Kang Seog Kim Distinguished R&D Staff Contact kimk1@ornl.gov | 865.576.5052 All Publications 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... Development of the MPACT 69-group Library for Magnox Reactor Analysis using CASL VERA... Improvement of SCALE-XSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation An Improved Energy Deposition Model in MPACT and Explicit Heat Generation Coupling with CTF Development of Perturbed MPACT Multigroup Libraries and the Perturbation Methodology for Subgroup Data Source Range Detector Response Modeling using VERA Summary: Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-group Libraries for Advanced Reactor Analysis... ATF Benchmark Problems Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-Group Libraries for Advanced Reactor Analysis... Spatially dependent embedded self-shielding method for nonuniform temperature distribution... Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure... Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification... The SCALE/AMPX multigroup cross section processing for fast reactor analysis... Comparison Between Spatially Dependent Embedded Self-Shielding and Subgroup Methods Verification and Validation of the ENDF/B-VII.1 v4.3m1 MPACT 51-group Cross Section Library... Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis... VERA Depletion Benchmarks by CASL VERA, SERPENT and McCARD with ENDF/B-VII.0 and VII.1... The AMPX/SCALE Multigroup Cross-Section Processing for Fast Reactor Analysis... Simplified AMPX Library Capability of the CASL Neutronics Simulator MPACT... Improvements in the Polaris Implementation of the Embedded Self-Shielding Method... Automatic Coarse Energy Group Structure Optimization by Minimizing Reaction Rate Differences for the SCALE and CASL Code Syst... Development of the CASL-VERA V4.2m5 MPACT 51-group Libraries for ENDF/B-VII.0 and VII.1... VERA Core Simulator Methodology for PWR Cycle Depletion... 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 Nuclear Transmutation and Decay Physics SCALE