Chansoo Lee , Kyuseok Shim , Hyuntaek Rho , Jooil Yoon , Heejeong Jeong , Youho Lee
{"title":"可溶无硼小堆全堆芯燃料分析:颗粒包层相互作用问题及通过装载模式设计提高燃料安全性","authors":"Chansoo Lee , Kyuseok Shim , Hyuntaek Rho , Jooil Yoon , Heejeong Jeong , Youho Lee","doi":"10.1016/j.net.2025.103709","DOIUrl":null,"url":null,"abstract":"<div><div>The full-core fuel behavior of the Soluble Boron-Free (SBF) Small Modular Reactor (SMR) was analyzed and compared with conventional pressurized water reactors (PWRs) and Soluble Boron-Using (SBU) SMRs to evaluate unique pellet-cladding interaction (PCI) risks. Unlike PWRs and SBU SMRs, SBF SMRs rely on control rods for reactivity control, leading to localized power increases during late-cycle withdrawal. This significantly elevates cladding hoop stress, particularly in fuel rods near control rods, increasing PCI risks even at moderate burnups. The maximum local cladding hoop stress due to PCI in SBF SMRs exceeds that of conventional PWRs, posing new fuel safety and qualification challenges despite being SMR fuel characteristics, such as lower power density, and extended relative fuel plenum length. Comparisons with boiling water reactors (BWRs) highlight the heightened PCI risk in SBF SMRs due to differences in core design and control strategies. A fuel loading strategy that positions high-burnup rods away from lead control rod banks effectively reduces peak cladding stress. However, PCI remains a concern, particularly for long-cycle cores with LEU+ fuel. These findings emphasize the need to integrate fuel performance considerations early in SBF SMR development to ensure safety, regulatory compliance, and adaptability for future LEU+ fuels.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103709"},"PeriodicalIF":2.6000,"publicationDate":"2025-05-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Full-core fuel analysis of a soluble boron-free SMR: Pellet-cladding interaction issue and enhancing fuel safety through loading pattern design\",\"authors\":\"Chansoo Lee , Kyuseok Shim , Hyuntaek Rho , Jooil Yoon , Heejeong Jeong , Youho Lee\",\"doi\":\"10.1016/j.net.2025.103709\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The full-core fuel behavior of the Soluble Boron-Free (SBF) Small Modular Reactor (SMR) was analyzed and compared with conventional pressurized water reactors (PWRs) and Soluble Boron-Using (SBU) SMRs to evaluate unique pellet-cladding interaction (PCI) risks. Unlike PWRs and SBU SMRs, SBF SMRs rely on control rods for reactivity control, leading to localized power increases during late-cycle withdrawal. This significantly elevates cladding hoop stress, particularly in fuel rods near control rods, increasing PCI risks even at moderate burnups. The maximum local cladding hoop stress due to PCI in SBF SMRs exceeds that of conventional PWRs, posing new fuel safety and qualification challenges despite being SMR fuel characteristics, such as lower power density, and extended relative fuel plenum length. Comparisons with boiling water reactors (BWRs) highlight the heightened PCI risk in SBF SMRs due to differences in core design and control strategies. A fuel loading strategy that positions high-burnup rods away from lead control rod banks effectively reduces peak cladding stress. However, PCI remains a concern, particularly for long-cycle cores with LEU+ fuel. These findings emphasize the need to integrate fuel performance considerations early in SBF SMR development to ensure safety, regulatory compliance, and adaptability for future LEU+ fuels.</div></div>\",\"PeriodicalId\":19272,\"journal\":{\"name\":\"Nuclear Engineering and Technology\",\"volume\":\"57 10\",\"pages\":\"Article 103709\"},\"PeriodicalIF\":2.6000,\"publicationDate\":\"2025-05-20\",\"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/S1738573325002773\",\"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/S1738573325002773","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}
Full-core fuel analysis of a soluble boron-free SMR: Pellet-cladding interaction issue and enhancing fuel safety through loading pattern design
The full-core fuel behavior of the Soluble Boron-Free (SBF) Small Modular Reactor (SMR) was analyzed and compared with conventional pressurized water reactors (PWRs) and Soluble Boron-Using (SBU) SMRs to evaluate unique pellet-cladding interaction (PCI) risks. Unlike PWRs and SBU SMRs, SBF SMRs rely on control rods for reactivity control, leading to localized power increases during late-cycle withdrawal. This significantly elevates cladding hoop stress, particularly in fuel rods near control rods, increasing PCI risks even at moderate burnups. The maximum local cladding hoop stress due to PCI in SBF SMRs exceeds that of conventional PWRs, posing new fuel safety and qualification challenges despite being SMR fuel characteristics, such as lower power density, and extended relative fuel plenum length. Comparisons with boiling water reactors (BWRs) highlight the heightened PCI risk in SBF SMRs due to differences in core design and control strategies. A fuel loading strategy that positions high-burnup rods away from lead control rod banks effectively reduces peak cladding stress. However, PCI remains a concern, particularly for long-cycle cores with LEU+ fuel. These findings emphasize the need to integrate fuel performance considerations early in SBF SMR development to ensure safety, regulatory compliance, and adaptability for future LEU+ fuels.
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