A coordinate control strategy for load following operation of sodium-cooled fast reactor system

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Qingfeng Jiang , Jinrong Jin , Areai Nuerlan , Yizhe Liu , Jiashuang Wan , Pengfei Wang
{"title":"A coordinate control strategy for load following operation of sodium-cooled fast reactor system","authors":"Qingfeng Jiang ,&nbsp;Jinrong Jin ,&nbsp;Areai Nuerlan ,&nbsp;Yizhe Liu ,&nbsp;Jiashuang Wan ,&nbsp;Pengfei Wang","doi":"10.1016/j.anucene.2025.111318","DOIUrl":null,"url":null,"abstract":"<div><div>The sodium-cooled fast reactor (SFR), as one of the most mature and promising Generation IV reactors, is a potential energy source. Load following operation has flexible regulation performance and is suitable for future development trend of grid peaking operation. The paper proposes a coordinate control strategy for the SFR under load following operation mode. Firstly, a simulation platform for the SFR was developed by adopting MATLAB/Simulink library technology. Secondly, a coordinate control strategy under load following operation mode was developed to coordinate primary sodium loop, secondary sodium loop, and feedwater-steam loop. Finally, typical operational transients such as step and ramp load change transients were simulated to validate the developed coordinate control strategy. The simulation results demonstrate that the reactor power has satisfactory flexibility and the system key parameters have good dynamic characteristics, which ensures expected performances of the SFR.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111318"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-11","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/S0306454925001355","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 sodium-cooled fast reactor (SFR), as one of the most mature and promising Generation IV reactors, is a potential energy source. Load following operation has flexible regulation performance and is suitable for future development trend of grid peaking operation. The paper proposes a coordinate control strategy for the SFR under load following operation mode. Firstly, a simulation platform for the SFR was developed by adopting MATLAB/Simulink library technology. Secondly, a coordinate control strategy under load following operation mode was developed to coordinate primary sodium loop, secondary sodium loop, and feedwater-steam loop. Finally, typical operational transients such as step and ramp load change transients were simulated to validate the developed coordinate control strategy. The simulation results demonstrate that the reactor power has satisfactory flexibility and the system key parameters have good dynamic characteristics, which ensures expected performances of the SFR.
求助全文
约1分钟内获得全文 求助全文
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.
×
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
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
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 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信