| 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 | 98 | 2017 |
| 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 | 62 | 2020 |
| 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 | 58 | 2015 |
| 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 | 50 | 2017 |
| Architecture and properties of TCR fuel form KA Terrani, BC Jolly, MP Trammell, G Vasudevamurthy, D Schappel, ... Journal of Nuclear Materials 547, 152781, 2021 | 42 | 2021 |
| 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 | 41 | 2018 |
| 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 | 40 | 2017 |
| 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 | 39 | 2020 |
| 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 | 37 | 2020 |
| 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 | 36 | 2021 |
| 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 | 36 | 2018 |
| 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 | 34 | 2021 |
| 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 | 32 | 2016 |
| 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 | 30 | 2019 |
| Advanced manufacturing for nuclear core design BR Betzler, BJ Ade, AJ Wysocki, MS Greenwood, JJW Heineman, ... EPJ Web of Conferences 247, 01011, 2021 | 29 | 2021 |
| 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 | 28 | 2019 |
| 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 | 28 | 2017 |
| 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 | 26 | 2019 |
| 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 | 26 | 2018 |
| 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 | 25 | 2017 |
