Neutron transport methods for multiphysics heterogeneous reactor core simulation in Griffin

Prince, Zachary M.; Hanophy, Joshua Thomas; Labouré, Vincent M.; Wang, Yaqi; Harbour, Logan H.; Choi, Namjae

doi:10.1016/j.anucene.2024.110365

Neutron transport methods for multiphysics heterogeneous reactor core simulation in Griffin

Journal Article · Wed Jan 31 00:00:00 EST 2024 · Annals of Nuclear Energy

DOI:https://doi.org/10.1016/j.anucene.2024.110365· OSTI ID:2345902

^[1]; Hanophy, Joshua Thomas ^[1]; ^[1]; ^[1]; Harbour, Logan H. ^[1]; ^[1]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Griffin is a reactor physics application based on the Multiphysics Object-Oriented Simulation Environment (MOOSE). This work discloses the methods, algorithms, and implementation for simulating heterogeneous reactor dynamics models. Griffin utilizes a discontinuous finite-element method with discrete ordinates (DFEM-S ) to discretize the field variable of the multigroup neutron transport equation. Multiphysics feedback is handled using two-step tabulated cross-section methodology. Feedback quantities are evaluated using the MOOSE-MultiApp system to couple various engineering phenomena, such as heat conduction and thermal fluids. The multiphysics DFEM-S system is solved using fixed-point iteration with a fully asynchronous parallel sweeper, unstructured coarse-mesh finite difference acceleration, and a multi-timescale improved quasi-static method scheme. The implementation is applied to a multiphysics microreactor model, with two transients: one initiated by a single heat-pipe failure and another by control drum rotation. Importantly, these examples demonstrate the ability of Griffin to tractably solve the neutron transport equation considering seven independent variables and feedback.

View Accepted Manuscript (DOE)

Research Organization:: Argonne National Laboratory (ANL), Argonne, IL (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2345902

Report Number(s):: INL/JOU--23-74676-Revision-0

Journal Information:: Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 200; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Neutron transport methods for multiphysics heterogeneous reactor core simulation in Griffin

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