Jin Whan Bae Research Associate Contact BAEJ@ORNL.GOV All Publications Enabling multiphysics simulation of fusion blankets on exascale architecture using OpenFOAM Reactor Physics Validation Roadmap for the High Flux Isotope Reactor Conversion to Low-Enriched Uranium Fuel... Isotope Production and Materials Irradiation Research Studies to Support HFIR LEU Conversion Assessment Integrated Fusion Neutronics Workflow for MCNP, OpenMC, and Shift Automated reactor physics analysis framework of High Flux Isotope Reactor low-enriched uranium silicide dispersion fuel designs FERMI: Fusion Energy Reactor Models Integrator Multiphysics code coupling for fusion blankets Remining and Restoring Abandoned US Mining Sites: The Case for Materials Needed for Zero-Carbon Transition Light Water Reactor LEU+ Lattice Optimization Reactor Physics Characteristics of High Flux Isotope Reactor Core Designs with Low-Enriched Uranium Fuels LEU+ BWR Lattice Design Optimization of Using SCALE/Polaris ARC reactor neutronics multi-code validation High Flux Isotope Reactor Low Enriched Uranium U-10Mo Fuel Design Parameters FERMI: A MULTI-PHYSICS SIMULATION ENVIRONMENT FOR FUSION REACTOR BLANKET Multi-Physics simulations for Fusion reactor blankets Optimization of a Simplified ARC Reactor Design Through Coupled Neutronics, Thermal Hydraulics Modeling Solving Advection Problems with Isotopic Evolution with SCALE/ORIGEN Characteristic Solutions for Advection Problems with Isotopic Evolution with SCALE/ORIGEN High Flux Isotope Reactor Low Enriched Uranium Low Density Silicide Fuel Design Parameters Neutronic and Thermal-Hydraulic Design Studies for High Flux Isotope Reactor Conversion to Low-Enriched Uranium High Density ... Fuel Conversion Efforts at the High Flux Isotope Reactor – a 2020 Status Update Metaheuristic Optimization Tool Automated Fuel Design Optimization for High Flux Isotope Reactor Low Enriched Uranium Core Design Conceptual Fuel Element Design Candidates for Conversion of High Flux Isotope Reactor with Low-Enriched Uranium Silicide Dispersion Fuel Neural Network Approach to Model Mixed Oxide Fuel Cycles in Cyclus, a Nuclear Fuel Cycle Simulator Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 Next page ›› Last page Last » Key Links Curriculum Vitae ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Modeling and Simulation Development and Deployment Section Research and Test Reactor Physics Group SCALE
