Robert Salko Jr Staff Research Scientist Contact 865.576.5339 | SALKORK@ORNL.GOV All Publications A study on the impact of using a subchannel resolution for modeling of large break loss of coolant accidents Comparison of Hybrid and Pure Machine Learning Models in Limited Data Scenarios... The MOOSE Fluid Properties Module FY24 Mole Development Updates and SAM-Mole Coupling for MSR Species Transport Applications... SAM: A Modern System Code for Advanced Non-LWR Safety Analysis Bubble mass transport measurement in the large-scale tests loops at 91°µÍø Initial assessment of CTF for time-at-temperature applications... Recent High Burnup LOCA Testing at 91°µÍø... High-Burnup BWR LOCA Burst Analysis Framework Development and Demonstration... Assessment of the CTF subchannel code for modeling a large-break loss-of-coolant accident reflood transient Implementation of a Drift Flux Model into SAM with Development of a Verification and Validation Test Suite for Modeling of No... Machine Learning for Gas Void Fraction Prediction in Two-Phase Flow... CTF Theory Manual: Version 4.4 NEAMS Burnup Extension Accomplishments and Remaining Modeling Gaps Heat and Mass Transfer Coefficients in the Molten Salt Reactor Experiment CTF Validation and Verification: Version 4.4 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 Subchannel Methods Development for Modeling of Light Water Reactors at 91°µÍø 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 Pagination Current page 1 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 Advanced Reactor Engineering and Development Section Advanced Reactor Systems Group User Facilities
