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... SAM: A Modern System Code for Advanced Non-LWR Safety Analysis The MOOSE Fluid Properties Module FY24 Mole Development Updates and SAM-Mole Coupling for MSR Species Transport Applications... High-Burnup BWR LOCA Burst Analysis Framework Development and Demonstration... 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... 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 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 91°µÍø 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 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
