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

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-05-01 Epub Date: 2025-02-04 DOI:10.1016/j.anucene.2024.111128
Yeon Sang Jung , Yaqi Wang , Changho Lee
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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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Griffin中基于混合有限元法的输运求解器的开发
在基于moose的反应堆物理代码Griffin中实现了一种新的基于混合有限元方法(HFEM)的低阶传输求解器选项,以支持先进反应堆应用的堆芯设计计算。采用球面谐波展开(PN)的HFEM公式,也称为变分节点法,可以有效地解决具有强输运效应的空间均匀化问题。在Griffin中推导并实现了HFEM弱形式的剩余评估,并在新的基于HFEM的传输求解器中提供了PN和扩散选项。在Richardson迭代框架中加入红黑迭代和粗网格有限差分(CMFD)加速格式,有效求解HFEM公式。使用简化的ABTR基准问题进行的性能测试表明,基于hfm的传输求解器是解决具有空间均匀化和显著流效应的问题的较好选择,通过适当的p-细化提供了优越的精度。
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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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