Study on the design of unattended SCRS full-condition adaptive bypass flow systems

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-12 DOI:10.1016/j.nucengdes.2024.113768
Bowen Zhang, Yizhuo Li, Haixu Zhu, Yunze Xue, Yuandong Zhang
{"title":"Study on the design of unattended SCRS full-condition adaptive bypass flow systems","authors":"Bowen Zhang,&nbsp;Yizhuo Li,&nbsp;Haixu Zhu,&nbsp;Yunze Xue,&nbsp;Yuandong Zhang","doi":"10.1016/j.nucengdes.2024.113768","DOIUrl":null,"url":null,"abstract":"<div><div>The Supercritical CO<sub>2</sub> Reactor System (SCRS), a member of the fourth-generation reactor family, offers promising prospects for practical application. The use of S-CO<sub>2</sub> as a working fluid leads to a more compact reactor design and higher energy conversion efficiency, positioning it as a strong contender for next-generation unattended intelligent reactor systems. However, the thermophysical properties of S-CO<sub>2</sub> exhibit dramatic changes near the critical point, placing higher demands on the control system to ensure SCRS stability. To address the challenge that PID control theory struggles to meet the complex control demands of supercritical reactors, this paper proposes an intelligent control-based approach. It utilizes neural networks to adaptively adjust the outputs of fuzzy control and PID control in the bypass flow control system. The optimized controller outperforms the original PI controller during normal operational transients and exhibits robust performance under accident conditions. The work presented in this paper provides valuable insights for the design and optimization of control systems in supercritical reactors for practical engineering applications.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"432 ","pages":"Article 113768"},"PeriodicalIF":2.1000,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549324008689","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2024/12/12 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

The Supercritical CO2 Reactor System (SCRS), a member of the fourth-generation reactor family, offers promising prospects for practical application. The use of S-CO2 as a working fluid leads to a more compact reactor design and higher energy conversion efficiency, positioning it as a strong contender for next-generation unattended intelligent reactor systems. However, the thermophysical properties of S-CO2 exhibit dramatic changes near the critical point, placing higher demands on the control system to ensure SCRS stability. To address the challenge that PID control theory struggles to meet the complex control demands of supercritical reactors, this paper proposes an intelligent control-based approach. It utilizes neural networks to adaptively adjust the outputs of fuzzy control and PID control in the bypass flow control system. The optimized controller outperforms the original PI controller during normal operational transients and exhibits robust performance under accident conditions. The work presented in this paper provides valuable insights for the design and optimization of control systems in supercritical reactors for practical engineering applications.

Abstract Image

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
无人值守SCRS全工况自适应旁通系统设计研究
超临界CO2反应器系统(SCRS)是第四代反应器家族中的一员,具有广阔的应用前景。使用S-CO2作为工作流体可以实现更紧凑的反应器设计和更高的能量转换效率,使其成为下一代无人值守智能反应器系统的有力竞争者。但S-CO2的热物理性质在临界点附近发生剧烈变化,对控制系统保证SCRS的稳定性提出了更高的要求。针对PID控制理论难以满足超临界反应器复杂控制需求的挑战,本文提出了一种基于智能控制的方法。利用神经网络对旁路流量控制系统中的模糊控制和PID控制的输出进行自适应调节。优化后的控制器在正常运行瞬态下优于原始PI控制器,在事故条件下表现出鲁棒性。本文的工作为超临界反应堆控制系统的设计和优化提供了有价值的见解。
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
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
期刊最新文献
Numerical study on the influence of internal heat generation on mixed convection heat transfer in a horizontal laminar pipe flow with wall cooling CRAFTY – A new separate-effect-test facility at LUT University for two-phase critical flow studies in transient nature Conclusions of OECD/NEA project on ‘LTO beyond 60 years’ Analysis of risk-important LOCA sequences in NuScale considering accident tolerant fuels High-fidelity turbulence simulation for the OECD–NEA cold-leg mixing benchmark
×
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:604180095
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