TY - BOOK
T1 - Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration
AU - Bostelmann, Rike
AU - Davidson, Eva
AU - Wieselquist, William
AU - Luxat, David Lyle
AU - Wagner, Kenneth
AU - Albright, Lucas
PY - 2023
Y1 - 2023
N2 - To assess the modeling and simulation capabilities for radionuclide characterization, criticality, and shielding in the nuclear fuel cycle of non-light–water reactor (LWR) technologies, the US Nuclear Regulatory Commission (NRC) initiated a collaborative project between the NRC, Sandia National Laboratories (SNL), and Oak Ridge National Laboratory (ORNL) with the goal to demonstrate capabilities of MELCOR and SCALE to calculate accident scenarios in all stages of the nuclear fuel cycle for relevant non-LWRs. The first project task was to develop representative nuclear fuel cycles and identify potential hazards and accident scenarios in the individual fuel cycle stages based on publicly available information. Because the nuclear fuel cycle is not established for any non-LWR concept, many assumptions were made, and it is anticipated that the details of the fuel cycles will eventually look different.
AB - To assess the modeling and simulation capabilities for radionuclide characterization, criticality, and shielding in the nuclear fuel cycle of non-light–water reactor (LWR) technologies, the US Nuclear Regulatory Commission (NRC) initiated a collaborative project between the NRC, Sandia National Laboratories (SNL), and Oak Ridge National Laboratory (ORNL) with the goal to demonstrate capabilities of MELCOR and SCALE to calculate accident scenarios in all stages of the nuclear fuel cycle for relevant non-LWRs. The first project task was to develop representative nuclear fuel cycles and identify potential hazards and accident scenarios in the individual fuel cycle stages based on publicly available information. Because the nuclear fuel cycle is not established for any non-LWR concept, many assumptions were made, and it is anticipated that the details of the fuel cycles will eventually look different.
KW - 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
KW - 97 MATHEMATICS AND COMPUTING
U2 - 10.2172/2251628
DO - 10.2172/2251628
M3 - Commissioned report
BT - Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration
CY - United States
ER -