Kang Seog Kim Distinguished R&D Staff Contact kimk1@ornl.gov | 865.576.5052 All Publications Benchmark Calculations for Peach Bottom Unit 2 and Hatch Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package Benchmark Calculations for BEAVRS and Watt Bar Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package Peaking Factor Uncertainty of VERA-MPACT with the ENDF/B-VII.1 51-Group Library through Benchmark Calculations for Critical Experiments On-the-Fly Energy Condensation for Whole-Core Multiphysics Simulations On-the-Fly Energy Group Condensation for Whole-Core Multiphysics Simulations... Cell Dancoff-Based Embedded Self-Shielding Capability for Doubly Heterogeneous Particulate Fuels in SCALE/Polaris... Dancoff-Based Wigner-Seitz Approximation for the Subgroup Resonance Self-Shielding in the VERA Neutronics Simulator MPACT... Validation of MPACT BWR Capabilities Against Critical Experiments... Revisit of the Dancoff-Based Wigner-Seitz Approximation for Pointwise and Multigroup Resonance Self-Shielding Calculations in... Development and Performance Simulations of the MPACT-AGREE Code Coupling Interface for MAGNOX Reactors... Spatially Dependent Resonance Self-Shielding Capability For Non-Uniform Temperature Profile In SCALE-6.3 XSPROC-BONAMI... Improvement Of The SCALE-XSPROC Capability For High-Temperature Gas-Cooled Reactor Analysis... Neutronic Characteristics of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for Light-Water Reactor Analysis... Reactivity Underestimation of ENDF/B-VIII.0 Compared with ENDF/B-VII.1 for the Pressurized Water Reactor Depletion Analysis... Improved MPACT energy deposition and explicit heat generation coupling with CTF... Lattice Physics Calculations Using the Embedded Self-Shielding Method in Polaris, Part I: Methods and Implementation... An In-scattering Transport Correction by the Neutron Leakage Conservation Method and Its Application to the DeCART Multigroup... An improved energy deposition model in MPACT with simplified gamma smearing and time-dependent delayed energy... Multigroup cross section library and processing for the CASL VERA neutronic simulators... Secondary-Source Core Reload Modeling with VERA... MPACT Diffusion Coefficient Improvement Through Westinghouse Collaboration... Benchmarking VERA for Criticality and Depletion Calculations of Accident Tolerant Fuels... MPACT Verification With Magnox Reactor Neutronics Progression Problems... Development of MPACT for Full-Core Simulations of MAGNOX Gas-Cooled Nuclear Reactors... Improvement of SCALE-XSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation... 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 Nuclear Transmutation and Decay Physics SCALE
