TY - JOUR
T1 - A workflow leveraging MOOSE transient multiphysics simulations to evaluate the impact of thermophysical property uncertainties on molten-salt reactors
AU - Abou-Jaoude, A.
AU - Harper, S.
AU - Giudicelli, G.
AU - Balestra, P.
AU - Schunert, S.
AU - Martin, N.
AU - Lindsay, A.
AU - Tano, M.
AU - Freile, R.
N1 - Funding Information:
This research work was prepared for DOE through Idaho National Laboratory (INL)’s LDRD Program under project 20A1049-015FP, entitled “Using Coupled Multiphysics Tools to Investigate Design-limiting Criteria for Molten Salt Reactors,” under the DOE Idaho Operations Office.
Funding Information:
This manuscript was authored by Battelle Energy Alliance, LLC under Contract No. DE-AC07-05ID14517 with the U.S. Department of Energy (DOE). The U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. Government purposes. This research work was prepared for DOE through Idaho National Laboratory (INL)?s LDRD Program under project 20A1049-015FP, entitled ?Using Coupled Multiphysics Tools to Investigate Design-limiting Criteria for Molten Salt Reactors,? under the DOE Idaho Operations Office. This research also made use of the resources of the High Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Funding Information:
This research also made use of the resources of the High Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Publisher Copyright:
© 2021 The Author(s)
PY - 2021/12/1
Y1 - 2021/12/1
N2 - A new approach is proposed to evaluate the safety of molten-salt reactors (MSRs), using advanced modeling and simulation (M&S) tools. This approach augments the Monitoring and Inspection (M&I) concept for fuel qualification by enabling computation of the change in critical safety parameters as a result of altered thermo-physical fuel properties. This work uses newly developed capabilities in the MOOSE framework to perform the requisite M&S. The neutronics code Griffin, using its neutron diffusion solver, is coupled to the coarse-mesh, multi-dimensional, thermal-hydraulic capabilities of Pronghorn. The resulting new capability enables efficient transient multiphysics simulations of open-pool-type MSR concepts, including delayed neutron precursor advection and beyond design basis events. The proposed approach uses the coupled Griffin/Pronghorn models to perform a sensitivity analysis by perturbing the salt thermophysical properties and evaluating the resulting impact on key safety parameters during an unprotected loss-of-forced-flow accident. In light of the challenges associated with predicting the effect of reactor operations and burnup on bulk salt properties, this work demonstrates how Griffin/Pronghorn multiphysics simulations may be used to evaluate whether changes in salt properties could potentially lead to unsafe reactor configurations.
AB - A new approach is proposed to evaluate the safety of molten-salt reactors (MSRs), using advanced modeling and simulation (M&S) tools. This approach augments the Monitoring and Inspection (M&I) concept for fuel qualification by enabling computation of the change in critical safety parameters as a result of altered thermo-physical fuel properties. This work uses newly developed capabilities in the MOOSE framework to perform the requisite M&S. The neutronics code Griffin, using its neutron diffusion solver, is coupled to the coarse-mesh, multi-dimensional, thermal-hydraulic capabilities of Pronghorn. The resulting new capability enables efficient transient multiphysics simulations of open-pool-type MSR concepts, including delayed neutron precursor advection and beyond design basis events. The proposed approach uses the coupled Griffin/Pronghorn models to perform a sensitivity analysis by perturbing the salt thermophysical properties and evaluating the resulting impact on key safety parameters during an unprotected loss-of-forced-flow accident. In light of the challenges associated with predicting the effect of reactor operations and burnup on bulk salt properties, this work demonstrates how Griffin/Pronghorn multiphysics simulations may be used to evaluate whether changes in salt properties could potentially lead to unsafe reactor configurations.
KW - Molten salt reactors
KW - Multiphysics
KW - Transients
KW - Griffin
KW - Pronghorn
KW - MOOSE
KW - Thermophysical properties
UR - https://www.scopus.com/pages/publications/85111286603
UR - https://www.mendeley.com/catalogue/d108cde8-ba63-390b-82e1-501b43bf97a2/
U2 - 10.1016/j.anucene.2021.108546
DO - 10.1016/j.anucene.2021.108546
M3 - Article
SN - 0306-4549
VL - 163
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
ER -