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 Annals of Nuclear Energy Pub Date : 2025-02-04 DOI:10.1016/j.anucene.2024.111128
Yeon Sang Jung , Yaqi Wang , Changho Lee
{"title":"Development of transport solver based on Hybrid Finite Element Method in Griffin","authors":"Yeon Sang Jung ,&nbsp;Yaqi Wang ,&nbsp;Changho Lee","doi":"10.1016/j.anucene.2024.111128","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111128"},"PeriodicalIF":1.9000,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924007916","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
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.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
求助全文
约1分钟内获得全文 去求助
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.
期刊最新文献
Development of transport solver based on Hybrid Finite Element Method in Griffin Collapsed energy group structure for analysis of prismatic high-temperature gas-cooled reactor with uranium fuel Editorial Board Optimized utilization of neural networks for online efficiency monitoring and fault detection in PWR nuclear power plant Analysis of the influence of bottom flow holes in control rod guide tubes on flow field and control rod displacement
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1