TY - GEN
T1 - Quantifying Uncertainties
T2 - 2024 International Conference on Physics of Reactors, PHYSOR 2024
AU - Rotilio, Davide
AU - Tano, Mauricio
AU - Abou-Jaoude, Abdalla
AU - Walker, Samuel
AU - Fratoni, Massimiliano
AU - Gatto, Renato
N1 - Publisher Copyright:
© 2024 AMERICAN NUCLEAR SOCIETY. All rights reserved.
PY - 2024
Y1 - 2024
N2 - This study introduces an innovative approach aimed at evaluating the safety of molten-salt reactors (MSRs) by harnessing advanced modeling and simulation (M&S) tools.This approach takes advantage of the recently enhanced capabilities within the MOOSE framework, enabling the execution of comprehensive M&S tasks tailored specifically to MSRs.Our methodology involves the coupling of two critical components: the Griffin neutronic code, featuring its neutron diffusion solver, and the Navier-Stokes (NV) module's thermal-hydraulic capabilities.This integration empowers efficient steady-state and transient multiphysics simulations, particularly suitable for MSR concepts encompassing the advection of delayed neutrons.The core of our proposed approach revolves around conducting a sensitivity involving perturbations in the thermophysical properties of the molten salt.By doing so, we can assess how variations in these properties impact key safely parameters like the maximum fluid and reflector temperature.The significance of this work lies in its ability to demonstrate how Griffin/NV module multiphysics simulations can serve as a valuable tool for assessing the potential risks associated with changes in salt properties.Understanding these risks is essential for ensuring the safe operation of MSRs considering also deviations from expected thermophysical properties, ultimately contributing to the advancement of this promising nuclear technology.highlights the main accomplishments.
AB - This study introduces an innovative approach aimed at evaluating the safety of molten-salt reactors (MSRs) by harnessing advanced modeling and simulation (M&S) tools.This approach takes advantage of the recently enhanced capabilities within the MOOSE framework, enabling the execution of comprehensive M&S tasks tailored specifically to MSRs.Our methodology involves the coupling of two critical components: the Griffin neutronic code, featuring its neutron diffusion solver, and the Navier-Stokes (NV) module's thermal-hydraulic capabilities.This integration empowers efficient steady-state and transient multiphysics simulations, particularly suitable for MSR concepts encompassing the advection of delayed neutrons.The core of our proposed approach revolves around conducting a sensitivity involving perturbations in the thermophysical properties of the molten salt.By doing so, we can assess how variations in these properties impact key safely parameters like the maximum fluid and reflector temperature.The significance of this work lies in its ability to demonstrate how Griffin/NV module multiphysics simulations can serve as a valuable tool for assessing the potential risks associated with changes in salt properties.Understanding these risks is essential for ensuring the safe operation of MSRs considering also deviations from expected thermophysical properties, ultimately contributing to the advancement of this promising nuclear technology.highlights the main accomplishments.
KW - MSRs Multiphysics Griffin Navier-Stokes MOOSE
UR - https://www.scopus.com/pages/publications/85202877574
U2 - 10.13182/PHYSOR24-43547
DO - 10.13182/PHYSOR24-43547
M3 - Conference contribution
AN - SCOPUS:85202877574
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024
SP - 1080
EP - 1089
BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024
PB - American Nuclear Society
Y2 - 21 April 2024 through 24 April 2024
ER -