Jin Whan Bae Research Associate Contact baej@ornl.gov All Publications Californium-252 production at the High Flux Isotope Reactor − I: Validation study using campaign data Californium-252 production at the High Flux Isotope Reactor - II: Comparison between the highly enriched uranium and a proposed low-enriched uranium core Plutonium-238 Production Sensitivity and Validation Studies Continued: Effects of Core Component Compositions... Comparative Analysis of Heat Deposition Rates and DPA in the HFIR Flux Trap to Support LEU Conversion Machine learning framework for predicting uranium enrichments from M400 CZT gamma spectra Sensitivity and Validation Studies of Plutonium-238 Production with Shift and ORIGEN Heat Deposition Analysis of Target Materials in the High Flux Isotope Reactor for HEU and LEU Cores High Flux Isotope Reactor Low-Enriched Uranium Conversion - Design and Fuel Qualification Overview Californium-252 Production Validation Studies at the High Flux Isotope Reactor with Campaign 78 Data Pressurized Water Reactor Gadolinia Pin Location Optimization High Flux Isotope Reactor Low-Enriched Uranium Conversion Overview Integral analysis of the effect of material dimension and composition on tokamak neutronics * 3D high-fidelity automated neutronics guided optimization of fusion blanket designs... Fuel Conversion Efforts at the High Flux Isotope Reactor – a 2023 Status Update Uncertainty Quantification of Fuel Inhomogeneity in Low-enriched Uranium Silicide High Flux Isotope Reactor Design Establishing the Impact of HFIR LEU Conversion through a Comprehensive Set of Reactor Physics Studies Pressurized Water Reactor Gadolinia Pin Location Optimization Impact of fusion reactor neutronics modeling for transmutation and thermal feedback FERMI: FUSION ENERGY REACTOR MODELS INTEGRATOR - Integrated High-fidelity Multiphysics Framework for Fusion Modeling Shutdown dose rate analysis with the Shift Monte Carlo radiation transport code and modular verification workflow Fuel cycle depletion validation and code-to-code verification studies for High Flux Isotope Reactor highly and low-enriched u... Fully Implicit Conjugate Heat Transfer Analysis of the ARC-Class Vacuum Vessel Nuclear Data Uncertainty Quantification of High Flux Isotope Reactor Low-Enriched Uranium Design 252Cf Production at the High Flux Isotope Reactor: Nuclear Data Selection and LEU Conversion Impacts Enabling multiphysics simulation of fusion blankets on exascale architecture using OpenFOAM Pagination Current page 1 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
