Aaron Wysocki Staff Research Scientist Contact 865.241.6888 | WYSOCKIAJ@ORNL.GOV All Publications A study on the impact of using a subchannel resolution for modeling of large break loss of coolant accidents 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 CTF Theory Manual: Version 4.4 NEAMS Burnup Extension Accomplishments and Remaining Modeling Gaps Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions CTF Validation and Verification: Version 4.4 Status of Multiphysics Modeling of Critical DPCs in a Geological Repository... Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies CTF Validation and Verification: Version 4.3 Subchannel Methods Development for Modeling of Light Water Reactors at 91°µÍø CTF Theory Manual: Version 4.3... Comparison Between Pin-by Pin Subchannel and System Level Thermal Hydraulic Results for High Burnup Loss-of-Coolant Applications Assessment and testing of CTF for LOCA reflood conditions TRACE Analysis of the STS Target Flow Loop Conceptual Design Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions Coupling of CTF and RELAP5-3D Within an Enhanced Fidelity Nuclear Power Plant Simulator CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pre... Assessment of the Effect of Prototypic High-Burnup Operating Conditions of Fuel Fragmentation, Relocation, and Dispersal Susceptibility Validation of Thermohydraulic Simulations using RELAP for Critical Dual Purpose Canisters Transformational Challenge Reactor Design Characteristics Coupling of CTF and RELAP5-3D Within an Enhanced Fidelity Nuclear Power Plant Simulator Analysis of Postulated Accident Scenarios for the Transformational Challenge Reactor VERA Transient Capability to Support ATF/High Burnup Fuel/HALEU Conversion Full core LOCA safety analysis for a PWR containing high burnup fuel... 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
