Robert K Salko Jr Staff Research Scientist Contact salkork@ornl.gov | 865.576.5339 All Publications CTF Validation and Verification: Version 4.4 Heat and Mass Transfer Coefficients in the Molten Salt Reactor Experiment Subchannel Methods Development for Modeling of Light Water Reactors at Oak Ridge National Laboratory CTF Validation and Verification: Version 4.3 Assessment and testing of CTF for LOCA reflood conditions Comparison Between Pin-by Pin Subchannel and System Level Thermal Hydraulic Results for High Burnup Loss-of-Coolant Applications CTF Theory Manual: Version 4.3... Implementation of a Gas Transport Model in SAM for Modeling of Molten Salt Reactors Advanced two-phase subchannel method via non-linear iteration... Coupling of CTF and RELAP5-3D Within an Enhanced Fidelity Nuclear Power Plant Simulator Improvement of two-phase closure models in CTF using Bayesian inference CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pre... Verification and Validation of the Alternative Nonlinear Two-phase Subchannel (ANTS) Code Bypass Flow Model Implementation for VERA BWR Multiscale Thermal Hydraulic Coupling Methods for Boiling Water Reactor Simulation... Coupling of CTF and RELAP5-3D Within an Enhanced Fidelity Nuclear Power Plant Simulator CTF Improved Drag Model and Flow Regime Transition Criteria Implementation of Two-Phase Gas Transport into VERA for Molten Salt Reactor Analysis VERA Transient Capability to Support ATF/High Burnup Fuel/HALEU Conversion... Implementation of a Drift-Flux Model in SAM for Modeling of Passively Transported GAS in Molten Salt Reactors Integration roadmap for multi-scale, multi-physics mass accountancy in Molten Salt Reactors... Code and Solution Verification Assessment of the CTF Thermal Hydraulic Subchannel Code Development of CTF modeling of interfacial drag, wall shear, and interfacial heat transfer for bubbly and annular-mist flow regimes Coupling of CTF and TRACE for Modeling of Transients... Multiphysics Coupling Methods for Molten Salt Reactor Modeling and Simulation in VERA... 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 Advanced Reactor Engineering and Development Section Advanced Reactor Systems Group User Facilities Oak Ridge Leadership Computing Facility
