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Neutron transport methods for multiphysics heterogeneous reactor core simulation in Griffin

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18 Scopus citations

Abstract

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-SN) 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-SN 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. These examples demonstrate the ability of Griffin to tractably solve the neutron transport equation considering seven independent variables and feedback.

Original languageEnglish
Article number110365
JournalAnnals of Nuclear Energy
Volume200
Early online dateJan 31 2024
DOIs
StatePublished - Jun 1 2024

Keywords

  • Griffin
  • MOOSE
  • Multiphysics
  • Radiation transport
  • Reactor dynamics

INL Publication Number

  • INL/JOU-23-74676
  • 162613

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