Understanding the geochemical processes of CO2-fluid-rock interactions in EGS reservoirs is significant important to investigate the performance of energy extraction with CO2 instead of water as a working fluid, carbon sequestration and risk assessment. The objectives of this study: (1) to calibrate and evaluate the kinetic rate constants and specific reactive surface areas of minerals based on the batch experimental data conducted by other researchers (collaborators Kaszuba and Lo Re at the University of Wyoming); (2) to investigate the effects of CO2-fluid-rock geochemical interactions on the energy extraction efficiency, carbon sequestration, and risk assessment. A series of laboratory experiments were conducted (Lo Re et al., 2012) to investigate the geochemical reactions among water, fractured granite rocks, and injected supercritical CO2 at elevated temperatures of 250 degrees C, and pressures of 250-450 bars. The batch simulations were firstly conducted to mimic the laboratory experiments with the calibration of mineral reactive surface areas using TOUGHREACT model and parameter estimation software (PEST). Then, we performed 2-D geochemical modeling to simulate the chemical interactions among CO2, fluids, and rocks at high temperatures and pressures of EGS reservoirs. We further investigated the effects of fluid-rock interactions on the energy extraction, carbon sequestration, and risk assessment with CO2 as a heat transmission fluid instead of water for EGS reservoirs. Results of carbonate mineral precipitations suggested that the CO2 as a working fluid instead of water was favorable for EGS reservoirs on the CO2 sequestration. Our simulations also suggested that the energy extraction could be enhanced using CO2 as the transmission fluid compared to water. JF - American Geophysical Union Fall Meeting AU - Pan, F AU - McPherson, B J AU - Lichtner, P C AU - Kaszuba, John P AU - Lo Re, C AU - Karra, S AU - Lu, Chuan AU - Xu, Tianfu AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract H13G EP - 1433 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 02C:Geochemistry of rocks, soils, and sediments UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1629940411?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Geochemical+simulations+on+CO+%28sub+2%29+-fluid-rock+interactions+in+EGS+reservoirs&rft.au=Pan%2C+F%3BMcPherson%2C+B+J%3BLichtner%2C+P+C%3BKaszuba%2C+John+P%3BLo+Re%2C+C%3BKarra%2C+S%3BLu%2C+Chuan%3BXu%2C+Tianfu%3BAnonymous&rft.aulast=Pan&rft.aufirst=F&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2012/FM/sections/H/sessions/H13G/abstracts/H13G-1433.html LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-04 N1 - CODEN - #07548 ER - TY - JOUR T1 - An integrated experimental and modeling study of episodic air-water two-phase flow in fractures and fracture networks AN - 1629940380; 2014-095868 AB - Multiphase flow in fracture and fracture networks is highly complex due to the complex interplays among inertial force, gravity, surface tension and wettability of fluids on fracture surfaces. The complex behavior of air-water two-phase flow in fractures has significant implications for contaminant transport in deep, fractured vadose zones. Understanding and predicting the complex physics of flow at the field scale is still limited due to the lack of physics-based numerical models, size limitations of laboratory fracture flow experiments, inadequate characterization of fracture networks and absence of efficient monitoring tools for multiphase flow in the field. In this work, we present an integrated experimental and modeling study of air-water flow dynamics in fractures and fracture networks at multiple scales of observation, ranging from single small fracture models with variable apertures, to an intermediate scale laboratory analog of a fracture network, and finally a large field scale infiltration test. The complex 3D flow dynamics, including pulsating flow and flow path switching near fracture intersections, and air-water interfacial behaviors, are simulated and discussed. The fracture flow experimental data will also be presented and discussed, and compared with the modeling results. The qualitative agreements between the numerical simulations and the experimental results clearly demonstrate the value of the mechanistically based models for sorting out the complexity of multiphase flow dynamics in unsaturated fracture networks. JF - American Geophysical Union Fall Meeting AU - Huang, Hai AU - Wood, Thomas R AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract H13H EP - 08 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1629940380?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&rft.genre=dissertations+%26+theses&rft.jtitle=&rft.atitle=&rft.au=Santi%2C+Antonio%2C+Jr.&rft.aulast=Santi&rft.aufirst=Antonio&rft.date=1997-09-01&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Santeria+compared+to+psychology+as+a+mental+health+care+system&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2012/FM/sections/H/sessions/H13H/abstracts/H13H-08.html LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-04 N1 - CODEN - #07548 ER - TY - JOUR T1 - Approaches for multicomponent equilibrium geothermometry as a tool for geothermal resource exploration AN - 1629938665; 2014-096114 AB - Geothermometry is an important tool to estimate deep reservoir temperature from the geochemical composition of shallower and cooler waters. The underlying assumption of geothermometry is that the shallow waters maintain a chemical signature that reflects equilibrium in the deeper reservoir. Many of the geothermometers used in practice are based on empirical observations and correlation between water temperatures and composition using a subset (typically silica, cations or cation ratios) of the dissolved constituents. An alternative approach is to use complete water compositions and equilibrium geochemical modeling to calculate the degree of disequilibrium (Saturation Index) for large number of potential reservoir mineral as a function of temperature. Key to applying this approach is to define the often unknown primary/secondary mineral assemblage controlling equilibrium in the deep reservoir and to apply develop parameter optimization approaches to estimate the likely conditions (e.g., temperature, PCO (sub 2) ) to which the water was exposed in the deep subsurface. Selection of mineral assemblages can be addressed by a combination of practical (e.g., taking into account common alteration mineral assemblages) as well as theoretical (limiting the number of minerals by the phase rule) considerations. Because the values of Saturation Indexes are a function of reaction stoichiometry, simultaneous interpretation requires that values be weighted or normalized. The approach used here is to write reaction in terms of thermodynamic components and then divide the saturation index by the total count of components in the reaction (e.g., 1 for quartz, 2 for calcite, 5 for albite, and 7 for muscovite). This approach is tested against both synthetic and field derived data sets to estimate reservoir temperatures which are compared to actual temperatures or temperatures estimated from commonly employed approaches for geothermometry. JF - American Geophysical Union Fall Meeting AU - Smith, R W AU - Palmer, C D AU - Cooper, D Craig AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract V23F EP - 08 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 29A:Economic geology, geology of energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1629938665?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Approaches+for+multicomponent+equilibrium+geothermometry+as+a+tool+for+geothermal+resource+exploration&rft.au=Smith%2C+R+W%3BPalmer%2C+C+D%3BCooper%2C+D+Craig%3BAnonymous&rft.aulast=Smith&rft.aufirst=R&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-04 N1 - CODEN - #07548 ER - TY - JOUR T1 - Climate along the crest of the US Rocky Mountains during the last glaciation; preliminary insights from numerical modeling of paleoglaciers AN - 1566810163; 2014-075228 AB - Climate conditions at the time of the local Last Glacial Maximum (LGM) in the US Rocky Mountains were assessed using a 2-d coupled glacier energy/mass-balance and ice-flow model (Plummer and Phillips, 2003). The model was employed to understand the conditions that would be necessary to sustain valley glaciers and small mountain icecaps at their maximum extents in eight areas distributed along the crest of the range from northern New Mexico (35.8 degrees N) to northern Montana (48.6 degrees N). For each setting, model experiments yield a set of temperature and precipitation combinations that may have accompanied the local LGM. If the results of global and regional climate models are used to constrain temperature depression estimates from our model experiments, the following precipitation pattern emerges for the local LGM. In the northern Rocky Mountains in Montana and northern Wyoming, model results suggest a strong reduction in precipitation of 50% or more. In the central Rocky Mountains of southern Wyoming and Colorado, precipitation appears to have been 50-90% of modern. By contrast, precipitation appears to have been strongly enhanced in the southern Rocky Mountains of New Mexico. These results are broadly consistent with a pattern of precipitation observed in global and regional climate simulations of the LGM in the western U.S., in which precipitation was reduced in the northern Rocky Mountains but increased in the southern Rocky Mountains. This pattern may reflect a southward displacement of mean position the Pacific Jet Stream in western North America during and possibly following the LGM. JF - American Geophysical Union Fall Meeting AU - Leonard, E M AU - Laabs, B J AU - Plummer, Mitchell A AU - Huss, E AU - Spiess, Vivian M AU - Mackall, B T AU - Jacobsen, R E AU - Quirk, Brendon James AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract PP51A EP - 2106 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1566810163?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Climate+along+the+crest+of+the+US+Rocky+Mountains+during+the+last+glaciation%3B+preliminary+insights+from+numerical+modeling+of+paleoglaciers&rft.au=Leonard%2C+E+M%3BLaabs%2C+B+J%3BPlummer%2C+Mitchell+A%3BHuss%2C+E%3BSpiess%2C+Vivian+M%3BMackall%2C+B+T%3BJacobsen%2C+R+E%3BQuirk%2C+Brendon+James%3BAnonymous&rft.aulast=Leonard&rft.aufirst=E&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-10-02 N1 - CODEN - #07548 ER - TY - JOUR T1 - A new model for the spectral induced polarization signature of bacterial growth in porous media AN - 1566810020; 2014-075176 AB - Recent biogeophysics studies demonstrated the sensitivity of complex conductivity to bacterial growth and microbial mediated mineral transformations in porous media. Frequency-domain induced polarization is a minimally invasive manner to measure the complex conductivity of a material over a broad range of frequencies. The real component of complex conductivity is associated with electromigration of the charge carriers, and the imaginary component represents reversible energy storage of charge carriers at polarization length scales. Quantitative relationship between frequency-domain induced polarization responses and bacterial growth and decay in porous media is analyzed in this study using a new developed model. We focus on the direct contribution of bacteria themselves to the complex conductivity in porous media in the absence of biomineralization. At low frequencies, the induced polarization of bacteria (alpha -polarization) is related to the properties of the electrical double layer surrounding the membrane surface of bacteria. Surface conductivity and alpha -polarization are due to the Stern layer of the counterions occurring in a brush of polymers coating the surface of the bacteria, and can be related to the cation exchange capacity of the bacteria. From the modeling results, at low frequencies (<10 Hz), the mobility of the counterions (K (super +) ) in the Stern layer of bacteria is found to be extremely small (4.7X10 (super -10) m (super 2) s (super -1) V (super -1) at 25 degrees C), and is close to the mobility of the same counterions along the surface of clay minerals (Na (super +) , 1.5X10 (super -10) m (super 2) s (super -1) V (super -1) at 25 degrees C). This result is in agreement with experimental observations and it indicates a very low relaxation frequency for the alpha -polarization of the bacteria cells (typically around 0.1 to 5 Hertz). By coupling this new model with reactive transport modeling in which the evolution of bacterial populations are usually described by Monod kinetics, we show that the changes in imaginary conductivity with time can be used to determine bacterial growth kinetics parameters such as the growth and endogenous decay coefficient. JF - American Geophysical Union Fall Meeting AU - Zhang, Chi AU - Revil, A AU - Atekwana, Estella A AU - Jardani, Abderrahim AU - Smith, Schaun M AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract B11A EP - 0405 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1566810020?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=A+new+model+for+the+spectral+induced+polarization+signature+of+bacterial+growth+in+porous+media&rft.au=Zhang%2C+Chi%3BRevil%2C+A%3BAtekwana%2C+Estella+A%3BJardani%2C+Abderrahim%3BSmith%2C+Schaun+M%3BAnonymous&rft.aulast=Zhang&rft.aufirst=Chi&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-10-02 N1 - CODEN - #07548 ER - TY - JOUR T1 - Deformation rates in the Snake River Plain and adjacent Basin and Range regions based on GPS measurements AN - 1560082430; 2014-067260 AB - We estimate horizontal velocities for 405 sites using Global Positioning System (GPS) phase data collected from 1994 to 2010 within the Northern Basin and Range Province, U.S.A. The velocities reveal a slowly-deforming region within the Snake River Plain in Idaho and Owyhee-Oregon Plateau in Oregon separated from the actively extending adjacent Basin and Range regions by shear. Our results show a NE-oriented extensional strain rate of 5.6 + or - 0.7 nanostrain/yr in the Centennial Tectonic Belt and an approximately E-oriented extensional strain rate of 3.5 + or - 0.2 nanostrain/yr in the Great Basin. These extensional rates contrast with the very low strain rate within the 125 km x 650 km region of the Snake River Plain and Owyhee-Oregon Plateau which is not distinguishable from zero (-0.1 + or - 0.4 X nanostrain/yr). Inversions of Snake River Plain velocities with dike-opening models indicate that rapid extension by dike intrusion in volcanic rift zones, as previously hypothesized, is not currently occurring. GPS data also disclose that rapid extension in the surrounding regions adjacent to the slowly-deforming region of the Snake River Plain drives shear between them. We estimate right-lateral shear with slip rates of 0.3-1.5 mm/yr along the northwestern boundary adjacent to the Centennial Tectonic Belt and left-lateral oblique extension with slip rates of 0.5-1.5 mm/yr along the southeastern boundary adjacent to the Intermountain Seismic Belt. The fastest lateral shearing evident in the GPS occurs near the Yellowstone Plateau where earthquakes with right-lateral strike-slip focal mechanisms are within a NE-trending zone of seismicity. The regional velocity gradients are best fit by nearby poles of rotation for the Centennial Tectonic Belt, Snake River Plain, Owyhee-Oregon Plateau, and eastern Oregon, indicating that clockwise rotation is not locally driven by Yellowstone hotspot volcanism, but instead by extension to the south across the Wasatch fault possibly due to gravitational collapse and by shear in the Walker Lane belt resulting from Pacific - Northern America relative plate motion. JF - American Geophysical Union Fall Meeting AU - Payne, S J AU - McCaffrey, R AU - King, R W AU - Kattenhorn, S A AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract V13B EP - 2849 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 18:Solid-earth geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1560082430?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Deformation+rates+in+the+Snake+River+Plain+and+adjacent+Basin+and+Range+regions+based+on+GPS+measurements&rft.au=Payne%2C+S+J%3BMcCaffrey%2C+R%3BKing%2C+R+W%3BKattenhorn%2C+S+A%3BAnonymous&rft.aulast=Payne&rft.aufirst=S&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-09-05 N1 - CODEN - #07548 ER - TY - JOUR T1 - Quantification of volcanic CO (sub 2) emissions using the eddy covariance method AN - 1542644081; 2014-047554 AB - Eddy covariance (EC) is a micrometeorological technique proposed as a method to measure passive volcanic CO (sub 2) emissions from soil, vent, groundwater, and surface water sources. EC provides an automated, semi-continuous, and time and space-averaged CO (sub 2) flux measurement. Also, the measurement's "intermediate" spatial scale (m (super 2) -km (super 2) ) has the potential to bridge the gap between relatively small-scale ground-based measurements (e.g., using the accumulation chamber, AC, method) and relatively large-scale satellite-based observations. We deployed and tested an EC system during two studies in an area of diffuse volcanic CO (sub 2) emissions on Mammoth Mountain, CA and near a bubbling spring in Soda Springs, ID. Half-hourly EC CO (sub 2) fluxes were measured on Mammoth Mountain during September-October 2006 and ranged from 218 to 3500 g m (super -2) d (super -1) . Maps of surface CO (sub 2) flux were simulated based on AC measurements made repeatedly on a grid over a ten-day period. Large meteorologically driven variations in surface flux distributions and emission rates (16 to 52 t d (super -1) ) were observed. Using source weight function modeling, we compared EC to AC measurements of CO (sub 2) flux. Half-hour EC CO (sub 2) fluxes were moderately correlated (R (super 2) =0.42) with AC fluxes, whereas average-daily EC and AC fluxes were well correlated (R (super 2) =0.70). We then made EC measurements of CO (sub 2) flux on Mammoth Mountain during September-October 2010, which ranged from 85 to 1766 g m (super -2) d (super -1) . Three AC soil CO (sub 2) flux surveys during this time were used to simulate maps of soil CO (sub 2) flux and estimate total emission rates. An inversion of measured EC CO (sub 2) fluxes and corresponding modeled source weight functions was carried out and recovered 58 to 77% of the CO (sub 2) emission rates estimated based on simulated AC soil CO (sub 2) fluxes within a 0.01 km (super 2) area. Spatial distributions of modeled surface CO (sub 2) fluxes based on EC and AC observations showed moderate to good correspondence (R (super 2) =0.36 to 0.70). In September-October 2011, we deployed an EC system near a bubbling spring in Soda Springs, ID and measured CO (sub 2) fluxes from -74 to 1147 g m (super -2) d (super -1) . An inversion of measured EC CO (sub 2) fluxes and modeled source weight functions mapped the surface CO (sub 2) flux distribution within and quantified CO (sub 2) emission rate (24.9 t d (super -1) ) from a 0.05 km (super 2) area surrounding the spring. This emission rate was 79% of the dissolved CO (sub 2) discharge from the spring estimated as the product of the measured concentration of dissolved inorganic carbon and spring outflow rate. Overall, the results of our investigations suggest that under appropriate terrain and atmospheric conditions, EC can serve as a valuable tool for semi-continuous monitoring and quantification of volcanic CO (sub 2) emissions from moderate size land areas. JF - American Geophysical Union Fall Meeting AU - Lewicki, J L AU - Hilley, G E AU - Dobeck, L AU - Fischer, M L AU - McLing, Travis L AU - Anonymous Y1 - 2012/12// PY - 2012 DA - December 2012 SP - Abstract V53B EP - 2837 PB - American Geophysical Union, Washington, DC VL - 2012 KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1542644081?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Quantification+of+volcanic+CO+%28sub+2%29+emissions+using+the+eddy+covariance+method&rft.au=Lewicki%2C+J+L%3BHilley%2C+G+E%3BDobeck%2C+L%3BFischer%2C+M+L%3BMcLing%2C+Travis+L%3BAnonymous&rft.aulast=Lewicki&rft.aufirst=J&rft.date=2012-12-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2012 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-07-04 N1 - CODEN - #07548 ER - TY - JOUR T1 - Drainage capture and discharge variations driven by glaciation in the Southern Alps, New Zealand AN - 1244677474; 2013-007363 AB - Sediment flux in proglacial fluvial settings is primarily controlled by discharge, which usually varies predictably over a glacial-interglacial cycle. However, glaciers can flow against the topographic gradient to cross drainage divides, reshaping fluvial drainage networks and dramatically altering discharge. In turn, these variations in discharge will be recorded by proglacial stratigraphy. Glacial-drainage capture often occurs in alpine environments where ice caps straddle range divides, and more subtly where shallow drainage divides cross valley floors. We investigate discharge variations resulting from glacial-drainage capture over the past 40 k.y. for the adjacent Ashburton, Rangitata, and Rakaia basins in the Southern Alps, New Zealand. Although glacial-drainage capture has previously been inferred in the range, our numerical glacier model provides the first quantitative demonstration that this process drives larger variations in discharge for a longer duration than those that occur due to climate change alone. During the Last Glacial Maximum, the effective drainage area of the Ashburton catchment increased to 160% of the interglacial value with drainage capture, driving an increase in discharge exceeding that resulting from glacier recession. Glacial-drainage capture is distinct from traditional (base level-driven) drainage capture and is often unrecognized in proglacial deposits, complicating interpretation of the sedimentary record of climate change. JF - Geology (Boulder) AU - Rowan, Ann V AU - Plummer, Mitchell A AU - Brocklehurst, Simon H AU - Jones, Merren A AU - Schultz, David M Y1 - 2012/11/13/ PY - 2012 DA - 2012 Nov 13 SP - 199 EP - 202 PB - Geological Society of America (GSA), Boulder, CO VL - 41 IS - 2 SN - 0091-7613, 0091-7613 KW - last glacial maximum KW - Quaternary KW - glaciation KW - Australasia KW - paleohydrology KW - drainage patterns KW - watersheds KW - glaciers KW - Southern Alps KW - simulation KW - stream capture KW - models KW - Cenozoic KW - South Island KW - alluvial fans KW - discharge KW - fluvial environment KW - New Zealand KW - 24:Quaternary geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1244677474?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Geology+%28Boulder%29&rft.atitle=Drainage+capture+and+discharge+variations+driven+by+glaciation+in+the+Southern+Alps%2C+New+Zealand&rft.au=Rowan%2C+Ann+V%3BPlummer%2C+Mitchell+A%3BBrocklehurst%2C+Simon+H%3BJones%2C+Merren+A%3BSchultz%2C+David+M&rft.aulast=Rowan&rft.aufirst=Ann&rft.date=2012-11-13&rft.volume=41&rft.issue=2&rft.spage=199&rft.isbn=&rft.btitle=&rft.title=Geology+%28Boulder%29&rft.issn=00917613&rft_id=info:doi/10.1130%2FG33829.1 L2 - http://www.gsajournals.org/ LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. Reference includes data from GeoScienceWorld, Alexandria, VA, United States | Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2013-01-01 N1 - Number of references - 26 N1 - PubXState - CO N1 - Document feature - illus. incl. sketch map N1 - SuppNotes - GSA Data Repository item 2013049 N1 - Last updated - 2014-01-09 N1 - CODEN - GLGYBA N1 - SubjectsTermNotLitGenreText - alluvial fans; Australasia; Cenozoic; discharge; drainage patterns; fluvial environment; glaciation; glaciers; last glacial maximum; models; New Zealand; paleohydrology; Quaternary; simulation; South Island; Southern Alps; stream capture; watersheds DO - http://dx.doi.org/10.1130/G33829.1 ER - TY - CPAPER T1 - System Evaluation and Life-Cycle Cost Analysis of Commercial-Scale High-Temperature Electrolysis Hydrogen Production Plant T2 - 2012 ASME International Mechanical Engineering Congress & Exposition AN - 1313105055; 6170740 JF - 2012 ASME International Mechanical Engineering Congress & Exposition AU - Harvego, Edwin AU - O'Brien, James AU - McKellar, Michael Y1 - 2012/11/09/ PY - 2012 DA - 2012 Nov 09 KW - Economics KW - Hydrogen KW - Electrolysis KW - Cost analysis UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313105055?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.atitle=System+Evaluation+and+Life-Cycle+Cost+Analysis+of+Commercial-Scale+High-Temperature+Electrolysis+Hydrogen+Production+Plant&rft.au=Harvego%2C+Edwin%3BO%27Brien%2C+James%3BMcKellar%2C+Michael&rft.aulast=Harvego&rft.aufirst=Edwin&rft.date=2012-11-09&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2012/ConferenceSchedule.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Particle Image Velocimetry Measurements in a Representative Gas-cooled Prismatic Reactor Core Model: Flow in the Coolant Channels and Interstitial Bypass Gaps T2 - 2012 ASME International Mechanical Engineering Congress & Exposition AN - 1313070951; 6171364 JF - 2012 ASME International Mechanical Engineering Congress & Exposition AU - Conder, Thomas AU - Skifton, Richard AU - Budwig, Ralph Y1 - 2012/11/09/ PY - 2012 DA - 2012 Nov 09 KW - Channels KW - Particulates KW - Interstitial environment KW - Models UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313070951?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.atitle=Particle+Image+Velocimetry+Measurements+in+a+Representative+Gas-cooled+Prismatic+Reactor+Core+Model%3A+Flow+in+the+Coolant+Channels+and+Interstitial+Bypass+Gaps&rft.au=Conder%2C+Thomas%3BSkifton%2C+Richard%3BBudwig%2C+Ralph&rft.aulast=Conder&rft.aufirst=Thomas&rft.date=2012-11-09&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2012/ConferenceSchedule.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Counting Failure Events for a Support System T2 - 2012 ASME International Mechanical Engineering Congress & Exposition AN - 1313064879; 6172933 JF - 2012 ASME International Mechanical Engineering Congress & Exposition AU - Smith, Curtis Y1 - 2012/11/09/ PY - 2012 DA - 2012 Nov 09 KW - Enumeration UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313064879?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.atitle=Counting+Failure+Events+for+a+Support+System&rft.au=Smith%2C+Curtis&rft.aulast=Smith&rft.aufirst=Curtis&rft.date=2012-11-09&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2012/ConferenceSchedule.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Evaluation of Blister Behavior for U10Mo Mini Fuel Plates with Cold Rolled Foils T2 - 2012 ASME International Mechanical Engineering Congress & Exposition AN - 1313038262; 6171044 JF - 2012 ASME International Mechanical Engineering Congress & Exposition AU - Ozaltun, Hakan AU - Miller, Samuel Y1 - 2012/11/09/ PY - 2012 DA - 2012 Nov 09 KW - Fuels UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313038262?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.atitle=Evaluation+of+Blister+Behavior+for+U10Mo+Mini+Fuel+Plates+with+Cold+Rolled+Foils&rft.au=Ozaltun%2C+Hakan%3BMiller%2C+Samuel&rft.aulast=Ozaltun&rft.aufirst=Hakan&rft.date=2012-11-09&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2012/ConferenceSchedule.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Evaluation of U10MO Fuel Plate Irradiation Behavior via Numerical and Experimental Benchmarking T2 - 2012 ASME International Mechanical Engineering Congress & Exposition AN - 1313038189; 6171043 JF - 2012 ASME International Mechanical Engineering Congress & Exposition AU - Miller, Samuel AU - Ozaltun, Hakan Y1 - 2012/11/09/ PY - 2012 DA - 2012 Nov 09 KW - Fuels KW - Irradiation KW - Radiation UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313038189?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.atitle=Evaluation+of+U10MO+Fuel+Plate+Irradiation+Behavior+via+Numerical+and+Experimental+Benchmarking&rft.au=Miller%2C+Samuel%3BOzaltun%2C+Hakan&rft.aulast=Miller&rft.aufirst=Samuel&rft.date=2012-11-09&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2012/ConferenceSchedule.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Finite Element Simulations of Monolithic Plates for the Conversion of High Performance Research and Test Reactors: NBSR, MITR, MURR and AFIP T2 - 2012 ASME International Mechanical Engineering Congress & Exposition AN - 1313038148; 6171042 JF - 2012 ASME International Mechanical Engineering Congress & Exposition AU - Ozaltun, Hakan AU - Miller, Samuel Y1 - 2012/11/09/ PY - 2012 DA - 2012 Nov 09 KW - Simulation KW - Mathematical models UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313038148?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.atitle=Finite+Element+Simulations+of+Monolithic+Plates+for+the+Conversion+of+High+Performance+Research+and+Test+Reactors%3A+NBSR%2C+MITR%2C+MURR+and+AFIP&rft.au=Ozaltun%2C+Hakan%3BMiller%2C+Samuel&rft.aulast=Ozaltun&rft.aufirst=Hakan&rft.date=2012-11-09&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+ASME+International+Mechanical+Engineering+Congress+%26+Exposition&rft.issn=&rft_id=info:doi/ L2 - http://www.asmeconferences.org/Congress2012/ConferenceSchedule.cfm LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Shale Gas: Opportunities and Challenges T2 - 2012 Annual Meeting of the Geological Society of America AN - 1313103596; 6174184 JF - 2012 Annual Meeting of the Geological Society of America AU - Meakin, Paul AU - Huang, Hai AU - Malthe-Sorenssen, Anders AU - Thogersen, Kjetil Y1 - 2012/11/04/ PY - 2012 DA - 2012 Nov 04 KW - Shale UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313103596?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+Annual+Meeting+of+the+Geological+Society+of+America&rft.atitle=Shale+Gas%3A+Opportunities+and+Challenges&rft.au=Meakin%2C+Paul%3BHuang%2C+Hai%3BMalthe-Sorenssen%2C+Anders%3BThogersen%2C+Kjetil&rft.aulast=Meakin&rft.aufirst=Paul&rft.date=2012-11-04&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+Annual+Meeting+of+the+Geological+Society+of+America&rft.issn=&rft_id=info:doi/ L2 - https://gsa.confex.com/gsa/2012AM/webprogram/start.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - JOUR T1 - Shale gas; opportunities and challenges AN - 1469625115; 2013-097422 AB - The production of hydrocarbon fluids from very low permeability rocks has been increasing at a high rate for many years, but it received little attention until production reached about 20% of US total gas production, just a few years ago, and resource reassessments indicated that addition of "first generation" unconventional gas (shale gas, tight gas and coalbed methane) could double the US technically recoverable resource. Shale gas is the most important of these resources, and by 2035 it could account for almost 1/2 of US natural gas production. Shale gas production is enabled by horizontal drilling, hydraulic fracturing and fracture propping, but despite many innovations, recovery factors are low (for shale gas recovery factors vary greatly with an average of about 20%). Based on current technology and resource estimates, hundreds of thousands of hydraulically fractured wells will be required to produce the US shale gas resource, and millions will be required worldwide. We have developed physics-based numerical models for hydraulic fracturing, fracture propping, the placement of propping particles in fracture apertures and fluid flow in propped fractures, and applied them to shale gas recovery. Most of these models are based on the discrete element models for rock deformation and fracturing coupled with a Darcy flow or pore network model for fluid flow and a continuum heat transport model. US and global first generation natural gas resources will be discussed and an overview of the technology used to produce gas from these resources will be presented with a focus on the geomechanics of shale gas production and the challenges of producing hydrocarbon fluids from very low permeability rocks. Some of our own research results will be included in the presentation. JF - Abstracts with Programs - Geological Society of America AU - Meakin, Paul AU - Huang, Hai AU - Malthe-Sorenssen, Anders AU - Thogersen, Kjetil AU - Anonymous Y1 - 2012/11// PY - 2012 DA - November 2012 SP - 519 PB - Geological Society of America (GSA), Boulder, CO VL - 44 IS - 7 SN - 0016-7592, 0016-7592 KW - United States KW - hydraulic fracturing KW - resources KW - horizontal drilling KW - technology KW - numerical models KW - natural gas KW - global KW - petroleum KW - gas shale KW - production KW - recovery KW - porosity KW - evaluation KW - sedimentary rocks KW - directional drilling KW - drilling KW - permeability KW - 29A:Economic geology, geology of energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1469625115?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Shale+gas%3B+opportunities+and+challenges&rft.au=Meakin%2C+Paul%3BHuang%2C+Hai%3BMalthe-Sorenssen%2C+Anders%3BThogersen%2C+Kjetil%3BAnonymous&rft.aulast=Meakin&rft.aufirst=Paul&rft.date=2012-11-01&rft.volume=44&rft.issue=7&rft.spage=519&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2012 annual meeting N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2013-01-01 N1 - PubXState - CO N1 - Last updated - 2013-12-20 N1 - CODEN - GAAPBC N1 - SubjectsTermNotLitGenreText - directional drilling; drilling; evaluation; gas shale; global; horizontal drilling; hydraulic fracturing; natural gas; numerical models; permeability; petroleum; porosity; production; recovery; resources; sedimentary rocks; technology; United States ER - TY - JOUR T1 - Characterization of interactions between carbon dioxide and groundwater at a CO2 leak analogue study site in Soda Springs Idaho AN - 1429840073; 2013-068713 AB - Migration of CO (sub 2) stored in deep geologic formations into overlying freshwater aquifers may have significant environmental impacts, including the transport of undesirable metals into a groundwater resource. Because of the timescales and volumes involved, it is not possible to conduct field scale experiments to measure the actual phenomenon. Geochemical transport models are useful, but without field-derived data, these models cannot provide unique solutions. Natural analogue sites for the study geologic carbon dioxide sequestration provide opportunities to bridge this gap by examining CO (sub 2) systems that have operated on time scales of centuries to millenia. Such sites provide a perspective that laboratory and field experiments (e.g., time scales of days to decades) cannot provide. One such Site is the CO (sub 2) Leak Analogue Study Site (CLASS) located in Soda Springs, Idaho, USA. At this site, CO (sub 2) and formation fluids generated by the dissolution of Paleozoic carbonates at depth are migrating and reacting with a series of shallower thoelitic basalt flows that host a fresh water aquifer. In many cases the CO (sub 2) escapes to the surface in large volumes. But in most cases the CO (sub 2) is trapped by mineralization reactions with in the aquifer and by dissolution into the groundwater. These mineralization reactions have generated a specific chemical signature within the formation fluid. This signature can be used to assess the relative impact of leaking CO (sub 2) on water-rock interactions, and provides a basis for interpreting results from field and laboratory experiments in the context of a large-scale CO (sub 2) system interacting with an overlying aquifer. Lessons learned from the work at the Soda Springs analog site have provided insight into how reactive in situ tracers can track the progress of CO (sub 2) -water-rock interactions, and preliminary results have been integrated into the risk management plan for the Big Sky Carbon Sequestration Partnership's project at Kevin Dome. JF - Abstracts with Programs - Geological Society of America AU - McLing, Travis L AU - Cooper, Craig AU - Smith, William AU - Anonymous Y1 - 2012/11// PY - 2012 DA - November 2012 SP - 152 EP - 153 PB - Geological Society of America (GSA), Boulder, CO VL - 44 IS - 7 SN - 0016-7592, 0016-7592 KW - United States KW - hydrology KW - Idaho KW - carbon sequestration KW - Soda Springs Idaho KW - Caribou County Idaho KW - ground water KW - carbon dioxide KW - aquifers KW - water-rock interaction KW - mineralization KW - geochemistry KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1429840073?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Characterization+of+interactions+between+carbon+dioxide+and+groundwater+at+a+CO2+leak+analogue+study+site+in+Soda+Springs+Idaho&rft.au=McLing%2C+Travis+L%3BCooper%2C+Craig%3BSmith%2C+William%3BAnonymous&rft.aulast=McLing&rft.aufirst=Travis&rft.date=2012-11-01&rft.volume=44&rft.issue=7&rft.spage=152&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2012 annual meeting N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2013-01-01 N1 - PubXState - CO N1 - Last updated - 2013-09-05 N1 - CODEN - GAAPBC N1 - SubjectsTermNotLitGenreText - aquifers; carbon dioxide; carbon sequestration; Caribou County Idaho; geochemistry; ground water; hydrology; Idaho; mineralization; Soda Springs Idaho; United States; water-rock interaction ER - TY - JOUR T1 - Numerical modeling experiment reveals opportunities and challenges for CO2 sequestration in low-volume basalt formations AN - 1429839998; 2013-068711 AB - Geologic carbon sequestration in basalt-hosted reservoirs is predicated on laboratory experiments demonstrating that CO (sub 2) -water-rock interactions are energetically favorable for permanent carbon trapping on a time scale of 10 (super 2) -10 (super 3) days. While these laboratory experiments suggest that basalt-hosted reservoirs may be ideal targets for long term CO (sub 2) disposal, little work has been done to understand the site scale impacts of commercial CO (sub 2) injections into basalt-hosted reservoirs. Among the many questions that remain open, the influence of spatially distributed formation heterogeneity is a fundamental challenge for characterizing and modeling CO (sub 2) injections into a basalt reservoir. In the work presented here, we use a Monte Carlo numerical modeling experiment of CO (sub 2) injections into a low-volume basalt reservoir--with properties based on data from the east Snake River plain (ESRP) in southern Idaho--to investigate how a priori unknown heterogeneous property distributions influence injection pressure accumulation, geomechanical changes in the target reservoir, and vertical CO (sub 2) migration. The target reservoir is modeled as a three-dimensional bimodal stochastic continuum (2.88M gridblocks) using 50 equally probable synthetic reservoirs. Supercritical CO (sub 2) is injected into each reservoir model at a constant mass rate of approximately 682,000 metric tons/year for 20 years. Results from this work suggest that 1) formation heterogeneity strongly influences the rate and magnitude of injection pressure accumulation within the first month of injection; 2) for an extensional stress regime (as exists within the ESRP), shear failure is unlikely for minimum horizontal compressive stress (S (sub h) ) greater than 60% of the vertical stress (S (sub v) ), and; 3) the mean vertical CO (sub 2) mass flux is less than 5 X 10 (super -4) kg/s at 800m depth after 20 years suggesting that carbonate precipitation rates described in the literature may be adequate to trap CO (sub 2) prior to widespread escape. JF - Abstracts with Programs - Geological Society of America AU - Pollyea, Ryan M AU - Fairley, Jerry P AU - Podgorney, Robert K AU - McLing, Travis L AU - Anonymous Y1 - 2012/11// PY - 2012 DA - November 2012 SP - 152 PB - Geological Society of America (GSA), Boulder, CO VL - 44 IS - 7 SN - 0016-7592, 0016-7592 KW - United States KW - hydrology KW - Idaho KW - experimental studies KW - carbon sequestration KW - volcanic rocks KW - underground storage KW - igneous rocks KW - injection KW - reservoir rocks KW - carbon dioxide KW - water-rock interaction KW - basalts KW - underground installations KW - Snake River plain KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1429839998?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+with+Programs+-+Geological+Society+of+America&rft.atitle=Numerical+modeling+experiment+reveals+opportunities+and+challenges+for+CO2+sequestration+in+low-volume+basalt+formations&rft.au=Pollyea%2C+Ryan+M%3BFairley%2C+Jerry+P%3BPodgorney%2C+Robert+K%3BMcLing%2C+Travis+L%3BAnonymous&rft.aulast=Pollyea&rft.aufirst=Ryan&rft.date=2012-11-01&rft.volume=44&rft.issue=7&rft.spage=152&rft.isbn=&rft.btitle=&rft.title=Abstracts+with+Programs+-+Geological+Society+of+America&rft.issn=00167592&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Geological Society of America, 2012 annual meeting N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. Reference includes data supplied by the Geological Society of America, Boulder, CO, United States N1 - Date revised - 2013-01-01 N1 - PubXState - CO N1 - Last updated - 2013-09-05 N1 - CODEN - GAAPBC N1 - SubjectsTermNotLitGenreText - basalts; carbon dioxide; carbon sequestration; experimental studies; hydrology; Idaho; igneous rocks; injection; reservoir rocks; Snake River plain; underground installations; underground storage; United States; volcanic rocks; water-rock interaction ER - TY - JOUR T1 - Using eigenmodes to perform the inverse problem associated with resonant ultrasound spectroscopy AN - 1349440528; 17851162 AB - In principle, resonant ultrasonic spectroscopy (RUS) can be used to characterize any parameter that influences the mechanical resonant response of a sample. Examples include the elastic constants, sample dimensions, and crystal orientation. Extracting the parameter of interest involves performing the inverse problem, which typically entails an iterative routine that compares calculated and measured eigenfrequencies. Here, we propose an alternative method based on laser-based resonant ultrasound spectroscopy (LRUS) that uses the eigenmodes. LRUS uses a pulsed laser to thermoelastically excite ultrasound and an interferometer to detect out-of-plane displacement associated with ultrasonic resonances. By raster scanning the probe along the sample surface, an image of the out-ofplane displacement pattern (i.e., eigenmode) is obtained. As an example of this method, we describe a technique to calculate the crystallographic orientation of a single-crystal high-purity copper sample. The crystallographic orientation is computed by comparing theoretical and experimental eigenmodes. The computed angle is shown to be in very good agreement with the angle obtained using electron backscatter diffraction. In addition, a comparison is made using eigenfrequencies and eigenmodes to calculate the crystallographic orientation. It is found for this particular application, the eigenmode method has superior sensitivity to crystal orientation. JF - IEEE Transactions on Ultrasonics, Ferroelectrics and Frequency Control AU - Farzbod, Farhad AU - Hurley, David H AD - Materials Science and Engineering Department, Idaho National Laboratory, Idaho Falls, ID Y1 - 2012/11// PY - 2012 DA - Nov 2012 SP - 2470 EP - 2475 PB - Institute of Electrical and Electronics Engineers, Inc., 3 Park Avenue, 17th Fl New York NY 10016-5997 United States VL - 59 IS - 11 SN - 0885-3010, 0885-3010 KW - Biotechnology and Bioengineering Abstracts KW - Scanning KW - Ultrasonics KW - Probes KW - Lasers KW - Crystals KW - Diffraction KW - Copper KW - Spectroscopy KW - Ultrasound KW - W 30910:Imaging UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1349440528?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Abiotechresearch&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=IEEE+Transactions+on+Ultrasonics%2C+Ferroelectrics+and+Frequency+Control&rft.atitle=Using+eigenmodes+to+perform+the+inverse+problem+associated+with+resonant+ultrasound+spectroscopy&rft.au=Farzbod%2C+Farhad%3BHurley%2C+David+H&rft.aulast=Farzbod&rft.aufirst=Farhad&rft.date=2012-11-01&rft.volume=59&rft.issue=11&rft.spage=2470&rft.isbn=&rft.btitle=&rft.title=IEEE+Transactions+on+Ultrasonics%2C+Ferroelectrics+and+Frequency+Control&rft.issn=08853010&rft_id=info:doi/10.1109%2FTUFFC.2012.2479 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Scanning; Ultrasonics; Probes; Lasers; Copper; Diffraction; Crystals; Spectroscopy; Ultrasound DO - http://dx.doi.org/10.1109/TUFFC.2012.2479 ER - TY - CPAPER T1 - Bench-Scale Electrochemical Production of Synthesis Gas T2 - 2012 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2012) AN - 1313122636; 6167036 JF - 2012 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2012) AU - Lister, Tedd AU - Dufek, Eric AU - McIlwain, Michael Y1 - 2012/10/28/ PY - 2012 DA - 2012 Oct 28 KW - Electrochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313122636?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2012%29&rft.atitle=Bench-Scale+Electrochemical+Production+of+Synthesis+Gas&rft.au=Lister%2C+Tedd%3BDufek%2C+Eric%3BMcIlwain%2C+Michael&rft.aulast=Lister&rft.aufirst=Tedd&rft.date=2012-10-28&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2012%29&rft.issn=&rft_id=info:doi/ L2 - https://aiche.confex.com/aiche/2012/webprogram/start.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Rapid Analysis of Feedstock Ash Composition Using Laser-Induced Breakdown Spectroscopy (LIBS) T2 - 2012 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2012) AN - 1313028746; 6169233 JF - 2012 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2012) AU - Westover, Tyler AU - Gresham, Garold AU - Boardman, Richard Y1 - 2012/10/28/ PY - 2012 DA - 2012 Oct 28 KW - Spectroscopy KW - Ash UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313028746?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2012%29&rft.atitle=Rapid+Analysis+of+Feedstock+Ash+Composition+Using+Laser-Induced+Breakdown+Spectroscopy+%28LIBS%29&rft.au=Westover%2C+Tyler%3BGresham%2C+Garold%3BBoardman%2C+Richard&rft.aulast=Westover&rft.aufirst=Tyler&rft.date=2012-10-28&rft.volume=&rft.issue=&rft.spage=&rft.isbn=978-1321778861&rft.btitle=&rft.title=Santeria+as+an+informal+psychosocial+support+among+Latinas+living+with+cancer&rft.issn=&rft_id=info:doi/ L2 - https://aiche.confex.com/aiche/2012/webprogram/start.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - The Issues and Opportunities Associated with Recycle and Reuse of Strategic and Critical Materials T2 - 2012 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2012) AN - 1313014407; 6168191 JF - 2012 Annual Meeting of the American Institute for Chemical Engineering (AIChE 2012) AU - Peterson, Eric Y1 - 2012/10/28/ PY - 2012 DA - 2012 Oct 28 KW - Chemical engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313014407?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=2012+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2012%29&rft.atitle=The+Issues+and+Opportunities+Associated+with+Recycle+and+Reuse+of+Strategic+and+Critical+Materials&rft.au=Peterson%2C+Eric&rft.aulast=Peterson&rft.aufirst=Eric&rft.date=2012-10-28&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=2012+Annual+Meeting+of+the+American+Institute+for+Chemical+Engineering+%28AIChE+2012%29&rft.issn=&rft_id=info:doi/ L2 - https://aiche.confex.com/aiche/2012/webprogram/start.html LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - JOUR T1 - Radioactive cesium isotope ratios as a tool for determining dispersal and re-dispersal mechanisms downwind from the Nevada Nuclear Security Site AN - 1780803075; 2016-031178 AB - Fractionation of the two longer-lived radioactive cesium isotopes ( (super 135) Cs and (super 137) Cs) produced by above ground nuclear tests have been measured and used to clarify the dispersal mechanisms of cesium deposited in the area between the Nevada Nuclear Security Site and Lake Mead in the southwestern United States. Fractionation of these isotopes is due to the 135-decay chain requiring several days to completely decay to (super 135) Cs, and the 137-decay chain less than one hour decay to (super 137) Cs. Since the Cs precursors are gases, iodine and xenon, the (super 135) Cs plume was deposited farther downwind than the (super 137) Cs plume. Sediment core samples were obtained from the Las Vegas arm of Lake Mead, sub-sampled and analyzed for (super 135) Cs/ (super 137) Cs ratios by thermal ionization mass spectrometry. The layers proved to have nearly identical highly fractionated isotope ratios. This information is consistent with a model where the cesium was initially deposited onto the land area draining into Lake Mead and the composite from all of the above ground shots subsequently washed onto Lake Mead by high intensity rain and wind storms producing a layering of Cs activity, where each layer is a portion of the composite. Abstract Copyright (2012) Elsevier, B.V. JF - Journal of Environmental Radioactivity AU - Snyder, Darin C AU - Delmore, James E AU - Tranter, Troy AU - Mann, Nick R AU - Abbott, Michael L AU - Olson, John E Y1 - 2012/08// PY - 2012 DA - August 2012 SP - 46 EP - 52 PB - Elsevier, Oxford VL - 110 SN - 0265-931X, 0265-931X KW - United States KW - isotope fractionation KW - plumes KW - dispersivity KW - isotopes KW - Nevada Nuclear Security Site KW - thermal ionization mass spectra KW - mass spectra KW - Clark County Nevada KW - spatial distribution KW - Nevada Test Site KW - Lake Mead KW - radioactive isotopes KW - cesium KW - sediments KW - spectra KW - nuclear explosions KW - Nevada KW - Idaho KW - explosions KW - pollutants KW - alkali metals KW - pollution KW - migration of elements KW - models KW - Cs-137 KW - metals KW - Las Vegas Nevada KW - Sandhole Lake KW - Cs-135 KW - mobilization KW - lake sediments KW - 02C:Geochemistry of rocks, soils, and sediments KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1780803075?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Environmental+Radioactivity&rft.atitle=Radioactive+cesium+isotope+ratios+as+a+tool+for+determining+dispersal+and+re-dispersal+mechanisms+downwind+from+the+Nevada+Nuclear+Security+Site&rft.au=Snyder%2C+Darin+C%3BDelmore%2C+James+E%3BTranter%2C+Troy%3BMann%2C+Nick+R%3BAbbott%2C+Michael+L%3BOlson%2C+John+E&rft.aulast=Snyder&rft.aufirst=Darin&rft.date=2012-08-01&rft.volume=110&rft.issue=&rft.spage=46&rft.isbn=&rft.btitle=&rft.title=Journal+of+Environmental+Radioactivity&rft.issn=0265931X&rft_id=info:doi/10.1016%2Fj.jenvrad.2012.01.019 L2 - http://www.sciencedirect.com/science/journal/0265931X LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data from CAPCAS, Elsevier Scientific Publishers, Amsterdam, Netherlands N1 - Date revised - 2016-01-01 N1 - Number of references - 22 N1 - Document feature - illus. incl. 2 tables, sketch map N1 - Last updated - 2016-04-14 N1 - SubjectsTermNotLitGenreText - alkali metals; cesium; Clark County Nevada; Cs-135; Cs-137; dispersivity; explosions; Idaho; isotope fractionation; isotopes; Lake Mead; lake sediments; Las Vegas Nevada; mass spectra; metals; migration of elements; mobilization; models; Nevada; Nevada Nuclear Security Site; Nevada Test Site; nuclear explosions; plumes; pollutants; pollution; radioactive isotopes; Sandhole Lake; sediments; spatial distribution; spectra; thermal ionization mass spectra; United States DO - http://dx.doi.org/10.1016/j.jenvrad.2012.01.019 ER - TY - JOUR T1 - APPROVED METHOD TO ESTIMATE RADIONUCLIDE EMISSIONS FROM AN OPEN INSTALLATION ACCELERATOR AN - 1032891906; 16966775 AB - Compliance with 40 CFR 61 Subpart H, National Emission Standards for Emissions of Radionuclides Other Than Radon from Department of Energy Facilities, requires determining radionuclide emissions using methods specified in the regulations. These methods do not suit an open installation accelerator operating in an outdoor environment without the containment of a shielded building and defined release points. Radionuclides created by an open installation accelerator are immediately released upon creation and are considered diffuse and fugitive. A representative source term cannot be sampled or measured. A process was developed to estimate the radionuclide source term based on methods contained in National Council on Radiation Protection and Measurements Report 144 and the Monte Carlo N-Particle Extended model. Adjustments were made base on operational parameters and accelerator configuration. The EPA approved the use of this method as an approved alternative to those contained within the standard. JF - Health Physics AU - Sandvig, M AD - Idaho National Laboratory, Idaho Falls, ID 83415-3750, USA Y1 - 2012/08// PY - 2012 DA - Aug 2012 SP - 1 PB - Williams & Wilkins, 351 W. Camden St. Baltimore MD 21201 United States VL - 103 IS - 2 SN - 0017-9078, 0017-9078 KW - Pollution Abstracts; Health & Safety Science Abstracts KW - Monte Carlo simulation KW - EPA KW - Compliance KW - Radioisotopes KW - Emissions KW - Emission standards KW - Radiation measurements KW - Containment KW - Councils KW - H 8000:Radiation Safety/Electrical Safety KW - P 0000:AIR POLLUTION UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1032891906?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Apollution&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Health+Physics&rft.atitle=APPROVED+METHOD+TO+ESTIMATE+RADIONUCLIDE+EMISSIONS+FROM+AN+OPEN+INSTALLATION+ACCELERATOR&rft.au=Sandvig%2C+M&rft.aulast=Sandvig&rft.aufirst=M&rft.date=2012-08-01&rft.volume=103&rft.issue=2&rft.spage=S47&rft.isbn=&rft.btitle=&rft.title=Health+Physics&rft.issn=00179078&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-08-01 N1 - Last updated - 2013-08-12 N1 - SubjectsTermNotLitGenreText - Monte Carlo simulation; EPA; Compliance; Emission standards; Emissions; Radioisotopes; Radiation measurements; Containment; Councils ER - TY - JOUR T1 - Using Unmanned Helicopters to Assess Vegetation Cover in Sagebrush Steppe Ecosystems AN - 1034826240; 17047303 AB - Evaluating vegetation cover is an important factor in understanding the sustainability of many ecosystems. Remote sensing methods with sufficient accuracy could dramatically alter how biotic resources are monitored on both public and private lands. Idaho National Laboratory (INL), in conjunction with the University of Idaho, evaluated whether unmanned aerial vehicles (UAVs) are sufficiently accurate and more efficient than the point-frame field method for monitoring vegetative cover and bare ground in sagebrush steppe ecosystems. These values are of interest to land managers because typically there are limited natural resource scientists and funding for comprehensive ground evaluations. In this project, unmanned helicopters were used to collect still-frame imagery to determine vegetation cover during June and July 2005. The images were used to estimate percent cover for six vegetative cover classes (shrub, dead shrub, grass, forbs, litter, and bare ground). Field plots used to collect imagery and on-the-ground measurements were located on the INL site west of Idaho Falls, Idaho. Ocular assessments of digital imagery were performed using SamplePoint, and the results were compared with field measurements collected using a point-frame method. The helicopter imagery evaluation showed a high degree of agreement with field cover class values for grass, litter, and bare ground and reasonable agreement for dead shrubs. Shrub cover was often overestimated, and forbs were generally underestimated. The helicopter method took 45% less time than the field method. This study demonstrates that UAV technology provides a viable method for monitoring selective types of cover on rangelands and could save time and resources. Evaluar la cobertura vegetal es un importante factor para entender la sustentabilidad de muchos ecosistemas. Metodos de teledeteccion con suficiente precision pueden considerablemente alterar la manera en como los recursos bioticos son monitoreados tanto en propiedad privada y publica. El laboratorio Nacional de Idaho (INL), en conjunto con la universidad de Idaho, evaluaron si vehiculos aereos no tripulados (UAVs) son suficientemente precisos y mas eficientes que los metodos de campo basados en punto de referencia para monitorear la cobertura de las vegetacion y el suelo desnudo en los ecosistemas de pastizales de Artemisia. Estas evaluaciones son de interes para los manejadores de tierra ya que normalmente hay pocos cientificos dedicados al estudio de los recursos naturales asi como escasos recursos monetarios para evaluaciones integrales. En este proyecto, helicopteros no tripulados fueron usados para recolectar imagenes usadas para determinar la cobertura vegetal durante junio y julio de 2005. Las imagenes fueron usadas para estimar el porcentaje de cobertura de seis clases de cubierta vegetal (arbustos, arbustos muertos, pastos, herbaceas, hojarasca y suelo desnudo). Parcelas de campo que fueron usadas para recolectar las imagenes asi como las mediciones en campo fueron localizadas en el sitio INL al oeste de Idaho Falls, Idaho. Evaluaciones oculares de imagenes digitales fueron realizadas usando SamplePoint y los resultados fueron comparados con las mediciones de campo recolectadas usando el metodo de point-frame. La evaluacion de las imagenes recolectadas por el helicoptero mostro un alto grado de correlacion con respecto a las evaluaciones de campo para pastos, hojarasca, y suelo desnudo, y una razonable relacion para plantas muertas. Las cobertura de los arbustos fue regularmente sobrestimado y para las herbaceas fueron generalmente subestimadas. El metodo del helicoptero tomo 45% menos tiempo que el metodo de campo. Este estudio demostro que la tecnologia UAV proporciono un metodo viable para monitorear los tipos selectivos de cobertura en los pastizales y podria salvar tiempo y recursos. JF - Rangeland Ecology & Management AU - Breckenridge, Robert P AU - Dakins, Maxine AU - Bunting, Stephen AU - Harbour, Jerry L AU - Lee, Randy D AD - Environmental Scientist, Idaho National Laboratory, Idaho Falls, ID 83415, USA, Robert.Breckenridge@inl.gov Y1 - 2012/07// PY - 2012 DA - Jul 2012 SP - 362 EP - 370 PB - Society for Range Management VL - 65 IS - 4 SN - 1550-7424, 1550-7424 KW - Sustainability Science Abstracts; Ecology Abstracts KW - Ecosystems KW - Forbs KW - Grasses KW - Hay KW - Litter KW - Rangelands KW - Remote sensing KW - Shrubs KW - Staphylococcal enterotoxin I KW - Steppes KW - Vegetation KW - Vegetation cover KW - helicopters KW - Artemisia KW - USA, Idaho KW - Cameroon, Sud, Campo KW - M3 1010:Issues in Sustainable Development KW - D 04060:Management and Conservation UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1034826240?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aecology&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Rangeland+Ecology+%26+Management&rft.atitle=Using+Unmanned+Helicopters+to+Assess+Vegetation+Cover+in+Sagebrush+Steppe+Ecosystems&rft.au=Breckenridge%2C+Robert+P%3BDakins%2C+Maxine%3BBunting%2C+Stephen%3BHarbour%2C+Jerry+L%3BLee%2C+Randy+D&rft.aulast=Breckenridge&rft.aufirst=Robert&rft.date=2012-07-01&rft.volume=65&rft.issue=4&rft.spage=362&rft.isbn=&rft.btitle=&rft.title=Rangeland+Ecology+%26+Management&rft.issn=15507424&rft_id=info:doi/10.2111%2FREM-D-10-00031.1 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-08-01 N1 - Number of references - 42 N1 - Last updated - 2012-10-08 N1 - SubjectsTermNotLitGenreText - Shrubs; Rangelands; Litter; Grasses; Forbs; Remote sensing; Vegetation; Staphylococcal enterotoxin I; Hay; Steppes; Vegetation cover; Ecosystems; helicopters; Artemisia; USA, Idaho; Cameroon, Sud, Campo DO - http://dx.doi.org/10.2111/REM-D-10-00031.1 ER - TY - CPAPER T1 - Universal model for nanoparticle size effects T2 - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AN - 1313088146; 6146061 JF - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AU - Farrell, Helen Y1 - 2012/06/24/ PY - 2012 DA - 2012 Jun 24 KW - nanoparticles KW - Models UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313088146?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.atitle=Universal+model+for+nanoparticle+size+effects&rft.au=Farrell%2C+Helen&rft.aulast=Farrell&rft.aufirst=Gabriela&rft.date=2008-01-01&rft.volume=&rft.issue=40&rft.spage=167&rft.isbn=&rft.btitle=&rft.title=Historia%2C+Antropologia+y+Fuentes+Orales&rft.issn=11361700&rft_id=info:doi/ L2 - http://www.snakeriveracs.com/Norm%202012/Final%20Full__NORM%202012_web.pdf LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Comparison of Fabry-Perot etalons for high resolution LIBS analysis T2 - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AN - 1313087006; 6146008 JF - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AU - Hatch, Jeremy AU - McJunkin, Timothy AU - Scott, Jill Y1 - 2012/06/24/ PY - 2012 DA - 2012 Jun 24 KW - Chemistry KW - Applied sciences UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313087006?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.atitle=Comparison+of+Fabry-Perot+etalons+for+high+resolution+LIBS+analysis&rft.au=Hatch%2C+Jeremy%3BMcJunkin%2C+Timothy%3BScott%2C+Jill&rft.aulast=Hatch&rft.aufirst=Jeremy&rft.date=2012-06-24&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://www.snakeriveracs.com/Norm%202012/Final%20Full__NORM%202012_web.pdf LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Further studies of the effects of gamma irradiation on a TBP process solvent T2 - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AN - 1313071091; 6146038 JF - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AU - McDowell, Rocklan AU - Olson, Lonnie AU - Tillotson, Richard AU - Law, Jack AU - Peterman, Dean Y1 - 2012/06/24/ PY - 2012 DA - 2012 Jun 24 KW - g Radiation KW - Solvents KW - Abiotic factors KW - Light effects UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313071091?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.atitle=Further+studies+of+the+effects+of+gamma+irradiation+on+a+TBP+process+solvent&rft.au=McDowell%2C+Rocklan%3BOlson%2C+Lonnie%3BTillotson%2C+Richard%3BLaw%2C+Jack%3BPeterman%2C+Dean&rft.aulast=McDowell&rft.aufirst=Rocklan&rft.date=2012-06-24&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://www.snakeriveracs.com/Norm%202012/Final%20Full__NORM%202012_web.pdf LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Radiolytic stability of a modified TALSPEAK process T2 - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AN - 1313064763; 6146041 JF - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AU - Grimes, Travis AU - Tillotson, Richard AU - Martin, Leigh Y1 - 2012/06/24/ PY - 2012 DA - 2012 Jun 24 KW - Chemistry KW - Applied sciences UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313064763?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.atitle=Radiolytic+stability+of+a+modified+TALSPEAK+process&rft.au=Grimes%2C+Travis%3BTillotson%2C+Richard%3BMartin%2C+Leigh&rft.aulast=Grimes&rft.aufirst=Travis&rft.date=2012-06-24&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://www.snakeriveracs.com/Norm%202012/Final%20Full__NORM%202012_web.pdf LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Chemistry of the Nuclear Fuel Cycle - Applied Aspects T2 - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AN - 1313013714; 6146036 JF - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AU - Todd, Terry Y1 - 2012/06/24/ PY - 2012 DA - 2012 Jun 24 KW - Nuclear fuels KW - Fuels UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313013714?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.atitle=Chemistry+of+the+Nuclear+Fuel+Cycle+-+Applied+Aspects&rft.au=Todd%2C+Terry&rft.aulast=Todd&rft.aufirst=Terry&rft.date=2012-06-24&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://www.snakeriveracs.com/Norm%202012/Final%20Full__NORM%202012_web.pdf LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - CPAPER T1 - Electrochemical Oxidation of Americium T2 - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AN - 1312984394; 6146020 JF - 67th American Chemical Society Northwest Regional Meeting (NORM 2012) AU - Uhnak, Nic AU - Russell, Dale AU - Mincher, Bruce Y1 - 2012/06/24/ PY - 2012 DA - 2012 Jun 24 KW - Oxidation KW - Americium KW - Electrochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1312984394?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.atitle=Electrochemical+Oxidation+of+Americium&rft.au=Uhnak%2C+Nic%3BRussell%2C+Dale%3BMincher%2C+Bruce&rft.aulast=Uhnak&rft.aufirst=Nic&rft.date=2012-06-24&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=67th+American+Chemical+Society+Northwest+Regional+Meeting+%28NORM+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://www.snakeriveracs.com/Norm%202012/Final%20Full__NORM%202012_web.pdf LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - JOUR T1 - IMPROVING THE INTEGRAL FAST REACTOR'S PROPOSED SALT WASTE MANAGEMENT SYSTEM AN - 1038318067; 16895655 AB - An often cited weakness of the Integral Fast Reactor (IFR) concept is that the chloride salt-based radioactive waste generated by its electrorefiner (ER) cannot be vitrified. Although that assertion is literally true, it is also misleading because it would be quite simple to recycle that waste's chloride and vitrify its cationic components (mostly alkali metals and fission products). Producing this alternative to Argonne National Laboratory's ceramic waste form would entail vitrification of a mixture of orthophosphoric acid, ferric oxide, and powdered ER salt with a melter able to efficiently disengage gas bub- bles, e.g., a Stir Melter. The HCl evolved by this process would be absorbed by an aqueous lithium/potassium hydroxide scrub solution, which would then be dried and recycled as fresh ER electrolyte. Because radioiodide would otherwise accumulate in the ER salt, the caustic scrub solution would occasionally be contacted with cuprous or silver chloride before recycle. This scenario's primary advantages would be much lower cost and approximately fivefold greater effective waste loading. This paper describes the experimental work supporting these contentions. JF - Nuclear Technology AU - Siemer, Darryl D AD - Idaho National Laboratory, Idaho Falls, Idaho 83402, d.siemer@hotmail.com Y1 - 2012/06// PY - 2012 DA - Jun 2012 SP - 341 EP - 352 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 3 SN - 0029-5450, 0029-5450 KW - Environment Abstracts KW - Ceramics KW - Salts KW - Electrolytes KW - Chlorides KW - Radioactive wastes KW - Alkali metals KW - Hazardous wastes KW - Lithium KW - Waste management KW - ENA 14:Radiological Contamination UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1038318067?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Technology&rft.atitle=IMPROVING+THE+INTEGRAL+FAST+REACTOR%27S+PROPOSED+SALT+WASTE+MANAGEMENT+SYSTEM&rft.au=Siemer%2C+Darryl+D&rft.aulast=Siemer&rft.aufirst=Darryl&rft.date=2012-06-01&rft.volume=178&rft.issue=3&rft.spage=341&rft.isbn=&rft.btitle=&rft.title=Nuclear+Technology&rft.issn=00295450&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-11-01 N1 - Number of references - 20 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Ceramics; Salts; Electrolytes; Radioactive wastes; Chlorides; Alkali metals; Lithium; Hazardous wastes; Waste management ER - TY - JOUR T1 - Development of a HEX-Z Partially Homogenized Benchmark Model for the FFTF Isothermal Physics Measurements AN - 1671284027; 16893216 AB - A series of isothermal physics measurements was performed as part of an acceptance testing program for the Fast Flux Test Facility (FFTF). A HEX-Z partially homogenized benchmark model of the FFTF fully loaded core configuration was developed for evaluation of these measurements. Evaluated measurements include the critical eigenvalue of the fully loaded core, two neutron spectra, 32 reactivity effects measurements, an isothermal temperature coefficient, and low-energy gamma and electron spectra. Dominant uncertainties in the critical configuration include the placement of radial shielding around the core, reactor core assembly pitch, composition of the stainless steel components, plutonium content in the fuel pellets, and boron content in the absorber pellets. Calculations of criticality, reactivity effects measurements, and the isothermal temperature coefficient using Monte Carlo N-Particle version 5.1.40 (MCNP5) and ENDF/B-VII.0 cross sections with the benchmark model are in good agreement with the benchmark experiment measurements. There is little agreement between calculated and measured spectral measurements. This benchmark evaluation has been added to the International Handbook of Evaluated Reactor Physics Benchmark Experiments. JF - Nuclear Science and Engineering AU - Bess, John D AD - Idaho National Laboratory, P.O. Box 1625, MS 3855, Idaho Falls, Idaho 83415 John.Bess@INL.gov Y1 - 2012/05// PY - 2012 DA - May 2012 SP - 32 EP - 40 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 171 IS - 1 SN - 0029-5639, 0029-5639 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Mathematical models KW - Eigenvalues KW - Computer simulation KW - Monte Carlo methods KW - Benchmarking KW - Spectra KW - Coefficients KW - Pellets UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1671284027?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Science+and+Engineering&rft.atitle=Development+of+a+HEX-Z+Partially+Homogenized+Benchmark+Model+for+the+FFTF+Isothermal+Physics+Measurements&rft.au=Bess%2C+John+D&rft.aulast=Bess&rft.aufirst=John&rft.date=2012-05-01&rft.volume=171&rft.issue=1&rft.spage=32&rft.isbn=&rft.btitle=&rft.title=Nuclear+Science+and+Engineering&rft.issn=00295639&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-09-01 N1 - Number of references - 22 N1 - Last updated - 2015-04-09 ER - TY - JOUR T1 - Toward reconciling magnitude discrepancies estimated from paleoearthquake data AN - 1017954248; 2012-054555 JF - Seismological Research Letters AU - Carpenter, N Seth AU - Payne, Suzette J AU - Schafer, Annette L Y1 - 2012/05// PY - 2012 DA - May 2012 SP - 555 EP - 565 PB - Seismological Society of America, El Cerrito, CA VL - 83 IS - 3 SN - 0895-0695, 0895-0695 KW - North America KW - technology KW - paleoseismicity KW - geologic hazards KW - Basin and Range Province KW - statistical analysis KW - magnitude KW - history KW - seismic risk KW - natural hazards KW - risk assessment KW - algorithms KW - earthquakes KW - regression analysis KW - faults KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1017954248?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Seismological+Research+Letters&rft.atitle=Toward+reconciling+magnitude+discrepancies+estimated+from+paleoearthquake+data&rft.au=Carpenter%2C+N+Seth%3BPayne%2C+Suzette+J%3BSchafer%2C+Annette+L&rft.aulast=Carpenter&rft.aufirst=N&rft.date=2012-05-01&rft.volume=83&rft.issue=3&rft.spage=555&rft.isbn=&rft.btitle=&rft.title=Seismological+Research+Letters&rft.issn=08950695&rft_id=info:doi/10.1785%2Fgssrl.83.3.555 L2 - http://srl.geoscienceworld.org/ LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Abstract, Copyright, Seismological Society of America | Reference includes data from GeoScienceWorld, Alexandria, VA, United States N1 - Date revised - 2012-01-01 N1 - Number of references - 42 N1 - PubXState - CA N1 - Document feature - illus. incl. 2 tables N1 - Last updated - 2016-10-25 N1 - SubjectsTermNotLitGenreText - algorithms; Basin and Range Province; earthquakes; faults; geologic hazards; history; magnitude; natural hazards; North America; paleoseismicity; regression analysis; risk assessment; seismic risk; statistical analysis; technology DO - http://dx.doi.org/10.1785/gssrl.83.3.555 ER - TY - JOUR T1 - REVIEW OF THE POTENTIAL OF NUCLEAR HYDROGEN FOR ADDRESSING ENERGY SECURITY AND CLIMATE CHANGE AN - 1024665231; 16726394 AB - Nuclear energy has the potential to exert a major positive impact on energy security and climate change by coupling it to the transportation sector, primarily through hydrogen production. In the short term, this coupling will provide carbon-free hydrogen for upgrading increasingly lower-quality petroleum resources such as oil sands, offsetting carbon emissions associated with steam methane reforming. In the intermediate term, nuclear hydrogen will be needed for large-scale production of infrastructure-compatible synthetic liquid fuels. In the long term, there is great potential for the use of hydrogen as a direct vehicle fuel, most likely in the form of light-duty pluggable hybrid hydrogen fuel cell vehicles (HFCVs). This paper presents a review of the potential benefits of large-scale nuclear hydrogen production for energy security (i.e., displacing imported petroleum) and reduction of greenhouse gas emissions. Life-cycle benefits of nuclear energy in this context are presented, with reference to recent major publications on this topic. The status of U.S. and international nuclear hydrogen research programs is discussed. Industry progress toward consumer-grade HFCVs is also examined. JF - Nuclear Technology AU - O'Brien, James E AD - Idaho National Laboratory, 2525 N Fremont Ave , MS 3885, Idaho Falls, Idaho 83415, james.obrien@inl.gov Y1 - 2012/04// PY - 2012 DA - April 2012 SP - 55 EP - 65 PB - American Nuclear Society, Inc., 555 N. Kensington Ave. La Grange Park IL 60525 United States VL - 178 IS - 1 SN - 0029-5450, 0029-5450 KW - Sustainability Science Abstracts KW - Security KW - USA KW - Petroleum KW - Reviews KW - Fuels KW - Nuclear fuels KW - Climate change KW - Emissions KW - Nuclear energy KW - Hydrogen KW - M3 1010:Issues in Sustainable Development UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1024665231?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Assamodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Technology&rft.atitle=REVIEW+OF+THE+POTENTIAL+OF+NUCLEAR+HYDROGEN+FOR+ADDRESSING+ENERGY+SECURITY+AND+CLIMATE+CHANGE&rft.au=O%27Brien%2C+James+E&rft.aulast=O%27Brien&rft.aufirst=James&rft.date=2012-04-01&rft.volume=178&rft.issue=1&rft.spage=55&rft.isbn=&rft.btitle=&rft.title=Nuclear+Technology&rft.issn=00295450&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-07-01 N1 - Number of references - 53 N1 - Last updated - 2016-07-07 N1 - SubjectsTermNotLitGenreText - Security; Fuels; Reviews; Petroleum; Climate change; Nuclear fuels; Emissions; Nuclear energy; Hydrogen; USA ER - TY - JOUR T1 - A new interpretation of deformation rates in the Snake River plain and adjacent basin and range regions based on GPS measurements AN - 1015459756; 2012-049978 AB - Within the Northern Basin and Range Province, USA, we estimate horizontal velocities for 405 sites using Global Positioning System (GPS) phase data collected from 1994 to 2010. The velocities, together with geologic, volcanic, and earthquake data, reveal a slowly deforming region within the Snake River plain in Idaho and Owyhee-Oregon Plateau in Oregon separated from the actively extending adjacent Basin and Range regions by shear. Our results show a NE-oriented extensional strain rate of 5.6 + or - 0.7 X 10 (super -9) yr (super -1) in the Centennial Tectonic Belt and an approximately E-oriented extensional strain rate of 3.5 + or - 0.2 X 10 (super -9) yr (super -1) in the Great Basin. These extensional rates contrast with the very low strain rate within the 125 km X 650 km region of the Snake River plain and Owyhee-Oregon Plateau, which is indistinguishable from zero (-0.1 + or - 0.4 X 10 (super -9) yr (super -1) ). Inversions of the velocities with dyke-opening models indicate that rapid extension by dyke intrusion in volcanic rift zones, as previously hypothesized, is not currently occurring in the Snake River plain. This slow internal deformation, in contrast to the rapidly extending adjacent Basin and Range regions, indicates shear along the boundaries of the Snake River plain. We estimate right-lateral shear with slip rates of 0.3-1.4 mm yr (super -1) along the northwestern boundary adjacent to the Centennial Tectonic Belt and left-lateral oblique extension with slip rates of 0.5-1.5 mm yr (super -1) along the southeastern boundary adjacent to the Intermountain Seismic Belt. The fastest lateral shearing evident in the GPS occurs near the Yellowstone Plateau where strike-slip focal mechanisms and faults with observed strike-slip components of motion are documented. The regional velocity gradients are best fit by nearby poles of rotation for the Centennial Tectonic Belt, Snake River plain, Owyhee-Oregon Plateau, and eastern Oregon, indicating that clockwise rotation is not locally driven by Yellowstone hotspot volcanism, but instead by extension to the south across the Wasatch Fault due to gravitational collapse and by shear in the Walker Lane Belt resulting from Pacific-Northern America relative plate motion. Abstract Copyright (2012), RAS. JF - Geophysical Journal International AU - Payne, S J AU - McCaffrey, R AU - King, R W AU - Kattenhorn, S A Y1 - 2012/04// PY - 2012 DA - April 2012 SP - 101 EP - 122 PB - Wiley-Blackwell on behalf of The Royal Astronomical Society, the Deutsche Geophysikalische Gesellschaft and the European Geophysical Society VL - 189 IS - 1 SN - 0956-540X, 0956-540X KW - United States KW - North America KW - Idaho KW - hot spots KW - Global Positioning System KW - technology KW - Basin and Range Province KW - strain KW - plate boundaries KW - mantle KW - Walker Lane KW - Owyhee Mountains KW - measurement KW - Oregon KW - kinematics KW - plate tectonics KW - neotectonics KW - Yellowstone Plateau KW - tectonics KW - Snake River plain KW - seismotectonics KW - crust KW - 18:Solid-earth geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1015459756?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Geophysical+Journal+International&rft.atitle=A+new+interpretation+of+deformation+rates+in+the+Snake+River+plain+and+adjacent+basin+and+range+regions+based+on+GPS+measurements&rft.au=Payne%2C+S+J%3BMcCaffrey%2C+R%3BKing%2C+R+W%3BKattenhorn%2C+S+A&rft.aulast=Payne&rft.aufirst=S&rft.date=2012-04-01&rft.volume=189&rft.issue=1&rft.spage=101&rft.isbn=&rft.btitle=&rft.title=Geophysical+Journal+International&rft.issn=0956540X&rft_id=info:doi/10.1111%2Fj.1365-246X.2012.05370.x L2 - http://www.blackwellpublishing.com/journal.asp?ref=0956-540X LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2012, American Geosciences Institute. Reference includes data from John Wiley & Sons, Chichester, United Kingdom N1 - Date revised - 2012-01-01 N1 - Number of references - 105 N1 - Document feature - illus. incl. 3 tables, geol. sketch maps N1 - Last updated - 2012-06-07 N1 - SubjectsTermNotLitGenreText - Basin and Range Province; crust; Global Positioning System; hot spots; Idaho; kinematics; mantle; measurement; neotectonics; North America; Oregon; Owyhee Mountains; plate boundaries; plate tectonics; seismotectonics; Snake River plain; strain; technology; tectonics; United States; Walker Lane; Yellowstone Plateau DO - http://dx.doi.org/10.1111/j.1365-246X.2012.05370.x ER - TY - JOUR T1 - Enthalpy of gamma-delta Transition in Ternary U-Pu-Zr Fuel Alloys AN - 1372611671; 18029465 AB - Several ternary nuclear fuel alloys were investigated using differential scanning calorimetry. The results were evaluated using a curvefitting routine, and the enthalpies of individual phase transitions were determined. Individual transitions were assigned with reference to published ternary phase diagrams, and a compositional analysis for the partial transformations of each alloy allowed the first determination of the gamma-delta transition enthalpy for the ternary fuel alloys. These results agree with prior research for binary fuel alloys that found the enthalpy to be approximately 5 kJ per mole with some variation depending on the exact composition within the broad delta-UZr2 phase range. The comparable results suggest that the heat of solution for the zirconium in the ternary delta-phase is similar to that for zirconium in the binary deltaphase, which might be expected; however it is possible that the activities of Pu and Zr in the delta phase may be self-compensating. JF - AIP Conference Proceedings AU - Papesch, Cynthia AU - O'Holleran, Thomas AU - Mariani, Robert AU - Cromwell, Matthew AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Conferences KW - Fuels KW - Nuclear fuels KW - Alloys KW - Calorimetry KW - Zirconium KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372611671?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Enthalpy+of+gamma-delta+Transition+in+Ternary+U-Pu-Zr+Fuel+Alloys&rft.au=Papesch%2C+Cynthia%3BO%27Holleran%2C+Thomas%3BMariani%2C+Robert%3BCromwell%2C+Matthew&rft.aulast=Papesch&rft.aufirst=Cynthia&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-09-03 N1 - SubjectsTermNotLitGenreText - Conferences; Fuels; Nuclear fuels; Calorimetry; Alloys; Zirconium; Technology ER - TY - JOUR T1 - Effect of Materials on the Autoignition of Cyclopentane AN - 1372611618; 18029440 AB - Cyclopentane, a flammable hydrocarbon, is being considered as a working fluid for waste heat recovery applications. Experiments were conducted to determine the ignition delay time (IDT) of cyclopentane using an Ignition Quality Test (IQT) device. Two sets of experiments were conducted per ASTM D6890 (with exception to charge pressure and temperature) to determine ignition delay of the fuel at atmospheric pressure for normal air (~21% oxygen) and vitiated air (13.3% oxygen) at a temperature of 530 degree C. Operation of the IQT device at a much lower pressure (1 bar) than normal operation (21.1 bar) led to very rich conditions and wetting of the stainless steel chamber walls. Catalytic effects produced small IDTs. Experiments were repeated with a modified injector to prevent wall wetting, resulting in average IDTs that are substantially longer. JF - AIP Conference Proceedings AU - Guillen, Donna AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Waste heat KW - Oxygen KW - Conferences KW - Fuels KW - Temperature KW - Flammability KW - Atmospheric pressure KW - Steel KW - Technology KW - ENA 01:Air Pollution UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372611618?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Effect+of+Materials+on+the+Autoignition+of+Cyclopentane&rft.au=Guillen%2C+Donna&rft.aulast=Guillen&rft.aufirst=Donna&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Waste heat; Oxygen; Conferences; Fuels; Temperature; Flammability; Atmospheric pressure; Steel; Technology ER - TY - JOUR T1 - Neptunium Oxide Reduction Technique AN - 1372611582; 18029464 AB - A process to reduce neptunium oxide (NpO(2)) to neptunium metal was developed. NpO(2) is combined with calcium and heated to temperatures between 650 degree C and 850 degree C under argon. Three successful trials were conducted to yield a total of approximately 20 g of neptunium with purity estimated greater than 97%. The metal is needed to determine important thermal and phase properties of binary neptunium systems as well as fresh metallic fuels that simulate the compositions of recycled fuel. The process development was necessary since most of the neptunium available is present as the oxide. Future efforts are planned for understanding the process parameters in relation to neptunium purity, and for purifying the metal produced. JF - AIP Conference Proceedings AU - Squires, Leah AU - Lessing, Paul AU - Stuart, James AU - Forsmann, Bryan AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Metals KW - Argon KW - Calcium KW - Conferences KW - Fuels KW - Temperature KW - Neptunium KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372611582?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Neptunium+Oxide+Reduction+Technique&rft.au=Squires%2C+Leah%3BLessing%2C+Paul%3BStuart%2C+James%3BForsmann%2C+Bryan&rft.aulast=Squires&rft.aufirst=Leah&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Metals; Calcium; Argon; Conferences; Fuels; Temperature; Neptunium; Technology ER - TY - JOUR T1 - Computational Studies of the Formation and Migration of Atomic Defect Clusters in UO2 under Irradiation AN - 1372608971; 18028484 AB - The production and migration of point defects and defect clusters in uranium dioxide (UO2) under irradiation are two important mechanisms of radiation damage and microstructure changes in this material. Investigating the atomistic details of these two processes is critical for understanding the microstructural evolution of UO2 under irradiation. Here we first use molecular dynamics simulations to investigate collision cascade induced defect production at the picosecond timescale at both 300 K and 1000 K. The energy of the primary knock-on atom is 2 keV. Based on 200+ cascade simulations, we obtain the distributions of defect clusters in terms of their compositions and sizes at both temperatures. We then use temperature accelerated dynamics to investigate the migration barriers of these interstitial and vacancy clusters and determine their mobility. Finally we examine the interaction between different types of defect clusters and discuss their opportunities of forming larger clusters at long timescales. JF - AIP Conference Proceedings AU - Bai, Xian-Ming AU - El-Azab, Anter AU - Allen, Todd AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Mobility KW - Conferences KW - Irradiation KW - Uranium KW - Temperature KW - Simulation KW - Migration KW - Technology KW - ENA 14:Radiological Contamination UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372608971?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Computational+Studies+of+the+Formation+and+Migration+of+Atomic+Defect+Clusters+in+UO2+under+Irradiation&rft.au=Bai%2C+Xian-Ming%3BEl-Azab%2C+Anter%3BAllen%2C+Todd&rft.aulast=Bai&rft.aufirst=Xian-Ming&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Conferences; Mobility; Uranium; Irradiation; Temperature; Simulation; Migration; Technology ER - TY - JOUR T1 - TEM Characterization of Irradiated RERTR Dispersion Fuels AN - 1372607368; 18028040 AB - The USA fuels program on Reduced Enrichment Research and Test Reactors (RERTR) is to develop low enrichment fuels to be used in the research and test reactors. Dispersion type plate fuels are popular for many research and test reactors, a special class of LWRs. A typical dispersion fuel plate in a test reactor consists of three layers with the outer layers of aluminum cladding and the middle layer of aluminum alloy dispersed with U-xMo (x=7-10 in wt%) or U3Si2 fuel particles. Fuel- Matrix Interaction (FMI) layer can develop as a result of fuel fabrication and reactor irradiation. The microstructural stability of the fuel under irradiation could strongly affect the fuel performance. This work reports the microstructure characterization using TEM on the irradiated RERTR dispersion fuels. The detailed microstrucural features will be analyzed and compared with the results in literature. The impact of the observed microstructure on fuel performance will be discussed. JF - AIP Conference Proceedings AU - Gan, Jian AU - Keiser, Dennis AU - Miller, Brandon AU - Robinson, Adam AU - Jue, Jan-Fong AU - Medvedev, Pavel AU - Wachs, Daniel AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - USA KW - Conferences KW - Fuels KW - Irradiation KW - Aluminum KW - Alloys KW - Particulates KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372607368?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=TEM+Characterization+of+Irradiated+RERTR+Dispersion+Fuels&rft.au=Gan%2C+Jian%3BKeiser%2C+Dennis%3BMiller%2C+Brandon%3BRobinson%2C+Adam%3BJue%2C+Jan-Fong%3BMedvedev%2C+Pavel%3BWachs%2C+Daniel&rft.aulast=Gan&rft.aufirst=Jian&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Conferences; Irradiation; Fuels; Aluminum; Alloys; Particulates; Technology; USA ER - TY - JOUR T1 - Development of W-UO2/CeO2 CERMET Fuels for Ultra High Temperature Reactor Applications AN - 1372607104; 18028432 AB - Historical and contemporary space reactor designs require the use of refractory materials to withstand steady state operational temperatures that range from 1000 K to 3000 K. This paper outlines the initial steps of a fuels program to recapture the technology required to fabricate W-UO2 fuel forms for hydrogen cooled nuclear rocket applications. The results and lessons learned from a robust literature search of the ANL CERMET fuels program and the General Electric 710 programs are detailed in this study. This paper also describes an initial effort to spheroidize particles of CeO2 which are also coated with tungsten to a 40 vol.% ratio. The particles are consolidated into fuel specimens and prototypic fuel element segments via Pulsed Electric Current Sintering (PECS) and Hot Isostatic Pressing (HIPing) techniques. Comparisons are made between the microstructure and basic properties of the specimens fabricated by PECS and HIP techniques. JF - AIP Conference Proceedings AU - Webb, Jonathan AU - Werner, James AU - Hickman, Robert AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Historical account KW - Nuclear reactors KW - Conferences KW - Fuels KW - High temperature KW - Nuclear fuels KW - Particulates KW - Technology KW - Tungsten KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372607104?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Development+of+W-UO2%2FCeO2+CERMET+Fuels+for+Ultra+High+Temperature+Reactor+Applications&rft.au=Webb%2C+Jonathan%3BWerner%2C+James%3BHickman%2C+Robert&rft.aulast=Webb&rft.aufirst=Jonathan&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Historical account; Nuclear reactors; Conferences; High temperature; Fuels; Nuclear fuels; Particulates; Tungsten; Technology ER - TY - JOUR T1 - Computational Crystal Plasticity with the Jacobian-Free Newton Krylov Method AN - 1372606673; 18026581 AB - The primary objective of this work is to study the interaction between grain growth and plastic deformation, focusing on dislocation glide along preferred slip planes. Implicit implementations of crystal plasticity finite element method (CPFEM) are usually solved using Newton's method. However, the inherent non-linearity in the flow rule model that characterizes the crystal slip system deformation makes it difficult to form the exact analytical Jacobian needed by Newton's method. Here we analyze how to circumvent this problem by using Jacobian Free Newton Krylov (JFNK), as it does not require a Jacobian. JFNK is used to solve the system of fully coupled implicit non-linear PDEs by using an approximation to the jacobian, in contrast to the traditional Newton solve thus significantly reducing the computational time. Further studies will be aimed at extending this work in simulating the effects of plasticity on 3-D microstructural evolution to characterize performance of nuclear fuels. JF - AIP Conference Proceedings AU - Chockalingam, Karthik AU - Tonks, Micheal AU - Millett, Paul AU - Biner, Bulent AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Finite element method KW - Conferences KW - Nuclear fuels KW - Grains KW - Deformation KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372606673?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Computational+Crystal+Plasticity+with+the+Jacobian-Free+Newton+Krylov+Method&rft.au=Chockalingam%2C+Karthik%3BTonks%2C+Micheal%3BMillett%2C+Paul%3BBiner%2C+Bulent&rft.aulast=Chockalingam&rft.aufirst=Karthik&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Finite element method; Conferences; Nuclear fuels; Grains; Technology; Deformation ER - TY - JOUR T1 - Compatibility of Metallic Transmutation Fuels with Fe-Based Alloys AN - 1372606650; 18027422 AB - Out-of-pile diffusion couple studies have been conducted over the past several years to better understand the complex phase evolution that occurs when U, Pu-based metallic nuclear fuel with and without minor actinides (Am, Np) and rare earth fission products (Ce, La, Pr, Nd) contacts Febased cladding alloys at elevated temperature. These studies are being performed to support in-pile tests of similar fuels and bound the expected behavior in terms of formation of brittle or low-melting point phases due to interdiffusion of fuel constituents into the cladding and cladding constituents into the fuel. The complex phase evolution observed will be discussed in terms of available equilibrium phase diagram data and the relation to anticipated in-pile behavior. JF - AIP Conference Proceedings AU - Cole, James AU - O'Holleran, Thomas AU - Mariani, Robert AU - Keiser, Dennis AU - Kennedy, J AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Fission products KW - Conferences KW - Fuels KW - Nuclear fuels KW - Temperature KW - Alloys KW - Diffusion KW - Actinides KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372606650?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Compatibility+of+Metallic+Transmutation+Fuels+with+Fe-Based+Alloys&rft.au=Cole%2C+James%3BO%27Holleran%2C+Thomas%3BMariani%2C+Robert%3BKeiser%2C+Dennis%3BKennedy%2C+J&rft.aulast=Cole&rft.aufirst=James&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-04-09 N1 - SubjectsTermNotLitGenreText - Fission products; Conferences; Fuels; Nuclear fuels; Temperature; Alloys; Diffusion; Technology; Actinides ER - TY - JOUR T1 - Multiscale Modeling of Reactor Fuel Restructuring AN - 1372606353; 18026579 AB - Due to temperature and stress gradients, as well as radiation effects, the grain and pore structure of reactor fuel changes significantly during its lifetime. This restructuring in the fuel has a significant impact on thermal conductivity and fission gas release, and therefore is of critical importance when predicting fuel performance. To gain a better understanding of fuel restructuring, we use a combination of atomistic and mesoscale phase field simulations to investigate GB and pore migration and how the two interact. We also compare the effects of stress and temperature gradients. Finally, we demonstrate how this information can be used to improve existing fuel performance materials models. JF - AIP Conference Proceedings AU - Tonks, Michael AU - Millett, Paul AU - Biner, Bulent AU - Zhang, Liangzhe AU - Bai, Xianming AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Conferences KW - Thermal conductivity KW - Fuels KW - Temperature KW - Stress KW - Simulation KW - Grains KW - Migration KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372606353?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Multiscale+Modeling+of+Reactor+Fuel+Restructuring&rft.au=Tonks%2C+Michael%3BMillett%2C+Paul%3BBiner%2C+Bulent%3BZhang%2C+Liangzhe%3BBai%2C+Xianming&rft.aulast=Tonks&rft.aufirst=Michael&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Thermal conductivity; Conferences; Fuels; Temperature; Simulation; Stress; Grains; Migration; Technology ER - TY - JOUR T1 - Creep-Fatigue Behavior of an Advanced Austenitic Alloy Strengthened by Nano-Scale MC Precipitates AN - 1372605817; 18027904 AB - An advanced austenitic alloy, HT-UPS (high temperature-ultrafine precipitate strengthened), is a potential candidate material for structural components of fast reactors and energy-conversion systems. The HT-UPS alloy, with a composition based largely on modifications to 316 stainless steel (SS), demonstrates improved creep resistance through additions of Ti and Nb that form nano-scale MC precipitates. The cycles to failure at 650 degree C of HT-UPS and 316 SS are similar in fatigue and creep-fatigue despite differences in peak stress profiles and the deformed microstructures. Internal grain boundary damage resulting from the tensile hold is present in the form of fine cracks for longer hold times, and substantially more of these internal cracks are visible in 316 SS than HT-UPS. The cycled dislocation substructure in 316 SS has regions with an equiaxed cellular structure and regions with a lath structure, whereas tangles of dislocations are pinned at the nanoscale MC precipitates in HT-UPS. JF - AIP Conference Proceedings AU - Carroll, Laura AU - Carroll, Mark AU - Wright, Richard AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Austenitic stainless steels KW - 316 KW - Creep KW - Fatigue KW - Conferences KW - Behavior KW - Alloys KW - Stress KW - Steel KW - Grains KW - Technology KW - ENA 07:General UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372605817?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Creep-Fatigue+Behavior+of+an+Advanced+Austenitic+Alloy+Strengthened+by+Nano-Scale+MC+Precipitates&rft.au=Carroll%2C+Laura%3BCarroll%2C+Mark%3BWright%2C+Richard&rft.aulast=Carroll&rft.aufirst=Laura&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Creep; Fatigue; Behavior; Conferences; Stress; Alloys; Steel; Grains; Technology ER - TY - JOUR T1 - Kinetic Monte Carlo Simulation of He Bubble Nucleation at Different Types of Grain Boundaries in Mo AN - 1372605359; 18028810 AB - The kinetic Monte Carlo (KMC) algorithm, which offers a relatively long time description of microstructural evolution at atomistic level, is adopted to investigate the Helium bubble nucleation process at grain boundaries (GBs) in Mo. To make KMC simulations robust, corresponding molecular dynamics simulations are consulted, which provide the nucleation mechanisms in detail within various settings. In the current work, the He bubble nucleation process at three types (twin, tilt and twist) of GBs is studied with randomly distributed He atoms as the initial condition. It is found that He bubbles nucleate at GBs with different rates and more He bubbles appear at tilt and twist boundaries. This is because the He binding energy of tilt and twist GBs is superior over the counterpart of twin GBs. Furthermore, inhomogeneous nucleation occurs with the impact of dislocations. JF - AIP Conference Proceedings AU - Zhang, Liangzhe AU - Millett, Paul AU - Tonks, Michael AU - Zhang, Yongfeng AU - Biner, Bulent AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Monte Carlo simulation KW - Conferences KW - Kinetics KW - Simulation KW - Helium KW - Grains KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372605359?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Kinetic+Monte+Carlo+Simulation+of+He+Bubble+Nucleation+at+Different+Types+of+Grain+Boundaries+in+Mo&rft.au=Zhang%2C+Liangzhe%3BMillett%2C+Paul%3BTonks%2C+Michael%3BZhang%2C+Yongfeng%3BBiner%2C+Bulent&rft.aulast=Zhang&rft.aufirst=Liangzhe&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Monte Carlo simulation; Conferences; Kinetics; Helium; Simulation; Grains; Technology ER - TY - JOUR T1 - Mesoscale Modeling of Intergranular Bubble Growth and Percolation AN - 1372605060; 18028488 AB - The production of fission gas products, namely xenon and krypton, in irradiated nuclear fuel elements leads to a variety of phenomena that directly influence fuel performance. Central to the retention and release of fission gases is the evolution of bubbles existing on grain boundaries and grain triple junctions. Here, three-dimensional phase-field simulations of the growth and coalescence of intergranular Xe bubbles in UO2 bicrystal grain geometries will be presented. We investigate the dependency of bubble percolation on three factors: the initial bubble density, the Xe grain boundary diffusivity, and the bubble shape, which is governed by the ratio of the grain boundary energy over the surface energy. The simulations show that variations of each of these factors can lead to large discrepancies in the bubble coalescence rate, and eventual percolation, which may partially explain this observed occurrence in experimental investigations. This research was supported by the NEAMS program within DOE-NE. JF - AIP Conference Proceedings AU - Millett, Paul AU - Tonks, Michael AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Growth KW - Gases KW - Xenon KW - Conferences KW - Fuels KW - Nuclear fuels KW - Simulation KW - Krypton KW - Grains KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372605060?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Mesoscale+Modeling+of+Intergranular+Bubble+Growth+and+Percolation&rft.au=Millett%2C+Paul%3BTonks%2C+Michael&rft.aulast=Millett&rft.aufirst=Paul&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Growth; Xenon; Gases; Conferences; Fuels; Nuclear fuels; Simulation; Krypton; Grains ER - TY - JOUR T1 - Mechanical Properties of U-Mo Fuels AN - 1372604730; 18026983 AB - The Reduced Enrichment for Research and Test Reactors (RERTR) program was initiated to develop new nuclear fuels to enable the research and test reactors to use low-enriched uranium fuels instead of highenriched uranium fuels, without significant loss in performance. Hence, a new monolithic fuel type that possesses the greatest possible uranium density in the fuel region is being developed, where the fuel region consists of a single foil encased inside an aluminum alloy cladding. Currently, efforts are ongoing to evaluate the mechanical properties and microstructure of fresh U-Mo fuels, as a function of molybdenum content, carbon content and temperature. Small-scale specimen testing techniques, such as sub-size tensile testing, microindentation hardness testing and shear punch testing are being performed. Other materials characterization techniques, such as optical microscopy, XRD and SEM are being used in conjunction with the small-scale mechanical test methods. JF - AIP Conference Proceedings AU - Prabhakaran, Ramprashad AU - Burkes, Douglas AU - Jue, Jan-Fong AU - Demint, Amy AU - Gooch, Jack AU - Keiser, Dennis AU - Wachs, Daniel AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Nuclear reactors KW - Conferences KW - Fuels KW - Uranium KW - Microscopy KW - Nuclear fuels KW - Aluminum KW - Molybdenum KW - Alloys KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372604730?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Mechanical+Properties+of+U-Mo+Fuels&rft.au=Prabhakaran%2C+Ramprashad%3BBurkes%2C+Douglas%3BJue%2C+Jan-Fong%3BDemint%2C+Amy%3BGooch%2C+Jack%3BKeiser%2C+Dennis%3BWachs%2C+Daniel&rft.aulast=Prabhakaran&rft.aufirst=Ramprashad&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Conferences; Uranium; Fuels; Molybdenum; Aluminum; Nuclear fuels; Microscopy; Alloys ER - TY - JOUR T1 - Postirradiation Examination of High Burnup Metallic Fuels AN - 1372604576; 18026989 AB - Within the Fuel Cycle Research & Development program, six metallic fuel alloy compositions were fabricated and irradiated in ATR. Irradiation to 653 effective full power days resulted in fuel burnups ranging from approximately 17-30 at.% HM. These alloys (e.g., U-29Pu-4Am-2Np-30Zr) are being studied in order to understand how fuel incorporating constituents from recycled light water reactor fuel would behave in fast reactors, with particular focus on transmuting actinides. Initial destructive postirradiation examinations of these alloys have been completed, including fission gas release, optical microscopy, and burnup analysis. Select results will be presented and compared to results from lower burnup companion experiments and the historical metallic fuel performance database. JF - AIP Conference Proceedings AU - Chichester, Heather AU - Porter, Douglas AU - Hayes, Steven AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Uranium base alloys KW - U-29Pu-4Am-2Np-30Zr KW - Historical account KW - Nuclear reactors KW - Conferences KW - Fuels KW - Irradiation KW - Microscopy KW - Alloys KW - Actinides KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372604576?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Postirradiation+Examination+of+High+Burnup+Metallic+Fuels&rft.au=Chichester%2C+Heather%3BPorter%2C+Douglas%3BHayes%2C+Steven&rft.aulast=Chichester&rft.aufirst=Heather&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Historical account; Nuclear reactors; Conferences; Irradiation; Fuels; Microscopy; Alloys; Technology; Actinides ER - TY - JOUR T1 - Microanalysis of Irradiated Coated Particle Fuel from the AGR-1 Irradiation Experiment AN - 1372604380; 18026988 AB - The AGR-1 irradiation of TRISO-coated particle fuel specimens was recently completed and represents the most successful such irradiation in US history, reaching peak burnups of greater than 19% FIMA with zero failures out of 300,000 particles. Extensive post-irradiation examination of the fuel is currently in progress. A critical component of the fuel characterization is microanalysis of the irradiated fuel particles, including ceramography, scanning electron microscopy, wavelength dispersive spectroscopy, and transmission electron microscopy of coatings and fuel kernels. Among the primary objectives of this examination are to determine the effects of irradiation on coating integrity, correlate coating microstructures with the extent of fission product retention, and develop a better understanding of fission product diffusive release. Of particular interest is silver, which has long been known to exhibit relatively high release from coated particle fuel. This paper will highlight some of the microanalytical techniques being utilized and present preliminary results. JF - AIP Conference Proceedings AU - Demkowicz, Paul AU - Rooyen, Isabella Van AU - Ploger, Scott AU - Riesterer, Jessica AU - Miller, Brandon AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Fission products KW - Conferences KW - Fuels KW - Irradiation KW - Microscopy KW - Particulates KW - Spectroscopy KW - Silver KW - Coatings KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372604380?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Microanalysis+of+Irradiated+Coated+Particle+Fuel+from+the+AGR-1+Irradiation+Experiment&rft.au=Demkowicz%2C+Paul%3BRooyen%2C+Isabella+Van%3BPloger%2C+Scott%3BRiesterer%2C+Jessica%3BMiller%2C+Brandon&rft.aulast=Demkowicz&rft.aufirst=Paul&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Fission products; Conferences; Irradiation; Fuels; Microscopy; Particulates; Spectroscopy; Silver; Coatings ER - TY - JOUR T1 - Advanced Fuels with Fission Product Getters to Suppress Fuel-Cladding Chemical Interactions AN - 1372603704; 18027423 AB - Rare earth fission products in metallic fuels are known to exacerbate undesirable fuel-cladding chemical interactions with steel cladding that can lead to premature failure. Rare earth fission products produced during irradiation migrate to the fuel-cladding interface where they can depress solidus temperatures leading to breach of cladding. Furthermore, recycled fuel for a fast burner reactor used to destroy actinides may contain several percent rare earth fission products prior to reactor insertion, leading to fuel-cladding chemical interactions at the outset. This paper describes the selection of additives to complex rare earth fission products during both fuel production and irradiation. It also describes the fabrication and characterization of experimental fuels to test these concepts. Preliminary results indicate effective gettering of (surrogate) rare earth fission products in as-fabricated fuel doped with rare earths. In fuels fabricated without rare earths, the getter forms intermetallics with other constituents. JF - AIP Conference Proceedings AU - O'Holleran, T AU - Mariani, R AU - Fielding, Randall AU - Hansen, P AU - Hyde, T AU - Kennedy, J AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Fission products KW - Conferences KW - Fuels KW - Irradiation KW - Chemical interactions KW - Steel KW - Additives KW - Actinides KW - Technology KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372603704?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Advanced+Fuels+with+Fission+Product+Getters+to+Suppress+Fuel-Cladding+Chemical+Interactions&rft.au=O%27Holleran%2C+T%3BMariani%2C+R%3BFielding%2C+Randall%3BHansen%2C+P%3BHyde%2C+T%3BKennedy%2C+J&rft.aulast=O%27Holleran&rft.aufirst=T&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Fission products; Conferences; Irradiation; Fuels; Steel; Chemical interactions; Additives; Technology; Actinides ER - TY - JOUR T1 - Transport Studies with Porous Metal Fuels AN - 1372603579; 18027430 AB - Metal nuclear fuels develop significant porosity above approximately 2% burnup (heavy metal basis). Since surfaces can facilitate more rapid transport than the bulk fuel alloy, it is important to characterize the transport of fuel constituents, fission products, and cladding components in porous fuel bodies. Special-effects, out-of-pile tests were therefore designed and are being implemented to assess the significance of porosity on transport, which may be critical to understanding the fuel behavior and to modeling. We describe methods of preparing porous alloy fuels, which included atomizing the alloys into spherical or flake powders. Powders were subsequently sintered and prepared as diffusion couples with reactive counterparts, such as iron. These experiments are a crucial supplement to the traditional bulk diffusion and transport experiments for understanding and modeling fuel properties. We will summarize the rationale and need, experimental plans, recent developments, and future steps. JF - AIP Conference Proceedings AU - Mariani, Robert AU - Clark, Curtis AU - O'Holleran, Thomas AU - Park, Blair AU - Fielding, Randall AU - Kennedy, J AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Metals KW - Conferences KW - Heavy metals KW - Fuels KW - Porosity KW - Nuclear fuels KW - Alloys KW - Diffusion KW - Iron KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372603579?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Transport+Studies+with+Porous+Metal+Fuels&rft.au=Mariani%2C+Robert%3BClark%2C+Curtis%3BO%27Holleran%2C+Thomas%3BPark%2C+Blair%3BFielding%2C+Randall%3BKennedy%2C+J&rft.aulast=Mariani&rft.aufirst=Robert&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Metals; Conferences; Heavy metals; Fuels; Nuclear fuels; Porosity; Alloys; Diffusion; Iron ER - TY - JOUR T1 - TEM Study on the Phase Development and Microstructure in a U-7 wt.% Mo vs. Al-7 wt.% Ge Diffusion Couple AN - 1372603508; 18026981 AB - Fuel development for the Reduced Enrichment for Research and Test Reactors (RERTR) program has demonstrated that U-Mo alloys in contact with Al develop interaction regions with phases that have poor irradiation behavior. The addition of Si to the Al has been considered with positive results. Compositional modification to replace Si with Ge is now under evaluation to further improve irradiation behavior and recycling of spent fuel systems. In this study, the microstructural and phase development of a diffusion couple of U-7 wt.% Mo in contact with Al-7 wt.% Ge was examined by transmission electron microscopy, scanning electron microscopy and energy dispersive spectroscopy. The interdiffusion zone developed a three phase microstructure containing an amorphous phase, the orthorhombic-UGe2 and the cubic-(U,Mo)(Al,Ge)(3) phase. Results from this study are compared to U-Mo vs. pure Al and U-Mo vs. Al-Si diffusion couples to discuss the differences in the microstructural evolution of the different interdiffusion zones. JF - AIP Conference Proceedings AU - Perez, E AU - Keiser, D D AU - Sohn, Y H AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Aluminum base alloys KW - Uranium base alloys KW - Al-7Ge KW - U-7Mo KW - Conferences KW - Fuels KW - Irradiation KW - Microscopy KW - Alloys KW - Diffusion KW - Recycling KW - Spectroscopy KW - Waste management KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372603508?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=TEM+Study+on+the+Phase+Development+and+Microstructure+in+a+U-7+wt.%25+Mo+vs.+Al-7+wt.%25+Ge+Diffusion+Couple&rft.au=Perez%2C+E%3BKeiser%2C+D+D%3BSohn%2C+Y+H&rft.aulast=Perez&rft.aufirst=E&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Conferences; Irradiation; Fuels; Microscopy; Alloys; Diffusion; Spectroscopy; Recycling; Waste management ER - TY - JOUR T1 - Advancements in Nuclear Materials Research at the Idaho National Laboratory AN - 1372601210; 18026942 AB - Over the past decade, the Idaho National Laboratory (INL) has developed an impressive array of leading edge technology in support of Light Water Reactor Sustainability (LWRS) programs and development of Next Generation Nuclear Power (NGNP) plants. Capabilities in advanced micro-structural analysis of irradiated as well as un-irradiated reactor structural and pressure boundary materials supplement a full suite of mechanical characterization infrastructure. Recent advancements include acquisition of a Local Electrode Atom Probe (LEAP) and Transmission Electron Microscope (TEM) capable of handling irradiated materials as well as highly shielded mechanical test systems intended for characterization of such parameter as Irradiation Assisted Stress Corrosion Cracking (IASCC) resistance, and Fracture Toughness. The INL is currently involved in developing code cases for advanced, NGNP materials and will soon be involved in characterization of irradiated material properties for the LWR life extension effort. This paper covers current and upcoming nuclear materials research programs based at INL. JF - AIP Conference Proceedings AU - Jackson, John AU - Teysseyre, Sebastien AU - Wright, Richard AU - Cole, James AU - Porter, Douglas AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Sustainability Science Abstracts; Environment Abstracts KW - Infrastructure KW - USA, Idaho KW - Nuclear reactors KW - Conferences KW - Stress corrosion KW - Radioactive materials KW - Electrodes KW - Sustainability KW - Research programs KW - Technology KW - M3 1010:Issues in Sustainable Development KW - ENA 07:General UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372601210?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Assamodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Advancements+in+Nuclear+Materials+Research+at+the+Idaho+National+Laboratory&rft.au=Jackson%2C+John%3BTeysseyre%2C+Sebastien%3BWright%2C+Richard%3BCole%2C+James%3BPorter%2C+Douglas&rft.aulast=Jackson&rft.aufirst=John&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-08-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Infrastructure; Nuclear reactors; Stress corrosion; Conferences; Electrodes; Radioactive materials; Research programs; Sustainability; Technology; USA, Idaho ER - TY - JOUR T1 - Strain Localization During Creep-Fatigue Deformation of Alloy 617 AN - 1372599959; 18026626 AB - Alloy 617 is the leading candidate material for the intermediate heat exchanger (IHX) of the Very High Temperature Reactor (VHTR), which will require an alloy capable of operating at temperatures of up to 950 degree C. In order to provide adequate test data for design Code purposes, numerous strain controlled low-cycle fatigue (LCF) tests with hold times up to 1800 s at peak tensile strain have been conducted at 950 degree C. Post-test observations reveal that bulk grain boundary damage in the form of intergranular cracking was present in the interior of the creep-fatigue specimens. This bulk cracking was observed throughout the deformed material in distinct grain boundary locations, although the majority of grain boundaries were absent of any observable damage or signs of cavitation. Localized strain fields in the grains adjacent to interior cracks are being investigated using orientation imaging microscopy (OIM) techniques coupled with transmission electron microscopy (TEM) characterization. JF - AIP Conference Proceedings AU - Carroll, Mark AU - Carroll, Laura AU - Wright, Richard AD - Idaho National Laboratory Y1 - 2012/03/15/ PY - 2012 DA - 2012 Mar 15 PB - American Institute of Physics, Ste. 1NO1 Melville NY 11747-4502 United States SN - 0094-243X, 0094-243X KW - Environment Abstracts KW - Nickel base alloys KW - Superalloys KW - Alloy 617 KW - Fatigue KW - Conferences KW - Heat exchangers KW - High temperature KW - Microscopy KW - Alloys KW - Grains KW - Deformation KW - Technology KW - ENA 06:Food & Drugs UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1372599959?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=AIP+Conference+Proceedings&rft.atitle=Strain+Localization+During+Creep-Fatigue+Deformation+of+Alloy+617&rft.au=Carroll%2C+Mark%3BCarroll%2C+Laura%3BWright%2C+Richard&rft.aulast=Carroll&rft.aufirst=Mark&rft.date=2012-03-15&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=AIP+Conference+Proceedings&rft.issn=0094243X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2014-02-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Fatigue; Conferences; High temperature; Heat exchangers; Microscopy; Alloys; Grains; Technology; Deformation ER - TY - JOUR T1 - Spectral induced polarization signatures of mineral precipitation and hydroxide adsorption in porous media AN - 1039360821; 640147-42 JF - Proceedings of SAGEEP AU - Zhang, Chi AU - Slater, Lee AU - Redden, George AU - Fujita, Yoshiko AU - Johnson, Timothy AU - Fox, Don AU - Momayez, Moe Y1 - 2012/03// PY - 2012 DA - March 2012 PB - Environmental and Engineering Geophysical Society, Denver, CO VL - 2012 SN - 1554-8015, 1554-8015 KW - Ottawa Sand KW - soil mechanics KW - electrical conductivity KW - technology KW - mineral composition KW - geophysical methods KW - electrical methods KW - induced polarization KW - spectral analysis KW - adsorption KW - geochemistry KW - 30:Engineering geology KW - 20:Applied geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1039360821?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefinprocess&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Proceedings+of+SAGEEP&rft.atitle=Spectral+induced+polarization+signatures+of+mineral+precipitation+and+hydroxide+adsorption+in+porous+media&rft.au=Zhang%2C+Chi%3BSlater%2C+Lee%3BRedden%2C+George%3BFujita%2C+Yoshiko%3BJohnson%2C+Timothy%3BFox%2C+Don%3BMomayez%2C+Moe&rft.aulast=Zhang&rft.aufirst=Chi&rft.date=2012-03-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Proceedings+of+SAGEEP&rft.issn=15548015&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - Proceedings of the 25th symposium on the application of geophysics to engineering & environmental problems on Making waves; geophysical innovations for a thirsty world N1 - Copyright - GeoRef in Process, Copyright 2017, American Geosciences Institute. After editing and indexing, this record will be added to Georef. N1 - PubXState - CO N1 - Last updated - 2017-01-24 N1 - SubjectsTermNotLitGenreText - adsorption; electrical conductivity; electrical methods; geochemistry; geophysical methods; induced polarization; mineral composition; Ottawa Sand; soil mechanics; spectral analysis; technology ER - TY - JOUR T1 - Self-calibrating water quality monitoring system AN - 1039359720; 640147-16 JF - Proceedings of SAGEEP AU - Armstrong, Trent AU - Teichert, Candice AU - Scott, Clark AU - Casey, Smith AU - Momayez, Moe Y1 - 2012/03// PY - 2012 DA - March 2012 PB - Environmental and Engineering Geophysical Society, Denver, CO VL - 2012 SN - 1554-8015, 1554-8015 KW - United States KW - water quality KW - technology KW - monitoring KW - acid mine drainage KW - South Carolina KW - pollution KW - calibration KW - remediation KW - ground water KW - McCormick County South Carolina KW - sampling KW - economics KW - Barite Hill Pit Lake KW - remote sensing KW - 20:Applied geophysics KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1039359720?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefinprocess&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Proceedings+of+SAGEEP&rft.atitle=Self-calibrating+water+quality+monitoring+system&rft.au=Armstrong%2C+Trent%3BTeichert%2C+Candice%3BScott%2C+Clark%3BCasey%2C+Smith%3BMomayez%2C+Moe&rft.aulast=Armstrong&rft.aufirst=Trent&rft.date=2012-03-01&rft.volume=2012&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Proceedings+of+SAGEEP&rft.issn=15548015&rft_id=info:doi/ L2 - file:///D:/SAGEEP2012/prof203.htm LA - English DB - GeoRef N1 - Conference title - Proceedings of the 25th symposium on the application of geophysics to engineering & environmental problems on Making waves; geophysical innovations for a thirsty world N1 - Copyright - GeoRef in Process, Copyright 2017, American Geosciences Institute. After editing and indexing, this record will be added to Georef. N1 - PubXState - CO N1 - Last updated - 2017-01-24 N1 - SubjectsTermNotLitGenreText - acid mine drainage; Barite Hill Pit Lake; calibration; economics; ground water; McCormick County South Carolina; monitoring; pollution; remediation; remote sensing; sampling; South Carolina; technology; United States; water quality ER - TY - JOUR T1 - Percolation on grain boundary networks: Application to fission gas release in nuclear fuels AN - 1010888830; 16144233 AB - The percolation behavior of grain boundary networks is characterized in two- and three-dimensional lattices with circular macroscale cross-sections that correspond to nuclear fuel elements. The percolation of gas bubbles on grain boundaries, and the subsequent percolation of grain boundary networks is the primary mechanism of fission gas release from nuclear fuels. Both radial cracks and radial gradients in grain boundary property distributions are correlated with the fraction of grain boundaries vented to the free surfaces. Our results show that cracks surprisingly do not significantly increase the percolation of uniform grain boundary networks. However, for networks with radial gradients in boundary properties, the cracks can considerably raise the vented grain boundary content. JF - Computational Materials Science AU - Millett, Paul C AD - Nuclear Fuels and Materials, Idaho National Laboratory, Idaho Falls, ID 83415, United States Paul.Millett@inl.gov Y1 - 2012/02// PY - 2012 DA - Feb 2012 SP - 31 EP - 36 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 53 IS - 1 SN - 0927-0256, 0927-0256 KW - METADEX (MD); Advanced Polymers Abstracts (EP); Environmental Engineering Abstracts (EN); Composites Industry Abstracts (ED); Engineered Materials Abstracts, Ceramics (EC); Computer and Information Systems Abstracts (CI) UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1010888830?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Computational+Materials+Science&rft.atitle=Percolation+on+grain+boundary+networks%3A+Application+to+fission+gas+release+in+nuclear+fuels&rft.au=Millett%2C+Paul+C&rft.aulast=Millett&rft.aufirst=Paul&rft.date=2012-02-01&rft.volume=53&rft.issue=1&rft.spage=31&rft.isbn=&rft.btitle=&rft.title=Computational+Materials+Science&rft.issn=09270256&rft_id=info:doi/10.1016%2Fj.commatsci.2011.09.025 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-05-01 N1 - Last updated - 2012-05-04 DO - http://dx.doi.org/10.1016/j.commatsci.2011.09.025 ER - TY - CPAPER T1 - Nuclear Assisted Bio-Fuel Production via High Temp. Steam Electrolysis T2 - 15th Annual Energy, Utility & Environment Conference (EUEC 2012) AN - 1313098149; 6151141 JF - 15th Annual Energy, Utility & Environment Conference (EUEC 2012) AU - Hawkes, Grant AU - McKellar, Michael AU - O'Brien, James Y1 - 2012/01/30/ PY - 2012 DA - 2012 Jan 30 KW - Fuel technology KW - Steam KW - Electrolysis KW - Biofuels UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1313098149?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Acpi&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=conference&rft.jtitle=15th+Annual+Energy%2C+Utility+%26+Environment+Conference+%28EUEC+2012%29&rft.atitle=Nuclear+Assisted+Bio-Fuel+Production+via+High+Temp.+Steam+Electrolysis&rft.au=Hawkes%2C+Grant%3BMcKellar%2C+Michael%3BO%27Brien%2C+James&rft.aulast=Hawkes&rft.aufirst=Grant&rft.date=2012-01-30&rft.volume=&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=15th+Annual+Energy%2C+Utility+%26+Environment+Conference+%28EUEC+2012%29&rft.issn=&rft_id=info:doi/ L2 - http://euec.com/getattachment/Index/Brochure_2012.pdf.aspx LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-26 N1 - Last updated - 2013-02-28 ER - TY - JOUR T1 - The effect of the CO (sub 3) (super 2-) to Ca (super 2+) ion activity ratio on calcite precipitation kinetics and Sr (super 2+) partitioning AN - 1832633553; 704144-1 AB - A proposed strategy for immobilizing trace metals in the subsurface is to stimulate calcium carbonate precipitation and incorporate contaminants by co-precipitation. Such an approach will require injecting chemical amendments into the subsurface to generate supersaturated conditions that promote mineral precipitation. However, the formation of reactant mixing zones will create gradients in both the saturation state and ion activity ratios (i.e., aCO3 2? /aCa2+). To better understand the effect of ion activity ratios on CaCO3 precipitation kinetics and Sr2+ co-precipitation, experiments were conducted under constant composition conditions where the supersaturation state (?) for calcite was held constant at 9.4, but the ion activity ratio (r = aCO3 2? /aCa2+ ) was varied between 0.0032 and 4.15. : Calcite was the only phase observed, by XRD, at the end of the experiments. Precipitation rates increased from 41.3 + or - 3.4 ?mol m-2 min-1 at r = 0.0315 to a maximum rate of 74.5 + or - 4.8 ?mol m-2 min-1 at r = 0.306 followed by a decrease to 46.3 + or - 9.6 ?mol m-2 min-1 at r = 1.822. The trend was simulated using a simple mass transfer model for solute uptake at the calcite surface. However, precipitation rates at fixed saturation states also evolved with time. Precipitation rates accelerated for low r values but slowed for high r values. These trends may be related to changes in effective reactive surface area. The aCO3 2? /aCa2+ ratios did not affect the distribution coefficient for Sr in calcite (DP Sr 2+), apart from the indirect effect associated with the established positive correlation between DP Sr 2+ and calcite precipitation rate. At a constant supersaturation state (? = 9.4), varying the ion activity ratio affects the calcite precipitation rate. This behavior is not predicted by affinity-based rate models. Furthermore, at the highest ion ratio tested, no precipitation was observed, while at the lowest ion ratio precipitation occurred immediately and valid rate measurements could not be made. The maximum measured precipitation rate was 2-fold greater than the minima, and occurred at a carbonate to calcium ion activity ratio of 0.306. These findings have implications for predicting the progress and cost of remediation operations involving enhanced calcite precipitation where mineral precipitation rates, and the spatial/temporal distribution of those rates, can have significant impacts on the mobility of contaminants. JF - Geochemical Transactions AU - Gebrehiwet, Tsigabu A AU - Redden, George D AU - Fujita, Yoshiko AU - Beig, Mikala S AU - Smith, Robert W Y1 - 2012/01/26/ PY - 2012 DA - 2012 Jan 26 SP - 11 PB - Springer for Royal Society of Chemistry, London VL - 13 IS - 1 SN - 1467-4866, 1467-4866 KW - calcium KW - alkaline earth metals KW - carbonate ion KW - X-ray diffraction data KW - pollutants KW - pollution KW - calcite KW - partitioning KW - saturation KW - precipitation KW - metals KW - cations KW - trace metals KW - mobility KW - kinetics KW - carbonates KW - strontium KW - activity KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1832633553?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefinprocess&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Geochemical+Transactions&rft.atitle=The+effect+of+the+CO+%28sub+3%29+%28super+2-%29+to+Ca+%28super+2%2B%29+ion+activity+ratio+on+calcite+precipitation+kinetics+and+Sr+%28super+2%2B%29+partitioning&rft.au=Gebrehiwet%2C+Tsigabu+A%3BRedden%2C+George+D%3BFujita%2C+Yoshiko%3BBeig%2C+Mikala+S%3BSmith%2C+Robert+W&rft.aulast=Gebrehiwet&rft.aufirst=Tsigabu&rft.date=2012-01-26&rft.volume=13&rft.issue=1&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Geochemical+Transactions&rft.issn=14674866&rft_id=info:doi/10.1186%2F1467-4866-13-1 L2 - http://www.geochemicaltransactions.com/ LA - English DB - GeoRef N1 - Copyright - GeoRef in Process, Copyright 2017, American Geosciences Institute. After editing and indexing, this record will be added to Georef. N1 - Number of references - 46 N1 - Document feature - illus. incl. 2 tables N1 - Last updated - 2017-01-24 N1 - SubjectsTermNotLitGenreText - activity; alkaline earth metals; calcite; calcium; carbonate ion; carbonates; cations; kinetics; metals; mobility; partitioning; pollutants; pollution; precipitation; saturation; strontium; trace metals; X-ray diffraction data DO - http://dx.doi.org/10.1186/1467-4866-13-1 ER - TY - JOUR T1 - Integration of facility modeling capabilities for nuclear nonproliferation analysis AN - 918060635; 16091193 AB - Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples. JF - Progress in Nuclear Energy AU - Garcia, Humberto E AU - Burr, Tom L AU - Coles, Garill A AU - Edmunds, Thomas A AU - Garrett, Alfred J AU - Gorensek, Maximilian B AU - Hamm, Luther L AU - Krebs, John F AU - Kress, Reid L AU - Lamberti, Vincent E AU - Schoenwald, David A AU - Tzanos, Constantine P AU - Ward, Richard C AD - Monitoring and Decision Systems, Idaho National Laboratory, Idaho Falls, ID 83415, USA, maximilian.gorensek@srnl.doe.gov Y1 - 2012/01// PY - 2012 DA - January 2012 SP - 96 EP - 111 PB - Elsevier B.V., P.O. Box 800 Kidlington Oxford OX5 1DX United Kingdom VL - 54 IS - 1 SN - 0149-1970, 0149-1970 KW - Environment Abstracts KW - Nuclear nonproliferation KW - Facility modeling KW - Integrated model KW - Inverse problem KW - Data collection KW - Data processing KW - Nuclear reactors KW - Sensors KW - Nuclear fuels KW - Nuclear energy KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/918060635?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Progress+in+Nuclear+Energy&rft.atitle=Integration+of+facility+modeling+capabilities+for+nuclear+nonproliferation+analysis&rft.au=Garcia%2C+Humberto+E%3BBurr%2C+Tom+L%3BColes%2C+Garill+A%3BEdmunds%2C+Thomas+A%3BGarrett%2C+Alfred+J%3BGorensek%2C+Maximilian+B%3BHamm%2C+Luther+L%3BKrebs%2C+John+F%3BKress%2C+Reid+L%3BLamberti%2C+Vincent+E%3BSchoenwald%2C+David+A%3BTzanos%2C+Constantine+P%3BWard%2C+Richard+C&rft.aulast=Garcia&rft.aufirst=Humberto&rft.date=2012-01-01&rft.volume=54&rft.issue=1&rft.spage=96&rft.isbn=&rft.btitle=&rft.title=Progress+in+Nuclear+Energy&rft.issn=01491970&rft_id=info:doi/10.1016%2Fj.pnucene.2011.07.007 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-01-01 N1 - Last updated - 2016-02-04 N1 - SubjectsTermNotLitGenreText - Data collection; Nuclear reactors; Data processing; Sensors; Nuclear fuels; Nuclear energy DO - http://dx.doi.org/10.1016/j.pnucene.2011.07.007 ER - TY - JOUR T1 - Fracturing driven by gas exsolution AN - 1832586307; 650179-15 JF - Geophysical Research Abstracts AU - Hafver, A AU - Kobchenko, M E AU - Malthe-Sorenssen, A AU - Meakin, P AU - Anonymous Y1 - 2012 PY - 2012 DA - 2012 SP - Abstract EGU2012 EP - 8643 PB - Copernicus GmbH on behalf of the European Geosciences Union (EGU), Katlenburg-Lindau VL - 14 SN - 1029-7006, 1029-7006 KW - models KW - fractures KW - discrete element analysis KW - experimental studies KW - stress KW - geometry KW - gases KW - carbon dioxide KW - 16:Structural geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1832586307?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefinprocess&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Geophysical+Research+Abstracts&rft.atitle=Fracturing+driven+by+gas+exsolution&rft.au=Hafver%2C+A%3BKobchenko%2C+M+E%3BMalthe-Sorenssen%2C+A%3BMeakin%2C+P%3BAnonymous&rft.aulast=Hafver&rft.aufirst=A&rft.date=2012-01-01&rft.volume=14&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Geophysical+Research+Abstracts&rft.issn=10297006&rft_id=info:doi/ L2 - http://meetingorganizer.copernicus.org/EGU2012/EGU2012-8643.pdf http://www.copernicus.org/EGU/gra/gra.html LA - English DB - GeoRef N1 - Conference title - European Geosciences Union general assembly 2012 N1 - Copyright - GeoRef in Process, Copyright 2017, American Geosciences Institute. After editing and indexing, this record will be added to Georef. N1 - Last updated - 2017-01-24 N1 - SubjectsTermNotLitGenreText - carbon dioxide; discrete element analysis; experimental studies; fractures; gases; geometry; models; stress ER - TY - JOUR T1 - Large hybrid energy systems for making low CO sub(2) load-following power and synthetic fuel AN - 1671494506; 17013118 AB - Hybrid energy systems using nuclear heat sources can economically produce load-following electrical power by exploiting their surplus generation capacity, available at night or seasonally, to make synthetic fuel. Vehicle fuel is the only current energy use large enough to absorb all the energy capacity that might be diverted from the power industry, and its ease of storage obviates problems with discontinuous synfuel production. The potential benefits and challenges of synfuels integration are illustrated by the production of methanol from natural gas (as a source of carbon) using steam from a light water nuclear power reactor which is assumed to be available in accord with a year's worth of power demand data. The synthesis of methanol is easily adapted to using 300 degree C heat from a light water reactor and this simple compound can be further processed into gasoline, biodiesel (to esterify vegetable oils), or dimethyl ether, fuels which can be used with the current vehicle fleet. A supplemental feed to the methanol process of natural gas (for energy) allows operation at constant full rate when the nuclear heat is being used to produce electrical power. The higher capital costs of such a system are offset by a lower cost of heat and power production from a large base load type of plant and by reduced costs associated with much lower CO sub(2) emissions. Other less tangible economic benefits of this and similar hybrid systems include better use of natural resources for fuels and greater energy supply reliability from the domestic production of vehicle fuel. JF - Energy & Environmental Science AU - Cherry, Robert S AU - Aumeier, Steven E AU - Boardman, Richard D AD - Idaho National Laboratory; Idaho Falls; ID; USA robert.cherry@inl.gov Y1 - 2012/01// PY - 2012 DA - Jan 2012 SP - 5489 EP - 5497 PB - Royal Society of Chemistry, c/o Springer-Verlag New York Inc. Secaucus New Jersey 07096 2485 United States VL - 5 IS - 2 SN - 1754-5692, 1754-5692 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA) KW - Energy use KW - Costs KW - Nuclear power generation KW - Energy (nuclear) KW - Fuels KW - Methyl alcohol KW - Economics KW - Vehicles UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1671494506?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Energy+%26+Environmental+Science&rft.atitle=Large+hybrid+energy+systems+for+making+low+CO+sub%282%29+load-following+power+and+synthetic+fuel&rft.au=Cherry%2C+Robert+S%3BAumeier%2C+Steven+E%3BBoardman%2C+Richard+D&rft.aulast=Cherry&rft.aufirst=Robert&rft.date=2012-01-01&rft.volume=5&rft.issue=2&rft.spage=5489&rft.isbn=&rft.btitle=&rft.title=Energy+%26+Environmental+Science&rft.issn=17545692&rft_id=info:doi/10.1039%2Fc1ee02731j LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-09-01 N1 - Number of references - 15 N1 - Last updated - 2015-04-09 DO - http://dx.doi.org/10.1039/c1ee02731j ER - TY - JOUR T1 - Carbon dioxide groundwater mixing and mineralization reactions with reservoir rocks at a natural analogue site, Soda Springs, Idaho, USA AN - 1520105436; 2014-027789 AB - Linking experimental and field observations of mineral carbonatation for in-situ long-term carbon storage analog sites are particularly relevant and useful to the study geologic carbon dioxide sequestration for a number of reasons, particularly because they offer the opportunity to examine a system that has operated on a time scale (centuries to eons) that laboratory and field experimentation (days to decades) cannot compare. One such example of a mafic rock CO (sub 2) analog is the Soda Springs site located in Caribou County of southeastern Idaho, USA. At this site, CO (sub 2) and formation fluids generated by the dissolution of Paleozoic carbonates at depth are migrating and reacting with a series of shallower thoelitic basalt flows that host a fresh water aquifer. We believe that the layered basalt flows are acting as a reactive barrier to the vertical migration of the deep CO (sub 2) charged fluids. However, in several cases the CO (sub 2) charged reservoir fluids make it to the surface and are expressed as either carbonated springs, or as a cold-water geyser that was caused by wells that encounter the system at depth. Analysis of these sources of water shows a steady evolution of groundwater from unaffected by the basalt (deep wells) to more fully reacted (springs). Data from this system makes a compelling argument for the ability of basalt flow to maintain containment for CCS applications. Our study has shown that CO (sub 2) charged fluids migrating upwards are being neutralized by mineral dissolution and precipitation within the basalt flows. These neutralization reactions have resulted in a specific chemical signature being imparted to the formation fluid that can be used to determine which minerals are dissolving and precipitating. Through and integrated study of this natural analog site including field and laboratory experiments, the relative roles of mineral dissolution and precipitation and phase assemblage are being characterized for this basalt-hosted system. The benefit of studying this natural analog is that it has been active for many 1000's of years and depending on sample location and depth, the resulting fluid chemistry carries the chemical signature (tracer) indicative of the degree of reaction within the basalt formation. Additionally, the study of this system is helping define the appropriate laboratory scale experiments that will be needed to accomplish the larger objective of the project, understanding changes in aqueous geochemistry associated with progressing CO (sub 2) -water-interactions. JF - Mineralogical Magazine AU - McLing, Travis L AU - Smith, Robert W AU - Smith, William AU - Anonymous Y1 - 2012 PY - 2012 DA - 2012 SP - 2094 PB - Mineralogical Society, London VL - 76 IS - 6 SN - 0026-461X, 0026-461X KW - United States KW - hydrology KW - Idaho KW - carbon sequestration KW - volcanic rocks KW - igneous rocks KW - gas storage KW - Caribou County Idaho KW - southeastern Idaho KW - reservoir rocks KW - ground water KW - carbon dioxide KW - models KW - chemical reactions KW - mixing KW - basalts KW - mineralization KW - reservoir properties KW - Soda Springs KW - 30:Engineering geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1520105436?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Mineralogical+Magazine&rft.atitle=Carbon+dioxide+groundwater+mixing+and+mineralization+reactions+with+reservoir+rocks+at+a+natural+analogue+site%2C+Soda+Springs%2C+Idaho%2C+USA&rft.au=McLing%2C+Travis+L%3BSmith%2C+Robert+W%3BSmith%2C+William%3BAnonymous&rft.aulast=McLing&rft.aufirst=Travis&rft.date=2012-01-01&rft.volume=76&rft.issue=6&rft.spage=2094&rft.isbn=&rft.btitle=&rft.title=Mineralogical+Magazine&rft.issn=0026461X&rft_id=info:doi/ L2 - http://minmag.geoscienceworld.org/content/76/6/2045.full.pdf+html http://www.minersoc.org/pages/e_journals/minmag.html LA - English DB - GeoRef N1 - Conference title - Goldschmidt 2012 N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Abstract, Copyright, Mineralogical Society of Great Britain and Ireland N1 - Date revised - 2014-01-01 N1 - Last updated - 2014-05-01 N1 - CODEN - MNLMBB N1 - SubjectsTermNotLitGenreText - basalts; carbon dioxide; carbon sequestration; Caribou County Idaho; chemical reactions; gas storage; ground water; hydrology; Idaho; igneous rocks; mineralization; mixing; models; reservoir properties; reservoir rocks; Soda Springs; southeastern Idaho; United States; volcanic rocks ER - TY - BOOK T1 - Hydropower AN - 1473599045; 2013-005743 JF - Renewable energy sources and climate change mitigation; special report of the Intergovernmental Panel on Climate Change AU - Kumar, Arun AU - Schei, Tormod AU - Ahenkorah, Alfred AU - Caceres Rodriguez, Rodolfo AU - Devernay, Jean-Michel AU - Freitas, Marcos AU - Hall, Douglas AU - Killingtveit, Anund AU - Liu, Zhiyu Y1 - 2012 PY - 2012 DA - 2012 PB - Cambridge University Press, New York, NY SN - 9781107023406; 9781107607101 KW - resources KW - technology KW - development KW - regulations KW - hydroelectric energy KW - environmental effects KW - exploration KW - utilization KW - energy sources KW - new energy sources KW - policy KW - ecology KW - industry KW - infrastructure KW - storage KW - public health KW - 29A:Economic geology, geology of energy sources KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1473599045?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/GeoRef&rft_val_fmt=info:ofi/fmt:kev:mtx:book&rft.genre=book&rft.jtitle=&rft.atitle=&rft.au=Kumar%2C+Arun%3BSchei%2C+Tormod%3BAhenkorah%2C+Alfred%3BCaceres+Rodriguez%2C+Rodolfo%3BDevernay%2C+Jean-Michel%3BFreitas%2C+Marcos%3BHall%2C+Douglas%3BKillingtveit%2C+Anund%3BLiu%2C+Zhiyu&rft.aulast=Kumar&rft.aufirst=Arun&rft.date=2012-01-01&rft.volume=&rft.issue=&rft.spage=&rft.isbn=9781107023406&rft.btitle=Hydropower&rft.title=Hydropower&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. N1 - Date revised - 2013-01-01 N1 - Number of references - 180 N1 - PubXState - NY N1 - Document feature - illus. incl. 10 tables, sketch map N1 - Last updated - 2014-01-02 ER - TY - JOUR T1 - VULCAN; a concept study for a New Frontiers-class Venus lander AN - 1469620041; 2013-099538 JF - Abstracts of Papers Submitted to the Lunar and Planetary Science Conference AU - Stickle, A M AU - Banks, M E AU - Benecchi, S D AU - Bradley, B K AU - Budney, C J AU - Clark, G B AU - Corbin, B A AU - James, P B AU - Kumar, K AU - O'Brien, R C AU - Rivera-Valentin, E G AU - Saltman, A AU - Schmerr, N AU - Seubert, C R AU - Siles, J V AU - Stockton, A M AU - Taylor, C AU - Zanetti, M AU - Anonymous Y1 - 2012 PY - 2012 DA - 2012 EP - Abstract 1939 PB - Lunar and Planetary Science Conference, Houston, TX VL - 43 KW - imagery KW - isotopes KW - VenUs Lander for Compositional ANalysis Mission KW - Venus KW - education KW - stable isotopes KW - atmospheric circulation KW - noble gases KW - chemical composition KW - meteorology KW - VULCAN Mission KW - landers KW - in situ KW - gamma-ray spectroscopy KW - atmosphere KW - mass spectroscopy KW - planetary missions KW - weathering KW - terrestrial planets KW - Raman spectroscopy KW - planets KW - objectives KW - spectroscopy KW - instruments KW - design KW - New Frontiers-class missions KW - 04:Extraterrestrial geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1469620041?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Abstracts+of+Papers+Submitted+to+the+Lunar+and+Planetary+Science+Conference&rft.atitle=VULCAN%3B+a+concept+study+for+a+New+Frontiers-class+Venus+lander&rft.au=Stickle%2C+A+M%3BBanks%2C+M+E%3BBenecchi%2C+S+D%3BBradley%2C+B+K%3BBudney%2C+C+J%3BClark%2C+G+B%3BCorbin%2C+B+A%3BJames%2C+P+B%3BKumar%2C+K%3BO%27Brien%2C+R+C%3BRivera-Valentin%2C+E+G%3BSaltman%2C+A%3BSchmerr%2C+N%3BSeubert%2C+C+R%3BSiles%2C+J+V%3BStockton%2C+A+M%3BTaylor%2C+C%3BZanetti%2C+M%3BAnonymous&rft.aulast=Stickle&rft.aufirst=A&rft.date=2012-01-01&rft.volume=43&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=Abstracts+of+Papers+Submitted+to+the+Lunar+and+Planetary+Science+Conference&rft.issn=&rft_id=info:doi/ L2 - http://www.lpi.usra.edu/meetings/lpsc2012/pdf/1939.pdf LA - English DB - GeoRef N1 - Conference title - Forty-third lunar and planetary science conference N1 - Copyright - GeoRef, Copyright 2013, American Geosciences Institute. N1 - Date revised - 2013-01-01 N1 - Number of references - 5 N1 - PubXState - TX N1 - Document feature - illus. N1 - SuppNotes - Accessed on Aug. 3, 2012 N1 - Last updated - 2013-12-20 N1 - CODEN - #02179 N1 - SubjectsTermNotLitGenreText - atmosphere; atmospheric circulation; chemical composition; design; education; gamma-ray spectroscopy; imagery; in situ; instruments; isotopes; landers; mass spectroscopy; meteorology; New Frontiers-class missions; noble gases; objectives; planetary missions; planets; Raman spectroscopy; spectroscopy; stable isotopes; terrestrial planets; Venus; VenUs Lander for Compositional ANalysis Mission; VULCAN Mission; weathering ER - TY - JOUR T1 - Status of Validating Core-Reload and Safety Analysis of the Advanced Test Reactor using HELIOS, invited AN - 1283711878; 17432047 AB - The Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) is a central testing facility at the forefront of fuel cycle research. To ensure high confidence in and efficient use of this state-of-the-art facility, it is important to maintain high standards of verification and validation. INL is in the processes of updating its nuclear software and design practices for the ATR to be consistent with modern verification and validation standards. This update project is replacing over-conservatism with modern "best-estimate" nuclear codes and models. Here "best-estimate" is meant to mean that the approach applies the state-of-the-art, best available (hence, best-estimate) tools and codes to compute safety margins in the ATR. Furthermore, it is essential to thoroughly test the code and model to know its accuracy (i.e., uncertainty due to covariance relationships with input data) and its precision (i.e., the systematic biases not associated with input data uncertainty). JF - Transactions of the American Nuclear Society AU - Bays, Samuel AU - Swain, Emily AU - Crawford, Douglas AD - Idaho National Laboratory, P.O. Box 1625, MS 3870, Idaho Falls, ID 83403, Samuel.Bays@inl.gov Y1 - 2012 PY - 2012 DA - 2012 SP - 808 EP - 810 PB - American Nuclear Society, Inc. VL - 106 SN - 0003-018X, 0003-018X KW - Health & Safety Science Abstracts KW - Computer programs KW - USA, Idaho KW - Nuclear reactors KW - Safety engineering KW - Fuels KW - Nuclear fuels KW - H 8000:Radiation Safety/Electrical Safety UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1283711878?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ahealthsafetyabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Transactions+of+the+American+Nuclear+Society&rft.atitle=Status+of+Validating+Core-Reload+and+Safety+Analysis+of+the+Advanced+Test+Reactor+using+HELIOS%2C+invited&rft.au=Bays%2C+Samuel%3BSwain%2C+Emily%3BCrawford%2C+Douglas&rft.aulast=Bays&rft.aufirst=Samuel&rft.date=2012-01-01&rft.volume=106&rft.issue=&rft.spage=808&rft.isbn=&rft.btitle=&rft.title=Transactions+of+the+American+Nuclear+Society&rft.issn=0003018X&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2013-02-01 N1 - Number of references - 8 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Computer programs; Nuclear reactors; Safety engineering; Fuels; Nuclear fuels; USA, Idaho ER - TY - JOUR T1 - Innovative fuels and structural materials for advanced nuclear energy systems AN - 1125239269; 17255315 AB - Advanced nuclear energy systems such as Generation IV reactors benefit from various innovative design features to enhance the performance of the nuclear reactors. The development of new nuclear fuels and structural materials is one of most important steps to accomplish the successful deployment of advanced nuclear energy systems. Under the guidance of the NEA Nuclear Science Committee, the Working Party on Scientific Issues of the Fuel Cycle has therefore been closely monitoring R&D programmes in these areas. Two of its expert groups have carried out reviews of the latest developments. JF - NEA News AU - Choi, Y-J AU - Pasamehmetoglu, KO AU - Allen, T R AD - Idaho National Laboratory in the United States, yong-joon.choi@inl.gov Y1 - 2012 PY - 2012 DA - 2012 SP - 21 EP - 23 VL - 30 IS - 1 SN - 1605-9581, 1605-9581 KW - Environment Abstracts KW - Indexing in process UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1125239269?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=NEA+News&rft.atitle=Innovative+fuels+and+structural+materials+for+advanced+nuclear+energy+systems&rft.au=Choi%2C+Y-J%3BPasamehmetoglu%2C+KO%3BAllen%2C+T+R&rft.aulast=Choi&rft.aufirst=Y-J&rft.date=2012-01-01&rft.volume=30&rft.issue=1&rft.spage=21&rft.isbn=&rft.btitle=&rft.title=NEA+News&rft.issn=16059581&rft_id=info:doi/ LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-10-01 N1 - Last updated - 2012-11-02 ER - TY - JOUR T1 - Microstructure of the irradiated U sub(3)Si sub(2)/Al silicide dispersion fuel AN - 918052457; 15794597 AB - The silicide dispersion fuel of U sub(3)Si sub(2)/Al is recognized as the best performance fuel for many nuclear research and test reactors with up to 4.8 gU/cm super(3) fuel loading. An irradiated U sub(3)Si sub(2)/Al dispersion fuel ( super(235)U [approx] 75%) from the high-flux side of a fuel plate (U0R040) from the Reduced Enrichment for Research and Test Reactors (RERTR)-8 test was characterized using transmission electron microscopy (TEM). The fuel was irradiated in the Advanced Test Reactor (ATR) for 105 days. The average irradiation temperature and fission density of the U sub(3)Si sub(2) fuel particles for the TEM sample are estimated to be approximately 110 degree C and 5.4 x 10 super(27) f/m super(3). The characterization was performed using a 200-kV TEM. The U/Si ratio for the fuel particle and (Si + Al)/U for the fuel-matrix-interaction layer are approximately 1.1 and 4-10, respectively. The estimated average diameter, number density and volume fraction for small bubbles (1 mu m) in the fuel particle are [approx]94 nm, 1.05 x 10 super(20) m super(-3) and [approx]11%, respectively. The results and their implication on the performance of the U sub(3)Si sub(2)/Al silicide dispersion fuel are discussed. JF - Journal of Nuclear Materials AU - Gan, J AU - Keiser, D D AU - Miller, B D AU - Jue, J-F AU - Robinson, AB AU - Madden, J W AU - Medvedev, P G AU - Wachs, D M AD - Nuclear Fuels and Materials Division, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188, USA, Jian.Gan@inl.gov Y1 - 2011/12// PY - 2011 DA - Dec 2011 SP - 97 EP - 104 PB - Elsevier B.V., P.O. Box 211 Amsterdam 1000 AE Netherlands VL - 419 IS - 1-3 SN - 0022-3115, 0022-3115 KW - Environment Abstracts KW - Nuclear reactors KW - Fuels KW - Irradiation KW - Nuclear fuels KW - Radioactive materials KW - Microscopy KW - Temperature KW - Particulates KW - ENA 03:Energy UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/918052457?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvabstractsmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Journal+of+Nuclear+Materials&rft.atitle=Microstructure+of+the+irradiated+U+sub%283%29Si+sub%282%29%2FAl+silicide+dispersion+fuel&rft.au=Gan%2C+J%3BKeiser%2C+D+D%3BMiller%2C+B+D%3BJue%2C+J-F%3BRobinson%2C+AB%3BMadden%2C+J+W%3BMedvedev%2C+P+G%3BWachs%2C+D+M&rft.aulast=Gan&rft.aufirst=J&rft.date=2011-12-01&rft.volume=419&rft.issue=1-3&rft.spage=97&rft.isbn=&rft.btitle=&rft.title=Journal+of+Nuclear+Materials&rft.issn=00223115&rft_id=info:doi/10.1016%2Fj.jnucmat.2011.07.030 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-01-01 N1 - Last updated - 2015-03-19 N1 - SubjectsTermNotLitGenreText - Nuclear reactors; Irradiation; Fuels; Microscopy; Radioactive materials; Nuclear fuels; Temperature; Particulates DO - http://dx.doi.org/10.1016/j.jnucmat.2011.07.030 ER - TY - JOUR T1 - CO (sub 2) sequestration in basalt; carbonate mineralization and fluid substitution AN - 916837528; 2012-012657 AB - Geological sequestration of carbon dioxide in deep reservoirs may provide a large-scale option for reducing the emissions of this gas into the atmosphere. The effectiveness of sequestration depends on the storage capacity and stability of the reservoir and risk of leakage into the overburden. Reservoir rocks can react with a CO (sub 2) -water mixture, potentially resulting in the precipitation of minerals in the available matrix pore space and within pre-existing fractures. This induced mineralization may form internal seals that could help mitigate the leakage of CO (sub 2) into the overburden. For basaltic host rocks, carbonic acid partially dissolves minerals in the host rock, such as the calcium plagioclase mineral, freeing various cations (e.g., Ca (super 2) + and Mg (super 2) +) for later precipitation as carbonate cements (Gislason et al., 2010). JF - Leading Edge (Tulsa, OK) AU - Otheim, Thomas L AU - Adam, Ludmila AU - van Wijk, Kasper AU - Batzle, Michael L AU - McLing, Travis AU - Podgorney, Robert AU - Smith, Tad M AU - Sayers, Colin M AU - Liner, Chris Y1 - 2011/12// PY - 2011 DA - December 2011 SP - 1354 EP - 1359 PB - Society of Exploration Geophysicists, Tulsa, OK VL - 30 IS - 12 SN - 1070-485X, 1070-485X KW - P-waves KW - volcanic rocks KW - engineering properties KW - igneous rocks KW - gas storage KW - elastic waves KW - elastic constants KW - reservoir rocks KW - carbon dioxide KW - laboratory studies KW - basalts KW - velocity KW - mineralization KW - water KW - body waves KW - experimental studies KW - carbon sequestration KW - underground storage KW - cementation KW - geophysical methods KW - bulk modulus KW - ultrasonic methods KW - porosity KW - seismic methods KW - gas injection KW - precipitation KW - diagenesis KW - reservoir properties KW - seismic waves KW - shear modulus KW - carbonates KW - S-waves KW - 30:Engineering geology KW - 20:Applied geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/916837528?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Leading+Edge+%28Tulsa%2C+OK%29&rft.atitle=CO+%28sub+2%29+sequestration+in+basalt%3B+carbonate+mineralization+and+fluid+substitution&rft.au=Otheim%2C+Thomas+L%3BAdam%2C+Ludmila%3Bvan+Wijk%2C+Kasper%3BBatzle%2C+Michael+L%3BMcLing%2C+Travis%3BPodgorney%2C+Robert%3BSmith%2C+Tad+M%3BSayers%2C+Colin+M%3BLiner%2C+Chris&rft.aulast=Otheim&rft.aufirst=Thomas&rft.date=2011-12-01&rft.volume=30&rft.issue=12&rft.spage=1354&rft.isbn=&rft.btitle=&rft.title=Leading+Edge+%28Tulsa%2C+OK%29&rft.issn=1070485X&rft_id=info:doi/10.1190%2F1.3672479 L2 - http://onlinelibrary.wiley.com/journal/10.1111/(ISSN)1745-6592 LA - English DB - GeoRef N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data from GeoScienceWorld, Alexandria, VA, United States | Reference includes data supplied by Society of Exploration Geophysicists, Tulsa, OK, United States N1 - Date revised - 2012-01-01 N1 - Number of references - 5 N1 - PubXState - OK N1 - Document feature - illus. incl. 2 tables N1 - Last updated - 2016-10-25 N1 - SubjectsTermNotLitGenreText - basalts; body waves; bulk modulus; carbon dioxide; carbon sequestration; carbonates; cementation; diagenesis; elastic constants; elastic waves; engineering properties; experimental studies; gas injection; gas storage; geophysical methods; igneous rocks; laboratory studies; mineralization; P-waves; porosity; precipitation; reservoir properties; reservoir rocks; S-waves; seismic methods; seismic waves; shear modulus; ultrasonic methods; underground storage; velocity; volcanic rocks; water DO - http://dx.doi.org/10.1190/1.3672479 ER - TY - JOUR T1 - Ultra-trace plutonium detection AN - 1844921779; 2016-099608 AB - This paper describes the performance of a multi-collector thermal ionization isotope ratio magnetic sector mass spectrometer. Using a unique ion dispersion lens the mass dispersed individual isotope beams are separated sufficiently to allow a full-sized discrete dynode pulse counting multiplier to be used to measure each isotope beam. SRM 996 (244Pu spike) at loadings of 2.4 and 12 fg on resin beads and the Pu separated fraction of SRM 4350B Columbia River Sediment samples were measured. The limit of detection (3sigma ) for 240Pu was 3.4 attograms; the limit of quantitation (10sigma ) was 11.2 attograms. JF - American Geophysical Union Fall Meeting AU - Appelhans, A D AU - Watrous, M G AU - Olson, J E AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract V31B EP - 2523 PB - American Geophysical Union, Washington, DC VL - 2011 KW - experimental studies KW - chemical analysis KW - detection limit KW - plutonium KW - isotope ratios KW - separation KW - mass spectroscopy KW - measurement KW - thermal ionization mass spectroscopy KW - detection KW - metals KW - sediments KW - spectroscopy KW - actinides KW - chemical fractionation KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1844921779?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Ultra-trace+plutonium+detection&rft.au=Appelhans%2C+A+D%3BWatrous%2C+M+G%3BOlson%2C+J+E%3BAnonymous&rft.aulast=Appelhans&rft.aufirst=A&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-12-01 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - actinides; chemical analysis; chemical fractionation; detection; detection limit; experimental studies; isotope ratios; mass spectroscopy; measurement; metals; plutonium; sediments; separation; spectroscopy; thermal ionization mass spectroscopy ER - TY - JOUR T1 - Concept study for a Venus lander mission to analyze atmospheric and surface composition AN - 1832615650; 638264-25 AB - We present a concept-level study of a New Frontiers class, Venus lander mission that was developed during Session 1 of NASA's 2011 Planetary Science Summer School, hosted by Team X at JPL. Venus is often termed Earth's sister planet, yet they have evolved in strikingly different ways. Venus' surface and atmosphere dynamics, and their complex interaction are poorly constrained. A lander mission to Venus would enable us to address a multitude of outstanding questions regarding the geological evolution of the Venusian atmosphere and crust. Our proposed mission concept, VenUs Lander for Composition ANalysis (VULCAN), is a two-component mission, consisting of a lander and a carrier spacecraft functioning as relay to transmit data to Earth. The total mission duration is 150 days, with primary science obtained during a 1-hour descent through the atmosphere and a 2-hour residence on the Venusian surface. In the atmosphere, the lander will provide new data on atmospheric evolution by measuring dominant and trace gas abundances, light stable isotopes, and noble gas isotopes with a neutral mass spectrometer. It will make important meteorological observations of mid-lower atmospheric dynamics with pressure and temperature sensors and obtain unprecedented, detailed imagery of surface geomorphology and properties with a descent Near-IR/VIS camera. A nepholometer will provide new constraints on the sizes of suspended particulate matter within the lower atmosphere. On the surface, the lander will quantitatively investigate the chemical and mineralogical evolution of the Venusian crust with a LIBS-Raman spectrometer. Planetary differentiation processes recorded in heavy elements will be evaluated using a gamma-ray spectrometer. The lander will also provide the first stereo images for evaluating the geomorphologic/volcanic evolution of the Venusian surface, as well as panoramic views of the sample site using multiple filters, and detailed images of unconsolidated material and rock textures from a microscopic imager. Our mission proposal will enable the construction of a unique Venus test facility that will attract a new generation of scientists to Venus science. With emphasis on flight heritage, we demonstrate our cost basis and risk mitigation strategies to ensure that the VULCAN mission can be conducted within the requirements and constraints of the New Frontiers Program. JF - American Geophysical Union Fall Meeting AU - Kumar, K AU - Banks, M E AU - Benecchi, S D AU - Bradley, B K AU - Budney, C J AU - Clark, G B AU - Corbin, B A AU - James, P B AU - O'Brien, R C AU - Rivera-Valentin, E G AU - Saltman, A AU - Schmerr, N C AU - Seubert, C R AU - Siles, J V AU - Stickle, A M AU - Stockton, A M AU - Taylor, C AU - Zanetti, M Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract P42B EP - 07 PB - American Geophysical Union, Washington, DC VL - 2011 UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1832615650?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefinprocess&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Concept+study+for+a+Venus+lander+mission+to+analyze+atmospheric+and+surface+composition&rft.au=Kumar%2C+K%3BBanks%2C+M+E%3BBenecchi%2C+S+D%3BBradley%2C+B+K%3BBudney%2C+C+J%3BClark%2C+G+B%3BCorbin%2C+B+A%3BJames%2C+P+B%3BO%27Brien%2C+R+C%3BRivera-Valentin%2C+E+G%3BSaltman%2C+A%3BSchmerr%2C+N+C%3BSeubert%2C+C+R%3BSiles%2C+J+V%3BStickle%2C+A+M%3BStockton%2C+A+M%3BTaylor%2C+C%3BZanetti%2C+M&rft.aulast=Kumar&rft.aufirst=K&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef in Process, Copyright 2017, American Geosciences Institute. After editing and indexing, this record will be added to Georef. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - PubXState - DC N1 - Last updated - 2017-01-24 N1 - CODEN - #07548 ER - TY - JOUR T1 - Applying plate tectonics to continents AN - 1812216576; 2016-069623 AB - The use of so-called 'block models' to represent the deformation of the Earth's surface has become widespread, in particular to explain the ever-increasing number of GPS velocities that are becoming available. The blocks represent portions of the lithosphere that are separated by faults and extend from the surface to a depth where the faults become stress-rate free. Each block is thought of as a small tectonic plate that can rotate on the Earth's surface and may also be subject to elastic strain rates from friction on its bounding faults or anelastic strain rates from internal faults or both. In most block model implementations, the motions are described kinematically, that is, there are no forces involved and hence they do not describe plate dynamics. Nevertheless, block modeling serves useful purposes such as accounting and correcting for the elastic strain rates that can be very large near faults, providing direct estimates of the slip rates on faults, and providing kinematic information that indirectly constrain dynamical models (strain and spin rates for examples). Limitations on the size of blocks that can be used arise from both data and mechanical reasons. Because the elastic strain around faults can be several tens of kilometers in wavelength, geodetic data have difficulty resolving the relative motions of blocks at this scale. Additional independent data, such as fault slip rates estimated from geology, that are not subject to the elastic strain, can help to constrain the motion of small blocks. From a mechanical point of view, small blocks may be better described as part of a continuum as might be expected for continental deformation. We will describe recent GPS results from the western US in which we observe regions of low strain rates within broadly deforming belts. The regions vary in size from irresolvably small to large fractions of the western US deforming region. JF - American Geophysical Union Fall Meeting AU - McCaffrey, R AU - Payne, S J AU - King, R W AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract T34D EP - 02 PB - American Geophysical Union, Washington, DC VL - 2011 KW - United States KW - strain KW - lithosphere KW - stress KW - friction KW - slip rates KW - geodesy KW - deformation KW - kinematics KW - plate tectonics KW - dynamics KW - Western U.S. KW - continents KW - tectonics KW - faults KW - 18:Solid-earth geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1812216576?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Applying+plate+tectonics+to+continents&rft.au=McCaffrey%2C+R%3BPayne%2C+S+J%3BKing%2C+R+W%3BAnonymous&rft.aulast=McCaffrey&rft.aufirst=R&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-08-18 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - continents; deformation; dynamics; faults; friction; geodesy; kinematics; lithosphere; plate tectonics; slip rates; strain; stress; tectonics; United States; Western U.S. ER - TY - JOUR T1 - Integration of terrestrial and airborne laser altimetry for fault scarp profiling AN - 1777464970; 2016-029237 AB - Terrestrial laser scanning (TLS) and airborne LiDAR (light detection and ranging) data are used to evaluate the Borah Peak fault scarp, Idaho, USA. The 1983 Borah Peak earthquake (M=7.3) generated a 36 km long range-front fault scarp characterized by more than 2 m of normal slip and minor left lateral movement. Profiles can be used to measure individual scarp height and slope as well as cumulative throw where multiple scarps formed. The morphology, geometry, and surface roughness of the scarps are compared across the length of the dataset, demonstrating differences in the materials controlling the scarp profiles. Variations in scarp degradation during the past 25+ years may also be evident. The scarp profiles measured by the terrestrial and airborne datasets are compared for differences in accuracy between the two laser altimetry methods. The fused terrestrial and airborne point cloud datasets are used to extrapolate the higher resolution metrics from the terrestrial data to the coarser-resolution but larger geographic extent of the airborne data. JF - American Geophysical Union Fall Meeting AU - Glenn, N F AU - Rodgers, D W AU - Shrestha, R AU - Spaete, L AU - Armstrong, Trent AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract G13A EP - 0869 PB - American Geophysical Union, Washington, DC VL - 2011 KW - United States KW - Idaho KW - laser methods KW - roughness KW - magnitude KW - laser ranging KW - altimetry KW - Custer County Idaho KW - Borah Peak Fault KW - lidar methods KW - Borah Peak earthquake 1983 KW - surface features KW - scarps KW - fault scarps KW - earthquakes KW - remote sensing KW - airborne methods KW - 19:Seismology KW - 20:Applied geophysics UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1777464970?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Integration+of+terrestrial+and+airborne+laser+altimetry+for+fault+scarp+profiling&rft.au=Glenn%2C+N+F%3BRodgers%2C+D+W%3BShrestha%2C+R%3BSpaete%2C+L%3BArmstrong%2C+Trent%3BAnonymous&rft.aulast=Glenn&rft.aufirst=N&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2016, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2016-01-01 N1 - PubXState - DC N1 - Last updated - 2016-04-01 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - airborne methods; altimetry; Borah Peak earthquake 1983; Borah Peak Fault; Custer County Idaho; earthquakes; fault scarps; Idaho; laser methods; laser ranging; lidar methods; magnitude; remote sensing; roughness; scarps; surface features; United States ER - TY - JOUR T1 - Development of a consensus standard for verification and validation of nuclear system thermal-fluids software AN - 1777108286; 16138716 AB - With the resurgence of nuclear power and increased interest in advanced nuclear reactors as an option to supply abundant energy without the associated greenhouse gas emissions of the more conventional fossil fuel energy sources, there is a need to establish internationally recognized standards for the verification and validation (V&V) of software used to calculate the thermal-hydraulic behavior of advanced reactor designs for both normal operation and hypothetical accident conditions. To address this need, ASME (American Society of Mechanical Engineers) Standards and Certification has established the V&V 30 Committee, under the jurisdiction of the V&V Standards Committee, to develop a consensus standard for verification and validation of software used for design and analysis of advanced reactor systems. The initial focus of this committee will be on the V&V of system analysis and computational fluid dynamics (CFD) software for nuclear applications. To limit the scope of the effort, the committee will further limit its focus to software to be used in the licensing of High-Temperature Gas-Cooled Reactors. Although software verification will be an important and necessary part of the standard, much of the initial effort of the committee will be focused on the validation of existing software and new models that could be used in the licensing process. In this framework, the Standard should conform to Nuclear Regulatory Commission (NRC) and other regulatory practices, procedures and methods for licensing of nuclear power plants as embodied in the United States (U.S.) Code of Federal Regulations and other pertinent documents such as Regulatory Guide 1.203, "Transient and Accident Analysis Methods" and NUREG-0800, "NRC Standard Review Plan". In addition, the Standard should be consistent with applicable sections of ASME NQA-1-2008 "Quality Assurance Requirements for Nuclear Facility Applications (QA)". This paper describes the general requirements for the proposed V&V 30 Standard, which includes: (a) applicable NRC and other regulatory requirements for defining the operational and accident domain of a nuclear system that must be considered if the system is to be licensed, (b) the corresponding calculation domain of the software that should encompass the nuclear operational and accident domain to be used to study the system behavior for licensing purposes, (c) the definition of the scaled experimental data set required to provide the basis for validating the software, (d) the ensemble of experimental data sets required to populate the validation matrix for the software in question, and (e) the practices and procedures to be used when applying a validation standard. Although this initial effort will focus on software for licensing of High-Temperature Gas-Cooled Reactors, it is anticipated that the practices and procedures developed for this Standard can eventually be extended to other nuclear and non-nuclear applications. JF - Nuclear Engineering and Design AU - Harvego, Edwin A AU - Schultz, Richard R AU - Crane, Ryan L AD - Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415, USA Y1 - 2011/12// PY - 2011 DA - December 2011 SP - 4691 EP - 4696 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 241 IS - 12 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Software KW - Nuclear power generation KW - Computer programs KW - Nuclear reactors KW - Mathematical models KW - Licensing KW - Standards KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1777108286?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Development+of+a+consensus+standard+for+verification+and+validation+of+nuclear+system+thermal-fluids+software&rft.au=Harvego%2C+Edwin+A%3BSchultz%2C+Richard+R%3BCrane%2C+Ryan+L&rft.aulast=Harvego&rft.aufirst=Edwin&rft.date=2011-12-01&rft.volume=241&rft.issue=12&rft.spage=4691&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2011.03.056 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-05-01 N1 - Last updated - 2016-05-18 DO - http://dx.doi.org/10.1016/j.nucengdes.2011.03.056 ER - TY - JOUR T1 - A hypothetical test of sub-seafloor storage for carbon dioxide on the Juan de Fuca Plate, western North America AN - 1729848915; 2015-103307 AB - The potential of the Juan de Fuca Plate, located off the coast of Washington State and southern British Columbia, and other areas along the west coast of North America, has been suggested as a potential location for the geologic sequestration of waste carbon dioxide. The mid ocean ridge basalt that comprises the basement rocks of the plate offers many attractive characteristics for carbon dioxide disposal, including a thick cover of low-permeability sediments, access to potentially a large storage volume with good injectivity, proximity to population centers, and the potential for gravity trapping of free-phase carbon dioxide due to the temperature/pressure regime. However, investigations of the suitability of the Juan de Fuca plate for carbon injection to date have been largely conceptual in nature. Here we present a hypothetical, although rigorous and quantitative, numerical analysis of some potential sequestration scenarios in an area of the Juan de Fuca bounded between approximately 47.8776 and 47.9864 degrees (decimal latitude) and -127.448/-127.338 degrees (decimal longitude). We use data garnered from ODP seismic records and drilling logs to develop a numerical model that captures some essential aspects of the study area, including a simplified basalt/sediment geometry and property sets, and simulate the injection of carbon dioxide into the crystalline bedrock. Here we examine the impact of the model geometry and variations in rock property distributions on carbon dioxide storage capacity. JF - American Geophysical Union Fall Meeting AU - Podgorney, R K AU - Fairley, J P AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract OS31A EP - 1610 PB - American Geophysical Union, Washington, DC VL - 2011 KW - United States KW - oceanic crust KW - North America KW - Washington KW - carbon sequestration KW - Juan de Fuca Plate KW - pollutants KW - geophysical methods KW - pollution KW - British Columbia KW - seismic methods KW - carbon dioxide KW - Canada KW - marine environment KW - submarine environment KW - Western Canada KW - Ocean Drilling Program KW - greenhouse gases KW - continental shelf KW - underground disposal KW - permeability KW - crust KW - 20:Applied geophysics KW - 22:Environmental geology KW - 07:Oceanography UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1729848915?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=A+hypothetical+test+of+sub-seafloor+storage+for+carbon+dioxide+on+the+Juan+de+Fuca+Plate%2C+western+North+America&rft.au=Podgorney%2C+R+K%3BFairley%2C+J+P%3BAnonymous&rft.aulast=Podgorney&rft.aufirst=R&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2015-11-05 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - British Columbia; Canada; carbon dioxide; carbon sequestration; continental shelf; crust; geophysical methods; greenhouse gases; Juan de Fuca Plate; marine environment; North America; Ocean Drilling Program; oceanic crust; permeability; pollutants; pollution; seismic methods; submarine environment; underground disposal; United States; Washington; Western Canada ER - TY - JOUR T1 - Microbially induced calcite precipitation for subsurface immobilization of contaminants AN - 1673365428; 2015-034664 AB - Subsurface radionuclide and metal contaminants throughout the U.S. Department of Energy (DOE) complex pose one of the greatest challenges for long-term stewardship. One promising stabilization mechanism for divalent trace ions, such as the short-lived radionuclide (super 90) Sr, is co-precipitation in calcite. We have found that calcite precipitation and co-precipitation of Sr can be accelerated by the activity of urea hydrolyzing microorganisms, that higher calcite precipitation rates can result in increased Sr partitioning, and that nutrient additions can stimulate ureolytic activity. To extend our understanding of microbially induced calcite precipitation (MICP) in an aquifer setting a continuous recirculation field experiment evaluating MICP was conducted at the Integrated Field Research Challenge (IFRC) site located at Rifle, CO. In this experiment, groundwater extracted from an onsite well was amended with urea (total mass of 42.5 kg) and molasses (a carbon and electron donor) and re-injected into a well approximately 4 meters up-gradient for a period of 12 days followed by 10 months of groundwater sampling and monitoring. Crosshole radar and electrical tomographic data were collected prior, during, and after the MICP treatment. The urea and molasses treatment resulted in an enhanced population of sediment associated urea hydrolyzing organisms as evidenced by increases in the number of ureC gene copies, increases in (super 14) C urea hydrolysis rates, and long-term observations of ammonium (a urea hydrolysis product) in the injection, extraction and down gradient monitoring wells. Permeability changes and increases in the calcite saturation indexes in the well field suggest that mineral precipitation has occurred; ongoing analysis of field samples seeks to confirm this. Changes in dielectric constant and electrical conductivity were used to interpret the spatiotemporal distribution of the injectate and subsequent calcite precipitation. Modeling activities are underway to define field-scale urea hydrolysis rates. JF - American Geophysical Union Fall Meeting AU - Smith, R W AU - Fujita, Y AU - Ginn, T R AU - Hubbard, S S AU - Dafflon, B AU - Delwiche, M AU - Gebrehiwet, T AU - Henriksen, J R AU - Peterson, J AU - Taylor, J L AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract H21A EP - 1051 PB - American Geophysical Union, Washington, DC VL - 2011 KW - Sr-90 KW - ammonium KW - alkaline earth metals KW - monitoring KW - isotopes KW - pollutants KW - pollution KW - hydrolysis KW - molasse KW - ground water KW - calcite KW - partitioning KW - radioactive isotopes KW - precipitation KW - metals KW - carbonates KW - strontium KW - permeability KW - 02D:Isotope geochemistry KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1673365428?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Microbially+induced+calcite+precipitation+for+subsurface+immobilization+of+contaminants&rft.au=Smith%2C+R+W%3BFujita%2C+Y%3BGinn%2C+T+R%3BHubbard%2C+S+S%3BDafflon%2C+B%3BDelwiche%2C+M%3BGebrehiwet%2C+T%3BHenriksen%2C+J+R%3BPeterson%2C+J%3BTaylor%2C+J+L%3BAnonymous&rft.aulast=Smith&rft.aufirst=R&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2015-04-16 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - alkaline earth metals; ammonium; calcite; carbonates; ground water; hydrolysis; isotopes; metals; molasse; monitoring; partitioning; permeability; pollutants; pollution; precipitation; radioactive isotopes; Sr-90; strontium ER - TY - JOUR T1 - Undesirable flow behavior in a proposed validation data set AN - 1671468323; 16138707 AB - The next generation nuclear plant (NGNP), whose development is supported by the U.S. Department of Energy, will be a very high temperature reactor (VHTR). The VHTR is a single-phase helium-cooled reactor that will provide helium at up to 1000 degree C. The prospect of a coolant at these temperatures circulating in the reactor vessel demands that careful analysis be performed to ensure that excessively hot spots are not created and that sufficient mixing of the coolant is obtained. Computational fluid dynamics (CFD) coupled with heat transfer will be used to perform the desired analyses. However, primarily because of the imperfect nature of modeling turbulent flow, any CFD calculations used to perform nuclear reactor safety analysis must be validated against experimental data. Experimental data have been taken in a scaled section of the lower plenum of a prismatic VHTR at the matched index of refraction (MIR) facility at the Idaho National Laboratory. These data were taken with the intent that they be examined for use as validation data. A series of investigations have been conducted to assess the MIR data. Issues that have already been examined include the extent of the required computational domain, the outlet boundary condition, the inlet data and the effect of the turbulence model. One of the jets that flow into the model impacts on a wedge, which represents a portion of a hexagonal graphite block that lines the inner wall of the lower plenum. The nature of the flow below this particular jet is such that a randomly varying recirculation zone is created. This recirculation zone is seen to change in size, causing a relatively long-time scale of motion or disturbance of the flow in the model. It is concluded that such a feature is undesirable in a validation data set, firstly because of its apparent random nature and, secondly, because to obtain an appropriate long-time average would be impractical because of the compute time required. It is predicted computationally that by eliminating the first of the four inlet jets into the scaled model, the resulting recirculation zone is rendered stable. JF - Nuclear Engineering and Design AU - Johnson, Richard W AU - McIlroy, Hugh M AU - Johnson, Ryan C AU - Christensen, Daniel P AD - Idaho National Laboratory, Idaho Falls, ID 83415, USA Y1 - 2011/12// PY - 2011 DA - Dec 2011 SP - 4682 EP - 4690 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 241 IS - 12 SN - 0029-5493, 0029-5493 KW - Mechanical & Transportation Engineering Abstracts (MT); Environmental Engineering Abstracts (EN); Electronics and Communications Abstracts (EA); CSA / ASCE Civil Engineering Abstracts (CE) KW - Nuclear power generation KW - Computational fluid dynamics KW - Nuclear reactors KW - Mathematical models KW - Inlets KW - Coolants KW - Nuclear reactor components KW - Nuclear engineering UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1671468323?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Nuclear+Engineering+and+Design&rft.atitle=Undesirable+flow+behavior+in+a+proposed+validation+data+set&rft.au=Johnson%2C+Richard+W%3BMcIlroy%2C+Hugh+M%3BJohnson%2C+Ryan+C%3BChristensen%2C+Daniel+P&rft.aulast=Johnson&rft.aufirst=Richard&rft.date=2011-12-01&rft.volume=241&rft.issue=12&rft.spage=4682&rft.isbn=&rft.btitle=&rft.title=Nuclear+Engineering+and+Design&rft.issn=00295493&rft_id=info:doi/10.1016%2Fj.nucengdes.2011.02.033 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-05-01 N1 - Last updated - 2015-04-09 DO - http://dx.doi.org/10.1016/j.nucengdes.2011.02.033 ER - TY - JOUR T1 - Development of a computational multiphase flow model for Fischer Tropsch synthesis in a slurry bubble column reactor AN - 1671320548; 16090755 AB - The Hybrid Energy Systems Testing (HYTEST) Laboratory at the Idaho National Laboratory was established to develop and test hybrid energy systems with the principal objective of reducing dependence on imported fossil fuels. A central component of the HYTEST is the slurry bubble column reactor (SBCR) in which the gas-to-liquid reactions are performed to synthesize transportation fuels using the Fischer Tropsch (FT) process. These SBCRs operate in the churn-turbulent flow regime, which is characterized by complex hydrodynamics, coupled with reacting flow chemistry and heat transfer. Results, our team is developing a research tool to aid in understanding the physicochemical processes occurring in the SBCR. A robust methodology to couple reaction kinetics and mass transfer into a four-field model (consisting of the bulk liquid, small bubbles, large bubbles and solid catalyst particles) consisting of thirteen species, which are CO reactant, H sub(2 reactant, hydrocarbon product, and H) sub(2)O product in small bubbles, large bubbles, and the bulk fluid plus catalyst is outlined. Mechanistic submodels for interfacial momentum transfer in the churn-turbulent flow regime are incorporated, along with bubble breakup/coalescence and two-phase turbulence submodels. The absorption and kinetic models, specifically changes in species concentrations, have been incorporated into the mass continuity equation. The reaction rate is based on the macrokinetic model for a cobalt catalyst developed by Yates and Satterfield. The model includes heat generation produced by the exothermic chemical reaction, as well as heat removal from a constant temperature heat exchanger. A property method approach is employed to incorporate vapor-liquid equilibrium (VLE) in a robust manner. Physical and thermodynamic properties as functions of changes in both pressure and temperature are obtained from VLE calculations performed external to the computational multiphase fluid dynamics (CMFD) solver. The novelty of this approach is in its simplicity, as well as its accuracy over a specified temperature and pressure range. JF - Chemical Engineering Journal AU - Guillen, Donna Post AU - Grimmett, Tami AU - Gandrik, Anastasia M AU - Antal, Steven P AD - Idaho National Laboratory, Idaho Falls, ID 83415, USA Y1 - 2011/12/01/ PY - 2011 DA - 2011 Dec 01 SP - 83 EP - 94 PB - Elsevier B.V., The Boulevard Kidlington Oxford OX5 1GB United Kingdom VL - 176-177 SN - 1385-8947, 1385-8947 KW - Advanced Polymers Abstracts (EP); Environmental Engineering Abstracts (EN); Composites Industry Abstracts (ED); Engineered Materials Abstracts, Ceramics (EC) KW - Churn-turbulent flow KW - Fischer Tropsch KW - Slurry bubble column reactor KW - Computational multiphase fluid dynamics KW - Turbulent flow KW - Computational fluid dynamics KW - Computation KW - Mathematical models KW - Catalysts KW - Turbulence KW - Fluid flow KW - Bubbles UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1671320548?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Aenvironmentalengabstracts&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=Chemical+Engineering+Journal&rft.atitle=Development+of+a+computational+multiphase+flow+model+for+Fischer+Tropsch+synthesis+in+a+slurry+bubble+column+reactor&rft.au=Guillen%2C+Donna+Post%3BGrimmett%2C+Tami%3BGandrik%2C+Anastasia+M%3BAntal%2C+Steven+P&rft.aulast=Guillen&rft.aufirst=Donna&rft.date=2011-12-01&rft.volume=176-177&rft.issue=&rft.spage=83&rft.isbn=&rft.btitle=&rft.title=Chemical+Engineering+Journal&rft.issn=13858947&rft_id=info:doi/10.1016%2Fj.cej.2011.08.078 LA - English DB - ProQuest Environmental Science Collection N1 - Date revised - 2012-05-01 N1 - Last updated - 2016-05-18 DO - http://dx.doi.org/10.1016/j.cej.2011.08.078 ER - TY - JOUR T1 - Supercritical CO2 migration under cross-bedded structures; outcrop analog from the Jurassic Navajo Sandstone AN - 1664436590; 2015-024849 AB - Jurassic aeolian sandstones (e.g. Navajo and White Rim Sandstones) on the Colorado Plateau of Utah have been considered potential sinks for geologic CO2 sequestration due to their regional lateral continuity, thickness, high porosity and permeability, presence of seal strata and proximity to large point sources of anthropogenic CO2. However, aeolian deposits usually exhibit inherent internal complexities induced by migrating bedforms of different sizes and their resulting bounding surfaces. Therefore, CO2 plume migration in such complex media should be well defined and successively linked in models for better characterization of the plume behavior. Based on an outcrop analog of the upper Navajo Sandstone in the western flank of the San Rafael Swell, Utah, we identified five different bedform types with dune and interdune facies to represent the spatial continuity of lithofacies units. Using generated 3D geometrical facies patterns of cross-bedded structures in the Navajo Sandstone, we performed numerical simulations to understand the detailed behavior of CO2 plume migration under the different cross-bedded bedforms. Our numerical simulation results indicate that cross-bedded structures (bedform types) play an important role on governing the rate and directionality of CO2 migration, resulting in changes of imbibition processes of CO2. CO2 migration tends to follow wind ripple laminations and reactivation surfaces updip. Our results suggest that geologically-based upscaling of CO2 migration is crucial in cross-bedded formations as part of reservoir or basin scale models. Furthermore, comparative modeling studies between 3D models and 2D cross-sections extracted from 3D models showed the significant three-dimensional interplay in a cross-bedded structure and the need to correctly capture the geologic heterogeneity to predict realistic CO2 plume behavior. Our outcrop analog approach presented in this study also demonstrates an alternative method for assessing geologic CO2 storage in deep formations when scarce data is available. JF - American Geophysical Union Fall Meeting AU - Lee, S AU - Allen, J AU - Han, W AU - Lu, C AU - McPherson, B J AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract H24B EP - 07 PB - American Geophysical Union, Washington, DC VL - 2011 KW - United States KW - contaminant plumes KW - San Rafael Swell KW - simulation KW - carbon dioxide KW - cross-stratification KW - sedimentary structures KW - cross-bedding KW - carbon sequestration KW - numerical models KW - Colorado Plateau KW - Jurassic KW - injection KW - pollution KW - Navajo Sandstone KW - migration of elements KW - porosity KW - Mesozoic KW - planar bedding structures KW - reservoir properties KW - Utah KW - greenhouse gases KW - point sources KW - permeability KW - 12:Stratigraphy KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1664436590?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Supercritical+CO2+migration+under+cross-bedded+structures%3B+outcrop+analog+from+the+Jurassic+Navajo+Sandstone&rft.au=Lee%2C+S%3BAllen%2C+J%3BHan%2C+W%3BLu%2C+C%3BMcPherson%2C+B+J%3BAnonymous&rft.aulast=Lee&rft.aufirst=S&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2011/FM/sections/H/sessions/H24B/abstracts/H24B-07.html LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2015-03-19 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - carbon dioxide; carbon sequestration; Colorado Plateau; contaminant plumes; cross-bedding; cross-stratification; greenhouse gases; injection; Jurassic; Mesozoic; migration of elements; Navajo Sandstone; numerical models; permeability; planar bedding structures; point sources; pollution; porosity; reservoir properties; San Rafael Swell; sedimentary structures; simulation; United States; Utah ER - TY - JOUR T1 - Probing microbial activity in a perched water body located in a deep vadose zone AN - 1664436421; 2015-024841 AB - Waste releases to the vadose zone are a legacy of past activities at a number of Department of Energy (DOE) facilities. At the Idaho National Laboratory (INL), (super 90) Sr has been detected in perched water bodies underlying the Idaho Nuclear Technology and Engineering Center (INTEC) facility. Microbially induced calcite precipitation (MICP) using urea-hydrolyzing microbes is one proposed approach for immobilization of (super 90) Sr in the subsurface. The sequestration mechanism is co-precipitation in calcite, promoted by the production of carbonate alkalinity from ureolysis. In order to assess the potential efficacy of MICP at INTEC a field study was conducted at the INL Vadose Zone Research Park (VZRP). The VZRP is located approximately 3 km from INTEC and shares many of the same hydrologic and lithologic features but in a non-contaminated setting. We conducted experiments over two field seasons in a perched water body located approximately 15 meters below land surface, using a 5-spot wellfield design. During the first season amendments (molasses and urea) were injected into the central well and water was extracted from two wells on either side, located along a diagonal. Water samples were characterized for microbial abundance, ureolytic activity and ureC gene numbers, along with solution composition. Before, during and after the injections cross-borehole geophysical imaging was performed, using various combinations of the available wells. During the second field season in situ static experiments were conducted to specifically characterize attached and unattached microbial communities, using surrogate substrates colonized during a 12 week incubation. Based on the field data a first order in situ urea hydrolysis rate constant of 0.034 d (super -1) was estimated. This was more than an order of magnitude higher than rate constants estimated above-ground using water samples, suggesting that attached microorganisms were responsible for >90% of the observed urea hydrolysis activity. The geophysical monitoring data indicated that both radar and electrical resistivity techniques were able to sense the spatiotemporal distributions of the amendments. In the static incubation studies, the activity of the attached community was >1000x higher than the unattached community. Phospholipid biomass estimates for the attached community using two different matrices were 1,000x and 10,000x higher than for the unattached. Community structure changes were seen over time and between wells. Streamtube ensemble-based modelling was applied to simulate the combined well-to-well transport and reaction system processes, with several simplifying assumptions including an immobile biomass phase. The transport model was calibrated by fitting the traveltime distribution function to bromide tracer data, and provided a useful framework for simulation of the reactive transport as indicated by the arrival of urea at the withdrawal well. JF - American Geophysical Union Fall Meeting AU - Fujita, Y AU - Taylor, J L AU - Henriksen, J R AU - Delwiche, M AU - Gebrehiwet, T AU - Hubbard, S S AU - Spycher, N AU - Weathers, T S AU - Ginn, T R AU - Pfiffner, S M AU - Smith, R W AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract H24A EP - 06 PB - American Geophysical Union, Washington, DC VL - 2011 KW - United States KW - Sr-90 KW - isotopes KW - halogens KW - unsaturated zone KW - hydrolysis KW - bromide ion KW - suspended materials KW - simulation KW - remediation KW - Idaho National Laboratory KW - radioactive isotopes KW - perched aquifers KW - transport KW - tracers KW - Idaho KW - alkaline earth metals KW - toxic materials KW - pollution KW - migration of elements KW - bromine KW - bioremediation KW - calcite KW - aquifers KW - models KW - precipitation KW - metals KW - traveltime KW - carbonates KW - strontium KW - microorganisms KW - 02D:Isotope geochemistry KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1664436421?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Probing+microbial+activity+in+a+perched+water+body+located+in+a+deep+vadose+zone&rft.au=Fujita%2C+Y%3BTaylor%2C+J+L%3BHenriksen%2C+J+R%3BDelwiche%2C+M%3BGebrehiwet%2C+T%3BHubbard%2C+S+S%3BSpycher%2C+N%3BWeathers%2C+T+S%3BGinn%2C+T+R%3BPfiffner%2C+S+M%3BSmith%2C+R+W%3BAnonymous&rft.aulast=Fujita&rft.aufirst=Y&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2011/FM/sections/H/sessions/H24A/abstracts/H24A-06.html LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2015-03-19 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - alkaline earth metals; aquifers; bioremediation; bromide ion; bromine; calcite; carbonates; halogens; hydrolysis; Idaho; Idaho National Laboratory; isotopes; metals; microorganisms; migration of elements; models; perched aquifers; pollution; precipitation; radioactive isotopes; remediation; simulation; Sr-90; strontium; suspended materials; toxic materials; tracers; transport; traveltime; United States; unsaturated zone ER - TY - JOUR T1 - A parallel fully-coupled fully-implicit solution to reactive transport in porous media using a preconditioned Jacobian-free Newton-Krylov method AN - 1645575409; 2015-005268 AB - Multicomponent reactive transport in porous media is a tightly coupled multiphysics problem often described by a system of coupled nonlinear partial differential algebraic equations (PDAEs). For reactive transport systems that are large, highly nonlinear, and tightly coupled due to complex reactions and strong solution-mineral interactions, a preconditioned Jacobian-free Newton-Krylov (JFNK) solution approach is applied to solve the PDAEs in a fully coupled, fully implicit manner. The advantage of the JFNK method is that it avoids explicit computation and storage of the Jacobian matrix during Newton nonlinear iterations, which is highly desirable for efficient solution of large reactive transport problems. This approach is also enhanced by a physics-based blocking approach for constructing the preconditioner and multigrid algorithm for efficient inversion of preconditioners. The preconditioning strategy can account for both inter-cell transport-reaction self-coupling by using the diagonal blocks of the approximate Jacobian and the additional intra-cell transport-reaction cross-coupling through off-diagonal blocks at minimal additional computational cost. Numerical results are presented to demonstrate the efficiency and massive scalability of the solution strategy for reactive transport problems involving strong solution-mineral interactions and fast kinetics. This approach has been applied to two reactive transport systems involving induced mineral precipitation. In the first system, calcite precipitation takes place as a result of the combination of injected calcium and ureolysis-produced bicarbonate ions. In the other system, separate solutions containing calcium and bicarbonate ions are introduced into the porous medium in a parallel injection format such that calcium carbonate mineral precipitates in the mixing zone formed between the two fluids. Highly nonlinear coupling effects of fluid flow, transport, kinetic and equilibrium reactions, and changes in media properties are investigated by using the preconditioned JFNK solution approach for both systems. The numerical simulation results are compared to laboratory experiment results, and the comparison demonstrates that the fully-coupled, fully-implicit solutions can capture the transient events and sharp chemical gradients characteristic of the system, including the changes in flow properties caused by mineral precipitation and/or dissolution. JF - American Geophysical Union Fall Meeting AU - Guo, L AU - Huang, H AU - Gaston, D AU - Redden, G AU - Permann, C AU - Andrs, D AU - Fox, D T AU - Fujita, Y AU - Lu, C AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract H53L EP - 07 PB - American Geophysical Union, Washington, DC VL - 2011 KW - hydrology KW - numerical models KW - matrix KW - data processing KW - pollution KW - fluid flow KW - coupling KW - porous materials KW - equations KW - simulation KW - ground water KW - calcite KW - aquifers KW - models KW - computer programs KW - transport KW - precipitation KW - reactive transport KW - kinetics KW - carbonates KW - 21:Hydrogeology KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1645575409?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=A+parallel+fully-coupled+fully-implicit+solution+to+reactive+transport+in+porous+media+using+a+preconditioned+Jacobian-free+Newton-Krylov+method&rft.au=Guo%2C+L%3BHuang%2C+H%3BGaston%2C+D%3BRedden%2C+G%3BPermann%2C+C%3BAndrs%2C+D%3BFox%2C+D+T%3BFujita%2C+Y%3BLu%2C+C%3BAnonymous&rft.aulast=Guo&rft.aufirst=L&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2011/FM/sections/H/sessions/H53L/abstracts/H53L-07.html LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2015-01-15 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - aquifers; calcite; carbonates; computer programs; coupling; data processing; equations; fluid flow; ground water; hydrology; kinetics; matrix; models; numerical models; pollution; porous materials; precipitation; reactive transport; simulation; transport ER - TY - JOUR T1 - Toward reconciling magnitude discrepancies estimated from paleoearthquake data; a new approach for predicting earthquake magnitudes from fault segment lengths AN - 1641011563; 2015-001749 AB - We recognize a discrepancy in magnitudes estimated for several Basin and Range faults in the Intermountain Seismic Belt, U.S.A.. For example, magnitudes predicted for the Wasatch (Utah), Lost River (Idaho), and Lemhi (Idaho) Faults from fault segment lengths, Lseg, where lengths are defined between geometrical, structural, and/or behavioral discontinuities assumed to persistently arrest rupture, are consistently less than magnitudes calculated from displacements, D, along these same segments. For self-similarity, empirical relationships (e.g. Wells and Coppersmith, 1994) should predict consistent magnitudes (M) using diverse fault dimension values for a given fault (i.e. M approximately Lseg, should equal M approximately D). Typically, the empirical relationships are derived from historical earthquake data and parameter values used as input into these relationships are determined from field investigations of paleoearthquakes. A commonly used assumption--grounded in the characteristic-earthquake model of Schwartz and Coppersmith (1984)--is equating Lseg with surface rupture length, SRL. Many large historical events yielded secondary and/or sympathetic faulting (e.g. 1983 Borah Peak, Idaho earthquake) which are included in the measurement of SRL and used to derive empirical relationships. Therefore, calculating magnitude from the M approximately SRL relationship using Lseg as SRL leads to an underestimation of magnitude and the M approximately Lseg and M approximately D discrepancy. Here, we propose an alternative approach to earthquake magnitude estimation involving a relationship between moment magnitude, Mw, and length, where length is Lseg instead of SRL. We analyze seven historical, surface-rupturing, strike-slip and normal faulting earthquakes for which segmentation of the causative fault and displacement data are available and whose rupture included at least one entire fault segment, but not two or more. The preliminary Mw approximately Lseg results are strikingly consistent with Mw approximately D calculations using paleoearthquake data for the Wasatch, Lost River, and Lemhi Faults, demonstrating self-similarity and implying that the Mw approximately Lseg relationship should supplant M approximately SRL relationships currently employed in seismic hazard analyses. The relationship will permit reliable use of Lseg data from field investigations and proper use and weighting of multiple-segment-rupture scenarios in seismic hazard analyses, and eliminate the need to reconcile the Mw approximately SRL and Mw approximately D differences in a multiple-parameter relationship for segmented faults. JF - American Geophysical Union Fall Meeting AU - Carpenter, N S AU - Payne, S J AU - Schafer, A L AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract S21A EP - 2149 PB - American Geophysical Union, Washington, DC VL - 2011 KW - United States KW - North America KW - risk management KW - paleoseismicity KW - geologic hazards KW - Basin and Range Province KW - paleogeography KW - seismicity KW - Western U.S. KW - earthquake prediction KW - seismic risk KW - natural hazards KW - risk assessment KW - tectonics KW - earthquakes KW - seismotectonics KW - 19:Seismology KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1641011563?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Toward+reconciling+magnitude+discrepancies+estimated+from+paleoearthquake+data%3B+a+new+approach+for+predicting+earthquake+magnitudes+from+fault+segment+lengths&rft.au=Carpenter%2C+N+S%3BPayne%2C+S+J%3BSchafer%2C+A+L%3BAnonymous&rft.aulast=Carpenter&rft.aufirst=N&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2011/FM/sections/S/sessions/S21A/abstracts/S21A-2149 LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2015, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2015-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-31 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - Basin and Range Province; earthquake prediction; earthquakes; geologic hazards; natural hazards; North America; paleogeography; paleoseismicity; risk assessment; risk management; seismic risk; seismicity; seismotectonics; tectonics; United States; Western U.S. ER - TY - JOUR T1 - Mapping and quantification of geologic CO (sub 2) emissions at Mammoth Mountain, CA and Soda Springs, ID, USA AN - 1637530458; 2014-103334 AB - We apply a diverse set of methods to map and quantify surface CO (sub 2) emissions with distinct styles and geologic sources at two natural CO (sub 2) release sites. Mammoth Mountain is a dormant volcano located in California, where volcanogenic CO (sub 2) is emitted diffusely through soils within relatively large (km (super 2) -scale) areas. We used the eddy covariance (EC) and accumulation chamber (AC) techniques at the Horseshoe Lake tree-kill area on Mammoth Mountain to map the spatial distribution of diffuse CO (sub 2) fluxes and quantify CO (sub 2) emission rate. EC measurements of CO (sub 2) flux during September-October 2010 ranged from 85 to 1766 g m (super -2) d (super -1) . Three AC soil CO (sub 2) flux surveys during this time were used to simulate maps of soil CO (sub 2) flux and estimate total emission rates. A least-squares inversion of measured EC CO (sub 2) fluxes and corresponding modeled source weight functions was carried out and recovered 58 to 77% of the CO (sub 2) emission rates estimated based on simulated AC soil CO (sub 2) fluxes. Spatial distributions of modeled surface CO (sub 2) fluxes based on EC and AC observations showed moderate to good correspondence (R (super 2) = 0.36 to 0.70). In Soda Springs, Idaho, CO (sub 2) of deep sedimentary origin is released at the surface from a number of relatively small-area carbonated spring sources. In Fall 2011, we will use for the first time the eddy covariance method in conjunction with aqueous geochemistry to map and quantify CO (sub 2) emissions from a high discharge spring and surrounding marsh area. Our results from Mammoth Mountain and Soda Springs should provide a framework for integrated monitoring of a range of surface CO (sub 2) leakage styles and geometries. JF - American Geophysical Union Fall Meeting AU - Lewicki, J L AU - Hilley, G E AU - McLing, Travis L AU - Dobeck, L AU - Marino, B AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract H32B EP - 02 PB - American Geophysical Union, Washington, DC VL - 2011 KW - United States KW - Idaho KW - monitoring KW - statistical analysis KW - seepage KW - measurement KW - gases KW - carbon dioxide KW - California KW - Mammoth Mountain KW - Horseshoe Lake KW - volcanoes KW - springs KW - Soda Springs KW - soil gases KW - geochemistry KW - covariance analysis KW - 22:Environmental geology KW - 02A:General geochemistry UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1637530458?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Mapping+and+quantification+of+geologic+CO+%28sub+2%29+emissions+at+Mammoth+Mountain%2C+CA+and+Soda+Springs%2C+ID%2C+USA&rft.au=Lewicki%2C+J+L%3BHilley%2C+G+E%3BMcLing%2C+Travis+L%3BDobeck%2C+L%3BMarino%2C+B%3BAnonymous&rft.aulast=Lewicki&rft.aufirst=J&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-18 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - California; carbon dioxide; covariance analysis; gases; geochemistry; Horseshoe Lake; Idaho; Mammoth Mountain; measurement; monitoring; seepage; Soda Springs; soil gases; springs; statistical analysis; United States; volcanoes ER - TY - JOUR T1 - Geophysical signatures to monitor fluids and mineralization for CO (sub 2) sequestration in basalts AN - 1629939778; 2014-092468 AB - Carbon dioxide sequestration in large reservoirs can reduce emissions of this green house gas into the atmosphere. Basalts are promising host rocks due to their volumetric extend, worldwide distribution, and recent observations that CO (sub 2) -water mixtures react with basalt minerals to precipitate as carbonate minerals, trapping the CO (sub 2) . The chemical reaction between carbonic acid and minerals rich in calcium, magnesium and iron precipitates carbonates in the pore space. This process would increase the elastic modulus and velocity of the rock. At the same time, the higher compressibility of CO (sub 2) over water changes the elastic properties of the rock, decreasing the saturated rock bulk modulus and the P-wave velocity. Reservoirs where the rock properties change as a result of fluid or pressure changes are commonly monitored with seismic methods. Here we present experiments to study the feasibility of monitoring CO (sub 2) migration in a reservoir and CO (sub 2) -rock reactions for a sequestration scenario in basalts. Our goal is to measure the rock's elastic response to mineralization with non-contacting ultrasonic lasers, and the effect of fluid substitution at reservoir conditions at seismic and ultrasonic frequencies. For the fluid substitution experiment we observe changes in the P- and S-wave velocities when saturating the sample with super-critical (sc) CO (sub 2) , CO (sub 2) -water mixtures and water alone for different pore and confining pressures. The bulk modulus of the rock is significantly dependent on frequency in the 2 approximately to 10 (super 6) approximately Hz range, for CO (sub 2) -water mixtures and pure water saturations. Dry and pure CO (sub 2) (sc or gas) do not show a frequency dependence on the modulus. Moreover, the shear wave modulus is not dispersive for either fluid. The frequency dependence of the elastic parameters is related to the attenuation (1/Q) of the rock. We will show the correlation between frequency dependent moduli and attenuation data for the different elastic moduli of the rocks. Three other basalt samples were stored in a pressure chamber with a sc CO (sub 2) -water solution to study the effect of mineralization on the elastic properties of the rock. The rock elastic properties are recorded with non-contacting ultrasonic lasers at room conditions. After 15 weeks the first post-mineralization scan showed differences in the rock velocities with respect to the pre-mineralization scan. The analysis is done through coda wave interferometry and direct arrivals. The samples were inserted back into the pressure vessel for continuing mineralization and subsequent scans. Finally, we will discuss the applicability of Gassmann's equation and how the combination of mineralization together with CO (sub 2) -water mixture affects the velocity of waves in basalt rocks. JF - American Geophysical Union Fall Meeting AU - Otheim, Larry T AU - Adam, L AU - Van Wijk, Kasper AU - Batzle, M L AU - McLing, Travis L AU - Podgorney, Robert K AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract GC51A EP - 0924 PB - American Geophysical Union, Washington, DC VL - 2011 KW - P-waves KW - body waves KW - toxic materials KW - injection KW - geophysical methods KW - pollution KW - atmosphere KW - porous materials KW - global change KW - elastic waves KW - migration of elements KW - rock mechanics KW - reservoir rocks KW - remediation KW - carbon dioxide KW - seismic waves KW - greenhouse gases KW - compressibility KW - 20:Applied geophysics KW - 22:Environmental geology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1629939778?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Geophysical+signatures+to+monitor+fluids+and+mineralization+for+CO+%28sub+2%29+sequestration+in+basalts&rft.au=Otheim%2C+Larry+T%3BAdam%2C+L%3BVan+Wijk%2C+Kasper%3BBatzle%2C+M+L%3BMcLing%2C+Travis+L%3BPodgorney%2C+Robert+K%3BAnonymous&rft.aulast=Otheim&rft.aufirst=Larry&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2011/FM/sections/GC/sessions/GC51A/abstracts/GC51A-0924.html LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-12-04 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - atmosphere; body waves; carbon dioxide; compressibility; elastic waves; geophysical methods; global change; greenhouse gases; injection; migration of elements; P-waves; pollution; porous materials; remediation; reservoir rocks; rock mechanics; seismic waves; toxic materials ER - TY - JOUR T1 - A fully-coupled, fully-implicit, finite element model for solving multiphase fluid flow, heat transport and rock deformation in enhanced geothermal systems AN - 1623260598; 2014-087350 AB - Reliable reservoir performance predictions of enhanced geothermal reservoir systems require accurate and robust modeling for the coupled thermal-hydrological-mechanical processes. Conventionally, in order to reduce computational cost, these types of problems are solved using operator splitting method, usually by sequentially coupling a subsurface flow and heat transport simulator with a solid mechanics simulator via input files. However, such operator splitting approaches are applicable only to loosely coupled problems and usually converge slowly. As in most enhanced geothermal systems (EGS), fluid flow, heat transport, and rock deformation are typically strongly nonlinearly coupled, an alternative is to solve the system of nonlinear partial differential equations that govern the system simultaneously using a fully coupled solution procedure for fluid flow, heat transport, and solid mechanics. This procedure solves for all solution variables (fluid pressure, temperature and rock displacement fields) simultaneously, which leads to one large nonlinear algebraic system that needs to be solved by a strongly convergent nonlinear solver. Development over the past 10 years in the area of physics-based conditioning, strongly convergent nonlinear solvers (such as Jacobian Free Newton methods) and efficient linear solvers (such as GMRES, AMG), makes such an approach competitive. In this presentation, we will introduce a continuum-scaled parallel physics-based, fully coupled, modeling tool for predicting the dynamics of fracture initiation and propagation, fluid flow, rock deformation, and heat transport in a single integrated code named FALCON (Fracturing And Liquid-steam CONvection). FALCON is built upon a parallel computing framework developed at Idaho National Laboratory (INL) for solving coupled systems of nonlinear equations with finite element method with unstructured and adaptively refined/coarsened grids. Currently, FALCON contains poro- and thermal-elastic models, and employs two rock deformation criteria: Mohr-Coulomb and tensile failure to describe the hydro-fracturing processes, while the fluid properties (such as density, viscosity) are evaluated with most recent water/steam equations of state to compute pressure and temperature fields with higher accuracy. Simulation results from FALCON of a hydrofracing process in an idealized EGS system, an EGS cooling process in a fracture network and a combined thermal/hydrological fracturing process will be demonstrated. JF - American Geophysical Union Fall Meeting AU - Lu, C AU - Deng, S AU - Podgorney, R K AU - Huang, H AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract H21E EP - 1162 PB - American Geophysical Union, Washington, DC VL - 2011 KW - hydraulic fracturing KW - density KW - fluid flow KW - enhanced recovery KW - simulation KW - porosity KW - geothermal energy KW - finite element analysis KW - viscosity KW - fluid pressure KW - thermomechanical properties KW - reservoir properties KW - dynamic properties KW - 29A:Economic geology, geology of energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1623260598?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=A+fully-coupled%2C+fully-implicit%2C+finite+element+model+for+solving+multiphase+fluid+flow%2C+heat+transport+and+rock+deformation+in+enhanced+geothermal+systems&rft.au=Lu%2C+C%3BDeng%2C+S%3BPodgorney%2C+R+K%3BHuang%2C+H%3BAnonymous&rft.aulast=Lu&rft.aufirst=C&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-11-13 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - density; dynamic properties; enhanced recovery; finite element analysis; fluid flow; fluid pressure; geothermal energy; hydraulic fracturing; porosity; reservoir properties; simulation; thermomechanical properties; viscosity ER - TY - JOUR T1 - Simulation studies on enhanced geothermal systems with CO2 as a working fluid AN - 1623259718; 2014-087339 AB - Supercritical CO2 has recently been considered as a working fluid in enhanced geothermal systems (EGS), given its non-ionic nature, larger expansivity and lower viscosity compared to water. In addition, an EGS with supercritical CO2 as a working fluid may also act as a mechanism for CO2 sequestration. To explore this, one must understand the various interactions that may take place between the reservoir rock and the supercritical CO2. In this work, we perform simulations in two and three dimensions using the massively parallel flow and transport code PFLOTRAN, to study these interactions under various conditions (aqueous, non-aqueous and two-phase). The two dimensional results using PFLOTRAN are compared with simulations made using the TOUGH2 code. Numerical studies examining mineral dissolution and precipitation reactions that may occur in EGS that use supercritical CO2 are also shown, in addition to preliminary indications of which well placements may enable optimal flow rates and simultaneous CO2 sequestration. JF - American Geophysical Union Fall Meeting AU - Karra, S AU - Ayling, B AU - Han, W AU - Lichtner, P C AU - Lu, C AU - McPherson, Brian J AU - McLin, K S AU - Moore, J AU - Pan, F AU - Rose, P E AU - Xu, T AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract H21C EP - 1126 PB - American Geophysical Union, Washington, DC VL - 2011 KW - TOUGH2 KW - geothermal energy KW - computer programs KW - petroleum engineering KW - carbon sequestration KW - numerical models KW - viscosity KW - three-dimensional models KW - enhanced recovery KW - simulation KW - carbon dioxide KW - 29A:Economic geology, geology of energy sources UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1623259718?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Simulation+studies+on+enhanced+geothermal+systems+with+CO2+as+a+working+fluid&rft.au=Karra%2C+S%3BAyling%2C+B%3BHan%2C+W%3BLichtner%2C+P+C%3BLu%2C+C%3BMcPherson%2C+Brian+J%3BMcLin%2C+K+S%3BMoore%2C+J%3BPan%2C+F%3BRose%2C+P+E%3BXu%2C+T%3BAnonymous&rft.aulast=Karra&rft.aufirst=S&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-11-13 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - carbon dioxide; carbon sequestration; computer programs; enhanced recovery; geothermal energy; numerical models; petroleum engineering; simulation; three-dimensional models; TOUGH2; viscosity ER - TY - JOUR T1 - Mixing zones and mineral precipitation dynamics in porous media AN - 1566814175; 2014-074573 AB - Precipitation of mineral phases in subsurface environments involves coupling between reactant transport and changes in media properties that control transport. Chemical gradients within mixing zones will determine the rates and products of reactions, which in turn can modify the permeability and flow paths within the porous media. This reaction-transport coupling is being studied using double diffusion experiments and reactive transport modeling, with calcium carbonate and calcium phosphate as the model mineral systems. In particular we are investigating: (1) the interplay between permeability modifications and reactions that can change local chemical conditions, hydrodynamic conditions, and therefore the rate of precipitation, (2) narrowing ("focusing") of the precipitation zone, and (3) migration of the precipitation zone associated with asymmetry across the mixing zone with respect to precipitation rates and/or local chemical conditions. Experiments are being conducted in hydrogel (polyacrylamide) and granular (glass beads and fine-grained sand) media. Gels were used to investigate the role of diffusion alone on the structure of precipitation zones. We observed differences between carbonate and phosphate systems with respect to the induction period for precipitation, and the position and migration of the precipitation zone. One interesting observation was that multiple precipitation bands are produced in the calcium phosphate system, while no clear banding has been observed in the calcium carbonate system. Initial reactive transport simulations that couple precipitation kinetics with reactant transport and mixing appear consistent with the experimental observations. Precipitation band width and position were found to change with time, and precipitation appeared to slow subsequent reactions at the mixing interfaces. The induction time, spacing between the precipitation bands and band width in the calcium phosphate system were influenced by pH, saturation state and relative concentration of components in the reservoirs. Diffusion of dye added before and after precipitation of minerals in both model systems help to visualize the reduction in permeability (but not complete clogging) of the porous media. In experiments using granular media, pressure or density driven transport can occur, increasing the complexity of chemical gradient dynamics in the mixing zone. Precipitation reactions themselves can reduce local solution density. As a result, the position of the precipitation zone can be less stable and more mobile than in diffusion-dominated systems (e.g., gels). Such observations will have implications for solute transport in engineered precipitation strategies for subsurface systems and for interpretation of field-scale data for reaction kinetics that relies on volume averaging of chemical conditions. JF - American Geophysical Union Fall Meeting AU - Gebrehiwet, T AU - Henrikson, J AU - Guo, L AU - Fox, D T AU - Huang, H AU - Fujita, Y AU - Tu, L AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract H31E EP - 1222 PB - American Geophysical Union, Washington, DC VL - 2011 KW - hydrology KW - experimental studies KW - clogging KW - suspended materials KW - porous materials KW - fluid dynamics KW - simulation KW - laboratory studies KW - mineral composition KW - chemical reactions KW - transport KW - precipitation KW - mixing KW - fine-grained materials KW - chemical properties KW - reactive transport KW - calcium phosphates KW - kinetics KW - permeability KW - diffusivity KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1566814175?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Mixing+zones+and+mineral+precipitation+dynamics+in+porous+media&rft.au=Gebrehiwet%2C+T%3BHenrikson%2C+J%3BGuo%2C+L%3BFox%2C+D+T%3BHuang%2C+H%3BFujita%2C+Y%3BTu%2C+L%3BAnonymous&rft.aulast=Gebrehiwet&rft.aufirst=T&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2011/FM/sections/H/sessions/H31E/abstracts/H31E-1222.html LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-10-02 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - calcium phosphates; chemical properties; chemical reactions; clogging; diffusivity; experimental studies; fine-grained materials; fluid dynamics; hydrology; kinetics; laboratory studies; mineral composition; mixing; permeability; porous materials; precipitation; reactive transport; simulation; suspended materials; transport ER - TY - JOUR T1 - Orographic precipitation, wind-blown snow, and landscape evolution in glaciated mountain ranges AN - 1553086655; 2014-060960 AB - Orographic precipitation and wind-blown snow appear to significantly influence the evolution of glaciated mountain ranges, and in narrow ranges the effect is opposite from orographic precipitation in non-glaciated ranges. While fluvially-eroded ranges tend to be exhumed more on the windward side, glacially-eroded ranges can experience greater erosion on the leeward side. On the timescale of an individual glaciation, the distribution of precipitation and settling is a key component of glacier mass balance and ice extent, while on longer timescales, the interaction of precipitation and topography can play a major role in landscape evolution and range morphology. Numerical modelling of last glacial maximum (LGM) ice extents for catchments on the eastern side of the Southern Alps, New Zealand, highlights the importance of the distribution of precipitation. The accumulation areas of the glaciers would have experienced much greater precipitation than lower elevations, because of the pronounced orographic precipitation gradient, so glacier length is very sensitive to the precipitation distribution employed for any given temperature change. This is particularly challenging given the lack of modern snow monitoring at high altitudes within the Southern Alps, the likelihood of steep accumulation gradients amongst high topography, below the resolution of current datasets, and the difficulty of extrapolating modern values to the LGM. The Sangre de Cristo Range, southern Colorado, and the Bitterroot Range on the Idaho-Montana border both run close to north-south, cross-cutting the prevailing westerly winds. Drainage basins on both sides of the ranges cover similar areas, but moraines are much more substantial on the eastern sides, indicating greater glacial incision, which we suggest at least partly reflects snow blown over the range crest. The Uinta Mountains, Utah, run west-east, parallel to prevailing winds, and show topographic asymmetry across individual catchments, rather than at the range scale. Rapid rock uplift and significant glacial erosion of the north-south Teton Range, Wyoming, has created some of the highest relief in the conterminous US. While an initial topographic asymmetry would have arisen from the tectonic gradient imposed by the extensional Teton Fault on the east side of the range, the topographic asymmetry would have been exaggerated by feedbacks associated with glacial erosion. Slowly-falling snow would have been advected further into the range by prevailing westerlies, which would also have redistributed fallen snow from the subdued topography typical of the headwaters of west-draining basins. Greater topographic shading and cover by rock debris would have mitigated ablation of eastern glaciers bounded by high valley walls. Glacier size, ice flux and erosion would therefore have been enhanced in eastern-draining basins, though only the largest glaciers were capable of eroding at rates that kept pace with rock uplift. Preliminary numerical modelling results are consistent with these inferences of the importance of orographic precipitation and wind-blown snow based on topographic analysis. JF - American Geophysical Union Fall Meeting AU - Brocklehurst, S H AU - Rowan, A V AU - Plummer, M A AU - Foster, D AU - Schultz, D M AU - MacGregor, K R AU - Anonymous Y1 - 2011/12// PY - 2011 DA - December 2011 SP - Abstract A41D EP - 0118 PB - American Geophysical Union, Washington, DC VL - 2011 KW - United States KW - last glacial maximum KW - erosion KW - Sangre de Cristo Mountains KW - uplifts KW - atmospheric precipitation KW - erosion rates KW - erosion features KW - Southern Alps KW - Bitterroot Range KW - South Island KW - mountains KW - glacial erosion KW - snow KW - drainage basins KW - exhumation KW - North America KW - Idaho KW - numerical models KW - modern analogs KW - Australasia KW - landform evolution KW - wind erosion KW - U. S. Rocky Mountains KW - Montana KW - Uinta Mountains KW - Utah KW - Colorado KW - incised valleys KW - Rocky Mountains KW - New Zealand KW - 23:Geomorphology KW - 21:Hydrogeology UR - http://libproxy.lib.unc.edu/login?url=http://search.proquest.com/docview/1553086655?accountid=14244 L2 - http://vb3lk7eb4t.search.serialssolutions.com/?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&rfr_id=info:sid/ProQ%3Ageorefmodule&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.jtitle=American+Geophysical+Union+Fall+Meeting&rft.atitle=Orographic+precipitation%2C+wind-blown+snow%2C+and+landscape+evolution+in+glaciated+mountain+ranges&rft.au=Brocklehurst%2C+S+H%3BRowan%2C+A+V%3BPlummer%2C+M+A%3BFoster%2C+D%3BSchultz%2C+D+M%3BMacGregor%2C+K+R%3BAnonymous&rft.aulast=Brocklehurst&rft.aufirst=S&rft.date=2011-12-01&rft.volume=2011&rft.issue=&rft.spage=&rft.isbn=&rft.btitle=&rft.title=American+Geophysical+Union+Fall+Meeting&rft.issn=&rft_id=info:doi/ L2 - http://abstractsearch.agu.org/meetings/2011/FM/sections/A/sessions/A41D/abstracts/A41D-0118.html LA - English DB - GeoRef N1 - Conference title - American Geophysical Union 2011 fall meeting N1 - Copyright - GeoRef, Copyright 2014, American Geosciences Institute. Reference includes data supplied by, and/or abstract, Copyright, American Geophysical Union, Washington, DC, United States N1 - Date revised - 2014-01-01 N1 - PubXState - DC N1 - Last updated - 2014-08-14 N1 - CODEN - #07548 N1 - SubjectsTermNotLitGenreText - atmospheric precipitation; Australasia; Bitterroot Range; Colorado; drainage basins; erosion; erosion features; erosion rates; exhumation; glacial erosion; Idaho; incised valleys; landform evolution; last glacial maximum; modern analogs; Montana; mountains; New Zealand; North America; numerical models; Rocky Mountains; Sangre de Cristo Mountains; snow; South Island; Southern Alps; U. S. Rocky Mountains; Uinta Mountains; United States; uplifts; Utah; wind erosion ER - TY - JOUR T1 - THETRIS: A micro-scale temperature and gas release model for TRISO fuel AN - 1010881380; 16138734 AB - The dominating mechanism in the passive safety of gas-cooled, graphite-moderated, high-temperature reactors (HTRs) is the Doppler feedback effect. These reactor designs are fueled with submillimeter-sized kernels formed into tristructural-isotropic (TRISO) particles that are imbedded in a graphite matrix. The best spatial and te