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Benjamin R. Betzler
Benjamin R. Betzler
在 ornl.gov 的电子邮件经过验证 - 首页
标题
引用次数
引用次数
年份
Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE
BR Betzler, JJ Powers, A Worrall
Annals of Nuclear Energy 101, 489-503, 2017
982017
Transformational Challenge Reactor preconceptual core design studies
BR Betzler, BJ Ade, AJ Wysocki, PK Jain, PC Chesser, MS Greenwood, ...
Nuclear Engineering and Design 367, 110781, 2020
622020
Modeling and simulations for the high flux isotope reactor cycle 400
G Ilas, D Chandler, BJ Ade, EE Sunny, BR Betzler, D Pinkston
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015
582015
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis
NR Brown, BR Betzler, JJ Carbajo, AJ Wysocki, MS Greenwood, C Gentry, ...
Annals of Nuclear Energy 103, 49-59, 2017
502017
Architecture and properties of TCR fuel form
KA Terrani, BC Jolly, MP Trammell, G Vasudevamurthy, D Schappel, ...
Journal of Nuclear Materials 547, 152781, 2021
422021
Multi-physics simulations for molten salt reactor evaluation: Chemistry modeling and database development
JW Mcmurray, TM Besmann, J Ard, B FItzpatrick, M Piro, J Jerden, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
412018
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview
AL Qualls, BR Betzler, NR Brown, JJ Carbajo, MS Greenwood, R Hale, ...
Annals of Nuclear Energy 107, 144-155, 2017
402017
Demonstration of the advanced dynamic system modeling tool TRANSFORM in a molten salt reactor application via a model of the molten salt demonstration reactor
MS Greenwood, BR Betzler, AL Qualls, J Yoo, C Rabiti
Nuclear Technology 206 (3), 478-504, 2020
392020
Modeling and simulation of a High Flux Isotope Reactor representative core model for updated performance and safety basis assessments
D Chandler, BR Betzler, EE Davidson, G Ilas
Nuclear Engineering and Design 366, 110752, 2020
372020
Candidate core designs for the transformational challenge reactor
BJ Ade, BR Betzler, AJ Wysocki, MS Greenwood, PC Chesser, KA Terrani, ...
Journal of Nuclear Engineering 2 (1), 74-85, 2021
362021
Fuel cycle and neutronic performance of a spectral shift molten salt reactor design
BR Betzler, S Robertson, EE Davidson, JJ Powers, A Worrall, L Dewan, ...
Annals of Nuclear Energy 119, 396-410, 2018
362018
Roadmap for thermal property measurements of Molten Salt Reactor systems
JW Mcmurray, K Johnson, C Agca, BR Betzler, DJ Kropaczek, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021
342021
Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading
D Chandler, B Betzler, GJ Hirtz, G Ilas, E Sunny
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2016
322016
Modeling and simulation functional needs for molten salt reactor licensing
BR Betzler, F Heidet, B Feng, C Rabiti, T Sofu, NR Brown
Nuclear Engineering and Design 355, 110308, 2019
302019
Advanced manufacturing for nuclear core design
BR Betzler, BJ Ade, AJ Wysocki, MS Greenwood, JJW Heineman, ...
EPJ Web of Conferences 247, 01011, 2021
292021
Fuel cycle performance of fast spectrum molten salt reactor designs
A Rykhlevskii, B Betzler, A Worrall, KD Huff
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019
282019
High-fidelity modeling and simulation for a high flux isotope reactor low-enriched uranium core design
BR Betzler, D Chandler, EE Davidson, G Ilas
Nuclear Science and Engineering 187 (1), 81-99, 2017
282017
Neutronic and thermal-hydraulic feasibility studies for High Flux Isotope Reactor conversion to low-enriched uranium silicide dispersion fuel
D Chandler, B Betzler, D Cook, G Ilas, D Renfro
Annals of Nuclear Energy 130, 277-292, 2019
262019
Dynamic system models for informing licensing and safeguards investigations of molten salt reactors
MS Greenwood, BR Betzler, AL Qualls
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018
262018
Heat deposition analysis for the High Flux Isotope Reactor’s HEU and LEU core models
EE Davidson, BR Betzler, D Chandler, G Ilas
Nuclear Engineering and Design 322, 563-576, 2017
252017
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