Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors

Wang, Yaqi; Prince, Zachary M.; Park, Hansol; Calvin, Olin W.; Choi, Namjae; Jung, Yeon Sang; Schunert, Sebastian; Kumar, Shikhar; Hanophy, Joshua Thomas; Labouré, Vincent M.; Lee, Changho; Ortensi, Javier; Harbour, Logan H.; Harter, Jackson R.

doi:10.1016/j.anucene.2024.110917

Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors

Journal Article · Thu Sep 26 00:00:00 EDT 2024 · Annals of Nuclear Energy

DOI:https://doi.org/10.1016/j.anucene.2024.110917· OSTI ID:2496604

^[1]; ^[1]; Park, Hansol ^[2]; Calvin, Olin W. ^[1]; ^[1]; ^[2]; Schunert, Sebastian ^[1]; ^[2]; Hanophy, Joshua Thomas ^[1]; ^[1]; Lee, Changho ^[2]; ^[1]; Harbour, Logan H. ^[1]; Harter, Jackson R. ^[1]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Argonne National Laboratory (ANL), Argonne, IL (United States)

Griffin is a Multiphysics Object-Oriented Simulation Environment (MOOSE) based reactor physics application for multiphysics simulations of advanced reactor designs jointly developed by Idaho National Laboratory and Argonne National Laboratory. This paper summarizes the motivation, significance, architecture, design, and features of Griffin. Griffin offers flexible and extensible features to address the challenges associated with advanced reactor designs. These features range from fundamental particle transport to specific reactor physics tasks. The features cover a wide range including on-the-fly and traditional two-step cross-section generation methods, steady-state and transient transport solvers suitable for both heterogeneous and homogeneous models, high-fidelity depletion where thousands of isotopes can be tracked and low-fidelity depletion characterized by burnup, etc. The most fundamental aspect that sets Griffin apart from other reactor analysis codes is that it is developed based on the MOOSE framework. A modular development approach is strongly enforced, with multiphysics being an essential element considered since the beginning of Griffin’s development. Griffin links various MOOSE physics modules and couples to other MOOSE-based applications and non-MOOSE-based applications for multiphyiscs simulations. Griffin includes three modules: ISOXML for preparing and managing multigroup cross sections, radiation transport for solving the neutron transport equation, and reactor analysis for user-oriented reactor physics analysis functionalities. Griffin uses various finite element methods for spatial discretization, multigroup approximation for energy discretization and discrete ordinates method, spherical harmonics expansion method, and diffusion approximation for streaming direction discretization to solve the neutron transport equation. Griffin’s flexibility is evidenced through Griffin’s various applications to fast reactor, high-temperature reactor, pebble bed reactor, molten salt reactor, and microreactor designs. Griffin development follows the software quality assurance procedure for MOOSE-based applications and with software requirements consistent with the ASME NQA-1 standard. Griffin has been adopted into the reactor analysis system for the U.S. NRC and is in use at U.S. companies, universities and national laboratories.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS)

Grant/Contract Number:: AC02-06CH11357; AC07-05ID14517

OSTI ID:: 2496604

Report Number(s):: INL/JOU--24-77257-Rev000

Journal Information:: Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 211; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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