| Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor A Rykhlevskii, JW Bae, KD Huff Annals of Nuclear Energy 128, 366-379, 2019 | 75 | 2019 |
| Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator JW Bae, A Rykhlevskii, G Chee, KD Huff Annals of Nuclear Energy 139, 107230, 2020 | 33 | 2020 |
| ARC reactor neutronics multi-code validation JW Bae, E Peterson, J Shimwell Nuclear Fusion 62 (6), 066016, 2022 | 26 | 2022 |
| High Flux Isotope Reactor Low-Enriched Uranium Low Density Silicide Fuel Design Parameters BR Betzler, D Chandler, JW Bae, G Ilas, JL Meszaros Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2021 | 17 | 2021 |
| Molten salt reactor neutronic and fuel cycle sensitivity and uncertainty analysis JW Bae, B Betzler, A Worrall Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | 17 | 2019 |
| FERMI: fusion energy reactor models integrator V Badalassi, A Sircar, JM Solberg, JW Bae, K Borowiec, P Huang, ... Fusion Science and Technology 79 (3), 345-379, 2023 | 16 | 2023 |
| High Flux Isotope Reactor Low Enriched Uranium High Density Silicide Fuel Design Parameters JW Bae, BR Betzler, D Chandler, G Ilas, JL Meszaros ORNL/TM-2020-1799. United States, 2021 | 16 | 2021 |
| FERMI: A multi-physics simulation environment for fusion reactor blanket A Sircar, JW Bae, E Peterson, J Solberg, V Badalasi Lawrence Livermore National Lab.(LLNL), Livermore, CA (United States), 2022 | 11 | 2022 |
| Standardized verification of the Cyclus fuel cycle simulator JW Bae, JL Peterson-Droogh, KD Huff Annals of Nuclear Energy 128, 288-291, 2019 | 11 | 2019 |
| High Flux Isotope Reactor Low Enriched Uranium High Density Silicide Thick Cladding Fuel Design Parameters J Bae, B BETZLER, D Chandler, G Ilas, J MESZAROS ORNL/TM-2020/1964, 2021 | 10 | 2021 |
| Conceptual Fuel Element Design Candidates for Conversion of High Flux Isotope Reactor with Low-Enriched Uranium Silicide Dispersion Fuel D Chandler, BR Betzler, JW Bae, DH Cook, G Ilas EPJ Web of Conferences 247, 08017, 2021 | 10 | 2021 |
| Molten Salt Reactor Safeguards: The Necessity of Advanced Modeling and Simulations to Inform on Fundamental Signatures A Worrall, JW Bae, BR Betzler, MS Greenwood, LG Worrall Proceedings from 60th INMM Meeting, INMM, 2019 | 9 | 2019 |
| arfc/saltproc: Code for online reprocessing simulation of molten salt reactor with external depletion solver SERPENT A Rykhlevskii, JW Bae, K Huff Zenodo, Mar, 2018 | 9 | 2018 |
| Fuel Conversion Efforts at the High Flux Isotope Reactor–a 2020 Status Update D Chandler, J Meszaros, B Betzler, JW Bae, DH Cook, V Fudurich, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 8 | 2020 |
| 252Cf Production at the High Flux Isotope Reactor: Nuclear Data Selection and LEU Conversion Impacts D Hartanto, D Chandler, JW Bae, J Burns, C Sizemore Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2023 | 7 | 2023 |
| Metaheuristic Optimization Tool I Variansyah, JW Bae, BR Betzler, G Ilas Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020 | 7 | 2020 |
| Synergistic spent nuclear fuel dynamics within the European Union JW Bae, CE Singer, KD Huff Progress in Nuclear Energy 114, 1-12, 2019 | 7 | 2019 |
| Fuel cycle depletion validation and code-to-code verification studies for High Flux Isotope Reactor highly and low-enriched uranium fuel designs D Chandler, JW Bae, BR Betzler, D Hartanto, CR Daily Annals of Nuclear Energy 190, 109895, 2023 | 5 | 2023 |
| High Flux Isotope Reactor Low Enriched Uranium U-10Mo Fuel Design Parameters BR Betzler, D Chandler, JW Bae, EE Davidson, G Ilas, JL Meszaros Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2022 | 5 | 2022 |
| Current Status of Predictive Transition Capability in Fuel Cycle Simulation KD Huff, JW Bae, RR Flanagan, AM Scopatz Proceedings of Global, 11, 2017 | 5 | 2017 |
Benjamin R. BetzlerOak Ridge National LaboratoryVerified email at ornl.gov