{"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 , Pardeep Kumar , Vinay Panwar , Mahesh Kumar Gupta , Dhowmya Bhatt , Dinesh Kumar , Vipin Kumar Sharma , Vikas Goyat , Gyander Ghangas , Arun Uniyal , 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 , Pardeep Kumar , Vinay Panwar , Mahesh Kumar Gupta , Dhowmya Bhatt , Dinesh Kumar , Vipin Kumar Sharma , Vikas Goyat , Gyander Ghangas , Arun Uniyal , 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}
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.
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