Kang Seog Kim Distinguished R&D Staff Contact 865.576.5052 | KIMK1@ORNL.GOV All Publications Cell Dancoff-Based Embedded Self-Shielding Capability for Doubly Heterogeneous Particulate Fuels in SCALE/Polaris Revisit of the Dancoff-Based Wigner-Seitz Approximation for Pointwise and Multigroup Resonance Self-Shielding Calculations in SCALE 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 Library 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 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 Development of MPACT for Full-Core Simulations of MAGNOX Gas-Cooled Nuclear Reactors... MPACT Verification With Magnox Reactor Neutronics Progression Problems 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 the MPACT 69-group Library for Magnox Reactor Analysis using CASL VERA... 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... Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 … Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae 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
