TY - GEN
T1 - NEAMS Activities Supporting Mechanistic Source Term Model Development for Molten Salt Reactors
AU - Shahbazi, Shayan
AU - Tano, Mauricio
AU - Thomas, Sara
AU - Walker, Samuel
AU - Jaoude, Abdalla Abou
AU - Jeong, Yeongshin
AU - Gong, Rushi
AU - Kam, Dong Hoon
AU - Chen, Ben
AU - Grabaskas, David
N1 - Publisher Copyright:
© 2023 Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023. All Rights Reserved.
PY - 2023
Y1 - 2023
N2 - As vendors of MSR technology enter the reactor licensing process, the determination of an appropriate and accurate source term will be central to the approval of the design by the U.S. NRC. The Multiphysics Applications technical area under the NEAMS program within DOE-NE is supporting development of mechanistic source term (MST) modeling and simulation tools to assist in the licensing process for advanced (non-LWR) reactors. Additional activities such as assessing and demonstrating multiphysics coupling of NEAMS-developed tools for MSRs are also ongoing. Multiphysics simulations can directly support licensing activities such as with transient analyses or indirectly by providing initial or boundary conditions to radionuclide (RN) transport analyses. Such efforts under NEAMS are complementary to the development of the accident analysis tool MELCOR by Sandia National Laboratories as indicated in a DOE-NRC Memorandum of Understanding to jointly advance the state of MST modeling and simulation tools for advanced reactors. Four specific tasks supporting MST development are ongoing, including an uncertainty quantification and sensitivity analysis (UQSA) study on the MSTDB-TC thermochemical properties database for molten salt mixtures, the development of salt aerosol modeling correlations based on experimental data generated from salt spill experiments, (3) a UQSA study on tritium within the reactor systems, and (4) the calculation of the RN inventory in auxiliary (ex-core) systems transport such as the off-gas system. An overview is also provided of the types of multiphysics simulations that are being demonstrated within the NEAMS program, such as the coupling of neutronics tools with thermal hydraulics and chemistry modeling tools.
AB - As vendors of MSR technology enter the reactor licensing process, the determination of an appropriate and accurate source term will be central to the approval of the design by the U.S. NRC. The Multiphysics Applications technical area under the NEAMS program within DOE-NE is supporting development of mechanistic source term (MST) modeling and simulation tools to assist in the licensing process for advanced (non-LWR) reactors. Additional activities such as assessing and demonstrating multiphysics coupling of NEAMS-developed tools for MSRs are also ongoing. Multiphysics simulations can directly support licensing activities such as with transient analyses or indirectly by providing initial or boundary conditions to radionuclide (RN) transport analyses. Such efforts under NEAMS are complementary to the development of the accident analysis tool MELCOR by Sandia National Laboratories as indicated in a DOE-NRC Memorandum of Understanding to jointly advance the state of MST modeling and simulation tools for advanced reactors. Four specific tasks supporting MST development are ongoing, including an uncertainty quantification and sensitivity analysis (UQSA) study on the MSTDB-TC thermochemical properties database for molten salt mixtures, the development of salt aerosol modeling correlations based on experimental data generated from salt spill experiments, (3) a UQSA study on tritium within the reactor systems, and (4) the calculation of the RN inventory in auxiliary (ex-core) systems transport such as the off-gas system. An overview is also provided of the types of multiphysics simulations that are being demonstrated within the NEAMS program, such as the coupling of neutronics tools with thermal hydraulics and chemistry modeling tools.
KW - analysis
KW - mechanistic source term
KW - model development
KW - molten salt reactor
KW - safety
UR - https://www.scopus.com/pages/publications/85184347886
UR - https://www.mendeley.com/catalogue/f3658eee-cd4a-3202-b4dc-fb04a7f89b8d/
U2 - 10.13182/PSA23-41261
DO - 10.13182/PSA23-41261
M3 - Conference contribution
AN - SCOPUS:85184347886
T3 - Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023
SP - 188
EP - 197
BT - Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023
PB - American Nuclear Society
T2 - 18th International Probabilistic Safety Assessment and Analysis, PSA 2023
Y2 - 15 July 2023 through 20 July 2023
ER -