Binxian He , Shusong Qin , Aobo Han , Wenchao Zhang , Lipeng Du , Xiangfei Meng , Jianchuang Sun , Weihua Cai
{"title":"三瓣花瓣型燃料棒热-机耦合性能初步分析","authors":"Binxian He , Shusong Qin , Aobo Han , Wenchao Zhang , Lipeng Du , Xiangfei Meng , Jianchuang Sun , Weihua Cai","doi":"10.1016/j.nucengdes.2024.113792","DOIUrl":null,"url":null,"abstract":"<div><div>In this paper, an analytical model of thermal–mechanical coupling performance of three-lobe and four-lobe petal-shaped fuel rods (PSFRs) irradiation is established based on the finite element method, and the thermo-mechanical characteristics of PSFR during normal operation and RIA condition are investigated. The results show that the temperature of three-lobe PSFR is large in the middle and small on both sides in the axial direction, and the petal lobe root is the largest in the circumferential direction. During normal operation, the cladding stress increases continuously with time, and the stress in the center region is the largest. At the 200th day and the 600th day, when RIA occurs suddenly, the cladding will exceed the yield strength in 1.003 s and 0.763 s, respectively. The cladding lobe root at the center of three-lobe PSFR is the location of maximum plastic deformation. There are similarities and differences in temperature, heat flux, and stress between three-lobe and four-lobe PSFRs, but they can be substituted for each other. The above study provides guidance for practical application of three-lobe PSFR.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"432 ","pages":"Article 113792"},"PeriodicalIF":2.5000,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Preliminary thermo-mechanical coupling performance analysis of a three-lobe petal-shaped fuel rod\",\"authors\":\"Binxian He , Shusong Qin , Aobo Han , Wenchao Zhang , Lipeng Du , Xiangfei Meng , Jianchuang Sun , Weihua Cai\",\"doi\":\"10.1016/j.nucengdes.2024.113792\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In this paper, an analytical model of thermal–mechanical coupling performance of three-lobe and four-lobe petal-shaped fuel rods (PSFRs) irradiation is established based on the finite element method, and the thermo-mechanical characteristics of PSFR during normal operation and RIA condition are investigated. The results show that the temperature of three-lobe PSFR is large in the middle and small on both sides in the axial direction, and the petal lobe root is the largest in the circumferential direction. During normal operation, the cladding stress increases continuously with time, and the stress in the center region is the largest. At the 200th day and the 600th day, when RIA occurs suddenly, the cladding will exceed the yield strength in 1.003 s and 0.763 s, respectively. The cladding lobe root at the center of three-lobe PSFR is the location of maximum plastic deformation. There are similarities and differences in temperature, heat flux, and stress between three-lobe and four-lobe PSFRs, but they can be substituted for each other. The above study provides guidance for practical application of three-lobe PSFR.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"432 \",\"pages\":\"Article 113792\"},\"PeriodicalIF\":2.5000,\"publicationDate\":\"2025-02-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0029549324008926\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"2024/12/18 0:00:00\",\"PubModel\":\"Epub\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549324008926","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2024/12/18 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Preliminary thermo-mechanical coupling performance analysis of a three-lobe petal-shaped fuel rod
In this paper, an analytical model of thermal–mechanical coupling performance of three-lobe and four-lobe petal-shaped fuel rods (PSFRs) irradiation is established based on the finite element method, and the thermo-mechanical characteristics of PSFR during normal operation and RIA condition are investigated. The results show that the temperature of three-lobe PSFR is large in the middle and small on both sides in the axial direction, and the petal lobe root is the largest in the circumferential direction. During normal operation, the cladding stress increases continuously with time, and the stress in the center region is the largest. At the 200th day and the 600th day, when RIA occurs suddenly, the cladding will exceed the yield strength in 1.003 s and 0.763 s, respectively. The cladding lobe root at the center of three-lobe PSFR is the location of maximum plastic deformation. There are similarities and differences in temperature, heat flux, and stress between three-lobe and four-lobe PSFRs, but they can be substituted for each other. The above study provides guidance for practical application of three-lobe PSFR.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.