超临界自然循环回路在不同加热功率分布下的流动特性、稳定性和安全极限计算分析的综合研究

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Santosh Kumar Rai , Pardeep Kumar , Vinay Panwar , Mahesh Kumar Gupta , Dhowmya Bhatt , Dinesh Kumar , Vipin Kumar Sharma , Vikas Goyat , Gyander Ghangas , Arun Uniyal , Mahiti Gupta
{"title":"超临界自然循环回路在不同加热功率分布下的流动特性、稳定性和安全极限计算分析的综合研究","authors":"Santosh Kumar Rai ,&nbsp;Pardeep Kumar ,&nbsp;Vinay Panwar ,&nbsp;Mahesh Kumar Gupta ,&nbsp;Dhowmya Bhatt ,&nbsp;Dinesh Kumar ,&nbsp;Vipin Kumar Sharma ,&nbsp;Vikas Goyat ,&nbsp;Gyander Ghangas ,&nbsp;Arun Uniyal ,&nbsp;Mahiti Gupta","doi":"10.1016/j.net.2025.103858","DOIUrl":null,"url":null,"abstract":"<div><div>The Generation IV International Forum (GIF) is a global organization focused on the research and advancement of next-generation nuclear reactor technologies. GIF-IV reactors particularly seek to improve the safety, efficiency, and sustainability of nuclear power, with an emphasis on developing cleaner and more renewable energy sources. Supercritical water reactors (SCWRs) and supercritical water natural circulations (SCWNCL) are one of the most advanced technologies developed by the GIF-IV for cooling the core of nuclear reactors. In this study,a thermal-hydraulic (TH) model has been developed based on the nonlinearly coupled equations of mass, momentum, and energy conservation, with an equation of state which depends on two independent thermodynamic characteristics pressure and enthalpy. The present model is first validated against literature result such as experimental and numerical which showed a good agreement, followed by a grid independence test (GIT) conducted for both steady state and transient conditions to ensure accurate predictions of the SCWNCL. Further, the simulations are carried out to examine loop behavior and ascertain thermal-hydraulic transient instability, along with determining the stable and safe limits of the SCWNCL. Additionally, numerous simulations have been conducted to ascertain the presence of static instability that occurs at extremely low enthalpy. Furthermore, dynamic instability has been seen in the loop at both low and high enthalpy using three different heating profiles like uniform, point and half sinusoidal profiles, resulting in the construction of the marginal stability map. Subsequently, comprehensive simulations have been conducted to forecast heat transfer deterioration within the loop from a material point of view, aiming to ascertain the stable and safe limits of the SCWNCL. Comparative studies have been conducted with and without the consideration of heating structure stability maps, demonstrating that the addition of the structure provides a higher stability zone compared to its absence.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103858"},"PeriodicalIF":2.6000,"publicationDate":"2025-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"A comprehensive investigation of computational analysis on flow characteristics, stability and safe limits of a supercritical natural circulation loop for different heating power profiles\",\"authors\":\"Santosh Kumar Rai ,&nbsp;Pardeep Kumar ,&nbsp;Vinay Panwar ,&nbsp;Mahesh Kumar Gupta ,&nbsp;Dhowmya Bhatt ,&nbsp;Dinesh Kumar ,&nbsp;Vipin Kumar Sharma ,&nbsp;Vikas Goyat ,&nbsp;Gyander Ghangas ,&nbsp;Arun Uniyal ,&nbsp;Mahiti Gupta\",\"doi\":\"10.1016/j.net.2025.103858\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The Generation IV International Forum (GIF) is a global organization focused on the research and advancement of next-generation nuclear reactor technologies. GIF-IV reactors particularly seek to improve the safety, efficiency, and sustainability of nuclear power, with an emphasis on developing cleaner and more renewable energy sources. Supercritical water reactors (SCWRs) and supercritical water natural circulations (SCWNCL) are one of the most advanced technologies developed by the GIF-IV for cooling the core of nuclear reactors. In this study,a thermal-hydraulic (TH) model has been developed based on the nonlinearly coupled equations of mass, momentum, and energy conservation, with an equation of state which depends on two independent thermodynamic characteristics pressure and enthalpy. The present model is first validated against literature result such as experimental and numerical which showed a good agreement, followed by a grid independence test (GIT) conducted for both steady state and transient conditions to ensure accurate predictions of the SCWNCL. Further, the simulations are carried out to examine loop behavior and ascertain thermal-hydraulic transient instability, along with determining the stable and safe limits of the SCWNCL. Additionally, numerous simulations have been conducted to ascertain the presence of static instability that occurs at extremely low enthalpy. Furthermore, dynamic instability has been seen in the loop at both low and high enthalpy using three different heating profiles like uniform, point and half sinusoidal profiles, resulting in the construction of the marginal stability map. Subsequently, comprehensive simulations have been conducted to forecast heat transfer deterioration within the loop from a material point of view, aiming to ascertain the stable and safe limits of the SCWNCL. Comparative studies have been conducted with and without the consideration of heating structure stability maps, demonstrating that the addition of the structure provides a higher stability zone compared to its absence.</div></div>\",\"PeriodicalId\":19272,\"journal\":{\"name\":\"Nuclear Engineering and Technology\",\"volume\":\"57 12\",\"pages\":\"Article 103858\"},\"PeriodicalIF\":2.6000,\"publicationDate\":\"2025-08-21\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Technology\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S1738573325004267\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573325004267","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

摘要

第四代国际论坛(GIF)是一个致力于研究和推进下一代核反应堆技术的全球性组织。GIF-IV型反应堆特别寻求提高核能的安全性、效率和可持续性,重点是开发更清洁、更可再生的能源。超临界水反应堆(SCWRs)和超临界水自然循环(SCWNCL)是GIF-IV开发的用于核反应堆堆芯冷却的最先进技术之一。本文建立了一个基于质量、动量和能量守恒非线性耦合方程的热工水力模型,其状态方程依赖于压强和焓两个独立的热力学特性。本文首先对文献结果进行了验证,如实验和数值结果显示出良好的一致性,然后对稳态和瞬态条件进行了网格独立性测试(GIT),以确保对SCWNCL的准确预测。此外,还进行了模拟,以检查回路行为,确定热液瞬态不稳定性,以及确定SCWNCL的稳定和安全极限。此外,已经进行了大量的模拟,以确定在极低焓下发生的静态不稳定性的存在。此外,在低焓和高焓下,使用均匀、点和半正弦三种不同的加热剖面,在环路中都可以看到动态不稳定性,从而构建了边际稳定性图。随后,进行了全面的模拟,从材料的角度预测循环内的传热恶化,旨在确定SCWNCL的稳定和安全极限。在考虑加热结构稳定性图和不考虑加热结构稳定性图的情况下进行了比较研究,结果表明,与没有加热结构相比,增加加热结构提供了更高的稳定区。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A comprehensive investigation of computational analysis on flow characteristics, stability and safe limits of a supercritical natural circulation loop for different heating power profiles
The Generation IV International Forum (GIF) is a global organization focused on the research and advancement of next-generation nuclear reactor technologies. GIF-IV reactors particularly seek to improve the safety, efficiency, and sustainability of nuclear power, with an emphasis on developing cleaner and more renewable energy sources. Supercritical water reactors (SCWRs) and supercritical water natural circulations (SCWNCL) are one of the most advanced technologies developed by the GIF-IV for cooling the core of nuclear reactors. In this study,a thermal-hydraulic (TH) model has been developed based on the nonlinearly coupled equations of mass, momentum, and energy conservation, with an equation of state which depends on two independent thermodynamic characteristics pressure and enthalpy. The present model is first validated against literature result such as experimental and numerical which showed a good agreement, followed by a grid independence test (GIT) conducted for both steady state and transient conditions to ensure accurate predictions of the SCWNCL. Further, the simulations are carried out to examine loop behavior and ascertain thermal-hydraulic transient instability, along with determining the stable and safe limits of the SCWNCL. Additionally, numerous simulations have been conducted to ascertain the presence of static instability that occurs at extremely low enthalpy. Furthermore, dynamic instability has been seen in the loop at both low and high enthalpy using three different heating profiles like uniform, point and half sinusoidal profiles, resulting in the construction of the marginal stability map. Subsequently, comprehensive simulations have been conducted to forecast heat transfer deterioration within the loop from a material point of view, aiming to ascertain the stable and safe limits of the SCWNCL. Comparative studies have been conducted with and without the consideration of heating structure stability maps, demonstrating that the addition of the structure provides a higher stability zone compared to its absence.
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
×
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:604180095
Book学术官方微信