Aaron Wysocki Staff Research Scientist Contact 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 Subchannel Methods Development for Modeling of Light Water Reactors at Oak Ridge National Laboratory 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 CTF Validation and Verification: Version 4.3 Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions TRACE Analysis of the STS Target Flow Loop Conceptual Design 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... Validation of Thermohydraulic Simulations using RELAP for Critical Dual Purpose Canisters Assessment of the Effect of Prototypic High-Burnup Operating Conditions of Fuel Fragmentation, Relocation, and Dispersal Susceptibility 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 ›› 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
