Presented By: Nuclear Engineering & Radiological Sciences
NERS Colloquia Series: The Thermal-Hydraulics Modeling and Simulation Tools and Developments at the INL
Theron Marshall, Idaho National Laboratory
Abstract:
As the Department of Energy lead laboratory for nuclear energy research and development, Idaho National Laboratory is preparing modeling and simulation tools to support both the existing nuclear fleet and advanced reactor designs. Dr. Marshall will present some of the thermal hydraulics challenges facing nuclear reactors and the INL research activities to provide modeling solutions for these challenges. Discussion topics will include PWR fuel rod ballooning, dynamic flow induced vibration, oxide layer growth, steam ingress for high temperature gas reactors, thermal striping with liquid sodium, and molten salt corrosion.
Bio:
Dr. Marshall is the engineering manager for the Idaho National Laboratory (INL) Thermal Fluid Systems Methods and Analysis Department. His department develops software for and performs modeling and simulation analyses in support of existing and advanced reactor designs. Dr. Marshall is also a Principal Investigator for the U.S. High Performance Research Reactor program with responsibilities of managing (1) irradiation experiments that support the conversion of Massachusetts Institute Technology Reactor and National Bureau of Standards Reactor from highly enriched uranium to low enriched uranium plate fuel and (2) fluid surface interaction model development at the INL. Dr. Marshall’s background is thermal hydraulics and he has nuclear engineering research experience at INL and commercial experience at General Electric Hitachi Nuclear Energy. He has a Ph.D in nuclear engineering from Rensselaer Polytechnic Institute.
As the Department of Energy lead laboratory for nuclear energy research and development, Idaho National Laboratory is preparing modeling and simulation tools to support both the existing nuclear fleet and advanced reactor designs. Dr. Marshall will present some of the thermal hydraulics challenges facing nuclear reactors and the INL research activities to provide modeling solutions for these challenges. Discussion topics will include PWR fuel rod ballooning, dynamic flow induced vibration, oxide layer growth, steam ingress for high temperature gas reactors, thermal striping with liquid sodium, and molten salt corrosion.
Bio:
Dr. Marshall is the engineering manager for the Idaho National Laboratory (INL) Thermal Fluid Systems Methods and Analysis Department. His department develops software for and performs modeling and simulation analyses in support of existing and advanced reactor designs. Dr. Marshall is also a Principal Investigator for the U.S. High Performance Research Reactor program with responsibilities of managing (1) irradiation experiments that support the conversion of Massachusetts Institute Technology Reactor and National Bureau of Standards Reactor from highly enriched uranium to low enriched uranium plate fuel and (2) fluid surface interaction model development at the INL. Dr. Marshall’s background is thermal hydraulics and he has nuclear engineering research experience at INL and commercial experience at General Electric Hitachi Nuclear Energy. He has a Ph.D in nuclear engineering from Rensselaer Polytechnic Institute.
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