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Jin Whan Bae
Jin Whan Bae
E-mail confirmado em ornl.gov - Página inicial
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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
602019
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
252020
Molten salt reactor neutronic and fuel cycle sensitivity and uncertainty analysis
JW Bae, BR Betzler, A Worrall
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019
132019
ARC reactor neutronics multi-code validation
JW Bae, E Peterson, J Shimwell
Nuclear Fusion 62 (6), 066016, 2022
122022
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 Lab.(ORNL), Oak Ridge, TN (United States). High Flux …, 2021
112021
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/XXX, Oak Ridge National Laboratory (expected 2020), 2021
112021
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
102022
Standardized verification of the Cyclus fuel cycle simulator
JW Bae, JL Peterson-Droogh, KD Huff
Annals of Nuclear Energy 128, 288-291, 2019
102019
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
82021
High Flux Isotope Reactor low enriched uranium high density silicide thick cladding fuel design parameters
J Bae, BR Betzler, D Chandler, G Ilas, JL Meszaros
ORNL/TM-2020/1964, Oak Ridge National Laboratory, 2021
72021
Metaheuristic Optimization Tool
I Variansyah, JW Bae, BR Betzler, G Ilas
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
72020
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
72018
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
62023
Fuel Conversion Efforts at the High Flux Isotope Reactor–a 2020 Status Update
D Chandler, J Meszaros, BR Betzler, JW Bae, DH Cook, VD Fudurich, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
62020
Automated Fuel Design Optimization for High Flux Isotope Reactor Low Enriched Uranium Core Design
JW Bae, BR Betzler, D Chandler, G Ilas
PHYSOR 2020, 2020
62020
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
62019
Synergistic spent nuclear fuel dynamics within the European Union
JW Bae, CE Singer, KD Huff
Progress in Nuclear Energy 114, 1-12, 2019
52019
Solving Advection Problems with Isotopic Evolution with SCALE/ORIGEN
JW Bae, B Betzler, W Wieselquist
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021
42021
Current Status of Predictive Transition Capability in Fuel Cycle Simulation
KD Huff, JW Bae, KA Mummah, RR Flanagan, AM Scopatz
Proceedings of Global, 11, 2017
42017
Report on Fuel Cycle Facility Requirements for Deployment of Demonstration Reactors and Potential Evolutionary Fuel Cycle Scenarios
TK Kim, S Richards, A Cuadra, R Hays, B Dixon, JW Bae, E Davidson
Argonne National Lab.(ANL), Argonne, IL (United States), 2022
32022
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