Transient characteristics and adjustment ranges of key parameters in supercritical CO2 direct-cooled microreactor system with simplified control strategies

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Hao Ding , Daogang Lu , Danting Sui , Xiao Luo , Kunjun Han
{"title":"Transient characteristics and adjustment ranges of key parameters in supercritical CO2 direct-cooled microreactor system with simplified control strategies","authors":"Hao Ding ,&nbsp;Daogang Lu ,&nbsp;Danting Sui ,&nbsp;Xiao Luo ,&nbsp;Kunjun Han","doi":"10.1016/j.pnucene.2024.105533","DOIUrl":null,"url":null,"abstract":"<div><div>The combination of supercritical carbon dioxide (SCO<sub>2</sub>) Brayton cycle and microreactor is a promising technology. SCO<sub>2</sub> direct-cooled microreactor system takes advantages of compact system design and high efficiency, which can be applied in various scenes. Although the design SCO<sub>2</sub> Brayton cycle system is already compact, the control rods in reactor core still results in relatively large design size of the reactor. Considering relatively high negative temperature coefficient of reactor core and fast response characteristics of SCO<sub>2</sub> Brayton cycle, simplified control strategies are proposed in this paper to reduce the number of control rods in the reactor, thus decreasing the diameter of the reactor. Aimed towards the design of SCO<sub>2</sub> cooled floating nuclear power plant (SCFNP),the simplified control strategies are proposed. Then, adjustment ranges of system key parameters with different control strategies are simulated, and comparisons between them in various aspects are performed. According to the results, inventory control, shaft speed control and bypass valve control are proved to be able to adjust reactor power effectively instead of control rods. When applied shaft speed control and bypass valve control, system maximum temperature obviously exceeds the design temperature, which is about 12% and 20% respectively. What's more, inventory control and shaft speed control take about six times longer than bypass control to stabilized the system parameters. Besides, advantages and disadvantages are concluded of the three different control strategies, which can be used as reference of the control system design for SCO<sub>2</sub> direct-cooled microreactor system.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"179 ","pages":"Article 105533"},"PeriodicalIF":3.3000,"publicationDate":"2024-11-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197024004839","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 combination of supercritical carbon dioxide (SCO2) Brayton cycle and microreactor is a promising technology. SCO2 direct-cooled microreactor system takes advantages of compact system design and high efficiency, which can be applied in various scenes. Although the design SCO2 Brayton cycle system is already compact, the control rods in reactor core still results in relatively large design size of the reactor. Considering relatively high negative temperature coefficient of reactor core and fast response characteristics of SCO2 Brayton cycle, simplified control strategies are proposed in this paper to reduce the number of control rods in the reactor, thus decreasing the diameter of the reactor. Aimed towards the design of SCO2 cooled floating nuclear power plant (SCFNP),the simplified control strategies are proposed. Then, adjustment ranges of system key parameters with different control strategies are simulated, and comparisons between them in various aspects are performed. According to the results, inventory control, shaft speed control and bypass valve control are proved to be able to adjust reactor power effectively instead of control rods. When applied shaft speed control and bypass valve control, system maximum temperature obviously exceeds the design temperature, which is about 12% and 20% respectively. What's more, inventory control and shaft speed control take about six times longer than bypass control to stabilized the system parameters. Besides, advantages and disadvantages are concluded of the three different control strategies, which can be used as reference of the control system design for SCO2 direct-cooled microreactor system.
采用简化控制策略的超临界二氧化碳直接冷却微反应器系统的瞬态特性和关键参数调整范围
超临界二氧化碳(SCO2)布雷顿循环与微反应器的结合是一项前景广阔的技术。SCO2 直接冷却微反应器系统具有系统设计紧凑、效率高的优点,可应用于各种场合。虽然 SCO2 布莱顿循环系统的设计已经很紧凑,但堆芯中的控制棒仍然导致反应堆的设计尺寸相对较大。考虑到反应堆堆芯负温度系数相对较高以及 SCO2 布莱顿循环的快速响应特性,本文提出了简化的控制策略,以减少反应堆中控制棒的数量,从而减小反应堆的直径。针对 SCO2 冷却浮动核电站(SCFNP)的设计,提出了简化控制策略。然后,模拟了不同控制策略下系统关键参数的调整范围,并对它们进行了多方面的比较。结果表明,库存控制、轴转速控制和旁路阀控制可代替控制棒有效调节反应堆功率。当采用轴速控制和旁路阀控制时,系统最高温度明显超过设计温度,分别约为 12% 和 20%。此外,库存控制和轴转速控制稳定系统参数的时间约为旁路控制的 6 倍。此外,还总结了三种不同控制策略的优缺点,可作为 SCO2 直接冷却微反应器系统控制系统设计的参考。
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 求助全文
来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
×
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