Binxian He , Juexiong Deng , Wenchao Zhang , Xiangfei Meng , Jianchuang Sun , Yuxiang Hong , Weihua Cai
{"title":"基于容错燃料包壳的花瓣形燃料棒热力学性能研究","authors":"Binxian He , Juexiong Deng , Wenchao Zhang , Xiangfei Meng , Jianchuang Sun , Yuxiang Hong , Weihua Cai","doi":"10.1016/j.anucene.2025.111863","DOIUrl":null,"url":null,"abstract":"<div><div>Accident-tolerant fuel (ATF) cladding enhances nuclear fuel performance under extreme accident conditions. Current research on applying ATF cladding to petal-shaped fuel rods (PSFRs) for performance improvement remains exploratory. This study establishes a finite element-based thermo-mechanical coupling model to analyse PSFR behaviour under irradiation. The thermal–mechanical performance of Cr-coated, FeCrAl-coated, Zr-1%Nb, and FeCrAl claddings was investigated under normal operation and reactivity-initiated accident (RIA) conditions to evaluate their potential for replacing conventional Zr-4 cladding. Results indicate that thermal creep is the primary factor driving performance differences among cladding materials. Cr/FeCrAl-coated PSFR exhibited minor deviations from the reference model in stress, strain, and temperature distribution. While FeCrAl cladding demonstrated superior deformation resistance, it displayed earlier plastic strain initiation. Zr-1%Nb achieved significantly lower cladding stress (15.6 MPa at 5 % FIMA) owing to its excellent creep rate, highlighting its advantage in stress management. However, creep-induced radial deformation necessitates either increasing the gap between fuel rods or localizing the cladding thickness at petal angle to mitigate dimensional impacts.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111863"},"PeriodicalIF":2.3000,"publicationDate":"2025-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Thermo-mechanical performance of petal-shaped fuel rods based on accident tolerant fuel cladding\",\"authors\":\"Binxian He , Juexiong Deng , Wenchao Zhang , Xiangfei Meng , Jianchuang Sun , Yuxiang Hong , Weihua Cai\",\"doi\":\"10.1016/j.anucene.2025.111863\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Accident-tolerant fuel (ATF) cladding enhances nuclear fuel performance under extreme accident conditions. Current research on applying ATF cladding to petal-shaped fuel rods (PSFRs) for performance improvement remains exploratory. This study establishes a finite element-based thermo-mechanical coupling model to analyse PSFR behaviour under irradiation. The thermal–mechanical performance of Cr-coated, FeCrAl-coated, Zr-1%Nb, and FeCrAl claddings was investigated under normal operation and reactivity-initiated accident (RIA) conditions to evaluate their potential for replacing conventional Zr-4 cladding. Results indicate that thermal creep is the primary factor driving performance differences among cladding materials. Cr/FeCrAl-coated PSFR exhibited minor deviations from the reference model in stress, strain, and temperature distribution. While FeCrAl cladding demonstrated superior deformation resistance, it displayed earlier plastic strain initiation. Zr-1%Nb achieved significantly lower cladding stress (15.6 MPa at 5 % FIMA) owing to its excellent creep rate, highlighting its advantage in stress management. However, creep-induced radial deformation necessitates either increasing the gap between fuel rods or localizing the cladding thickness at petal angle to mitigate dimensional impacts.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"226 \",\"pages\":\"Article 111863\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-09-16\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0306454925006802\",\"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":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925006802","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}
Thermo-mechanical performance of petal-shaped fuel rods based on accident tolerant fuel cladding
Accident-tolerant fuel (ATF) cladding enhances nuclear fuel performance under extreme accident conditions. Current research on applying ATF cladding to petal-shaped fuel rods (PSFRs) for performance improvement remains exploratory. This study establishes a finite element-based thermo-mechanical coupling model to analyse PSFR behaviour under irradiation. The thermal–mechanical performance of Cr-coated, FeCrAl-coated, Zr-1%Nb, and FeCrAl claddings was investigated under normal operation and reactivity-initiated accident (RIA) conditions to evaluate their potential for replacing conventional Zr-4 cladding. Results indicate that thermal creep is the primary factor driving performance differences among cladding materials. Cr/FeCrAl-coated PSFR exhibited minor deviations from the reference model in stress, strain, and temperature distribution. While FeCrAl cladding demonstrated superior deformation resistance, it displayed earlier plastic strain initiation. Zr-1%Nb achieved significantly lower cladding stress (15.6 MPa at 5 % FIMA) owing to its excellent creep rate, highlighting its advantage in stress management. However, creep-induced radial deformation necessitates either increasing the gap between fuel rods or localizing the cladding thickness at petal angle to mitigate dimensional impacts.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.