Research and application of the neutronics and thermal–hydraulic coupling based on the MORE framework

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-24 DOI:10.1016/j.anucene.2024.111067
Bo Wang , Zeyi Xie , Dayu Huang , Wenbo Zhao , Hongbo Zhang , Zhang Chen , Wei Zeng , Wenbin Wu
{"title":"Research and application of the neutronics and thermal–hydraulic coupling based on the MORE framework","authors":"Bo Wang ,&nbsp;Zeyi Xie ,&nbsp;Dayu Huang ,&nbsp;Wenbo Zhao ,&nbsp;Hongbo Zhang ,&nbsp;Zhang Chen ,&nbsp;Wei Zeng ,&nbsp;Wenbin Wu","doi":"10.1016/j.anucene.2024.111067","DOIUrl":null,"url":null,"abstract":"<div><div>The MORE framework, developed by the Nuclear Power Institute of China (NPIC), is a new coupling framework that integrates multiple powerful functionalities for handling input and output data from simulation codes. SHARK, also developed by NPIC, is an advanced whole core transport code that incorporates constructive solid geometry (CSG), the subgroup method, and the 2D/1D transport method. TH1D, another code developed by NPIC, is a single-channel thermal–hydraulic code that utilizes the single-channel model and one-dimensional heat conduction equation. Both SHARK and TH1D are encapsulated within the MORE framework. The coupling system generates interfaces for coupling which are controlled by a supervisor. Finally, validation of the coupling system is conducted using the VERA benchmark, with numerical results demonstrating that the MORE framework is suitable for accurate whole core coupling calculations.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111067"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-24","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/S0306454924007308","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

The MORE framework, developed by the Nuclear Power Institute of China (NPIC), is a new coupling framework that integrates multiple powerful functionalities for handling input and output data from simulation codes. SHARK, also developed by NPIC, is an advanced whole core transport code that incorporates constructive solid geometry (CSG), the subgroup method, and the 2D/1D transport method. TH1D, another code developed by NPIC, is a single-channel thermal–hydraulic code that utilizes the single-channel model and one-dimensional heat conduction equation. Both SHARK and TH1D are encapsulated within the MORE framework. The coupling system generates interfaces for coupling which are controlled by a supervisor. Finally, validation of the coupling system is conducted using the VERA benchmark, with numerical results demonstrating that the MORE framework is suitable for accurate whole core coupling calculations.
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
基于 MORE 框架的中子和热液耦合研究与应用
由中国核动力研究院(NPIC)开发的 MORE 框架是一个新的耦合框架,集成了多种强大功能,用于处理来自仿真代码的输入和输出数据。同样由 NPIC 开发的 SHARK 是一种先进的全核输运代码,它集成了构造实体几何(CSG)、子群法和 2D/1D 输运法。TH1D 是 NPIC 开发的另一种代码,是一种单通道热流体力学代码,采用单通道模型和一维热传导方程。SHARK 和 TH1D 都封装在 MORE 框架内。耦合系统生成的耦合界面由监控器控制。最后,使用 VERA 基准对耦合系统进行了验证,数值结果表明 MORE 框架适用于精确的全核心耦合计算。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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
Investigation on heat split in a vertical 3 × 3 dual-cooled annular rod bundle Impact of temperature- and phase-dependent zirconium hydride phonons on criticality Evaluation of uranium-233 neutron capture cross section in keV region Application of data partitioned Kriging algorithm with GPU acceleration in real-time and refined reconstruction of three-dimensional radiation fields Boiling critical characteristics in narrow rectangular channel under local heat flux concentration conditions
×
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