TY - GEN
T1 - Monte Carlo Variance Reduction in MOOSE Stochastic Tools Module
T2 - 2022 International Conference on Physics of Reactors, PHYSOR 2022
AU - Dhulipala, Somayajulu L.N.
AU - Prince, Zachary M.
AU - Slaughter, Andrew E.
AU - Munday, Lynn B.
AU - Jiang, Wen
AU - Spencer, Benjamin W.
AU - Hales, Jason D.
N1 - Funding Information:
This research is supported through the INL Laboratory Directed Research & Development (LDRD) Program under DOE Idaho Operations Office Contract DE-AC07-05ID14517. This research made use of the resources of the High Performance Computing Center at INL, which is supported by the Office of Nuclear Energy of the U.S. DOE and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Publisher Copyright:
© 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.
PY - 2022
Y1 - 2022
N2 - Modeling and simulation using the MOOSE open-source software has been considerably benefiting the design and safety assessment of nuclear reactor technologies. Given the myriad uncertainties in the modeling process, not only does safety needs to be characterized in a probabilistic fashion, but also, probabilistic failure analysis needs to be fast and capable of considering high-fidelity models. This paper presents some recent developments to the MOOSE's stochastic tools module for accelerating the probabilistic failure analysis with adaptive sampling-based variance reduction methods. These methods guarantee higher confidence in the probabilistic failure assessments compared to a Monte Carlo for the same or lesser number of model evaluations. In adaptive sampling, a new sample is proposed, the model is evaluated, a decision is made of whether or not to accept the proposed sample, and this decision-information is further used for proposing the next sample. We describe the software objects in MOOSE such as Sampler, MultiApp, and Reporter that support adaptive sampling-based variance reduction. We further describe the MOOSE input format for using adaptive sampling. Finally, we demonstrate these adaptive sampling capabilities in MOOSE using two applications: high temperature creep response of a nuclear alloy and probabilistic failure analysis of the advanced nuclear fuel TRISO.
AB - Modeling and simulation using the MOOSE open-source software has been considerably benefiting the design and safety assessment of nuclear reactor technologies. Given the myriad uncertainties in the modeling process, not only does safety needs to be characterized in a probabilistic fashion, but also, probabilistic failure analysis needs to be fast and capable of considering high-fidelity models. This paper presents some recent developments to the MOOSE's stochastic tools module for accelerating the probabilistic failure analysis with adaptive sampling-based variance reduction methods. These methods guarantee higher confidence in the probabilistic failure assessments compared to a Monte Carlo for the same or lesser number of model evaluations. In adaptive sampling, a new sample is proposed, the model is evaluated, a decision is made of whether or not to accept the proposed sample, and this decision-information is further used for proposing the next sample. We describe the software objects in MOOSE such as Sampler, MultiApp, and Reporter that support adaptive sampling-based variance reduction. We further describe the MOOSE input format for using adaptive sampling. Finally, we demonstrate these adaptive sampling capabilities in MOOSE using two applications: high temperature creep response of a nuclear alloy and probabilistic failure analysis of the advanced nuclear fuel TRISO.
KW - High Performance Computing
KW - Multiphysics Simulations
KW - Safety
KW - Software
KW - Uncertainty
UR - http://www.scopus.com/inward/record.url?scp=85173608736&partnerID=8YFLogxK
U2 - 10.13182/PHYSOR22-37608
DO - 10.13182/PHYSOR22-37608
M3 - Conference contribution
AN - SCOPUS:85173608736
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
SP - 2470
EP - 2479
BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
PB - American Nuclear Society
Y2 - 15 May 2022 through 20 May 2022
ER -