{"title":"Simplified models for high burnup spent nuclear fuel rods and their comparison","authors":"Seyeon Kim, Sanghoon Lee","doi":"10.1016/j.nucengdes.2025.114032","DOIUrl":null,"url":null,"abstract":"<div><div>Effective management of spent nuclear fuel requires maintaining its structural integrity with safety guidelines emphasizing protection of the cladding from mechanical and physical damage that could lead to significant fuel rod failure. According to NUREG-1864, the plastic strain that can cause cladding failure was observed to be in the range of 1.0 ∼ 4.0 %. The experimental data was obtained by pressurized tube tests with defueled cladding specimens and could not reflect the complicated stress states due to the pellet-clad interaction that occurs in real drop impacts. However, the failure criterion of irradiated cladding under more complicated stress states is not easily available. In this study, we perform a comparative analysis of the applicability of simplified models for an SNF rod based on two new fracture criteria and flexural rigidity modification proposed in NUREG-2224. The two new failure criteria utilize curvature based plastic bending strain and membrane plus bending stress through the thickness of the cladding, respectively. Of the three models, the simplified model based on membrane plus bending stress failure criterion was found to be the most conservative in dynamic impact applications.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114032"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-03","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/S0029549325002092","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
Abstract
Effective management of spent nuclear fuel requires maintaining its structural integrity with safety guidelines emphasizing protection of the cladding from mechanical and physical damage that could lead to significant fuel rod failure. According to NUREG-1864, the plastic strain that can cause cladding failure was observed to be in the range of 1.0 ∼ 4.0 %. The experimental data was obtained by pressurized tube tests with defueled cladding specimens and could not reflect the complicated stress states due to the pellet-clad interaction that occurs in real drop impacts. However, the failure criterion of irradiated cladding under more complicated stress states is not easily available. In this study, we perform a comparative analysis of the applicability of simplified models for an SNF rod based on two new fracture criteria and flexural rigidity modification proposed in NUREG-2224. The two new failure criteria utilize curvature based plastic bending strain and membrane plus bending stress through the thickness of the cladding, respectively. Of the three models, the simplified model based on membrane plus bending stress failure criterion was found to be the most conservative in dynamic impact applications.
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.