Neutron transport methods for multiphysics heterogeneous reactor core simulation in Griffin
ANNALS OF NUCLEAR ENERGY(2024)
摘要
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 (DFEMSN) 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.
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关键词
Griffin,MOOSE,Radiation transport,Multiphysics,Reactor dynamics
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