Development of transport solver based on Hybrid Finite Element Method in Griffin

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yeon Sang Jung , Yaqi Wang , Changho Lee
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引用次数: 0

Abstract

A new lower-order transport solver option based on the Hybrid Finite Element Methods (HFEM) was implemented in Griffin, the MOOSE-based reactor physics code, to support core design calculations for advanced reactor applications. The HFEM formulation with spherical harmonics expansion (PN), also known as the variational nodal method, effectively solves spatially homogenized problems with strong transport effects. The residual evaluations of the HFEM weak form were derived and implemented in Griffin, with PN and diffusion options available in the new HFEM-based transport solver. The red-black iteration and the Coarse Mesh Finite Difference (CMFD) acceleration schemes are incorporated within the Richardson iteration framework to effectively solve the HFEM formulation. Performance tests conducted using the simplified ABTR benchmark problems demonstrated that the HFEM-based transport solver is a preferable option for solving problems with spatial homogenization and significant streaming effects, providing superior accuracy with appropriate p-refinement.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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