Simplified models for high burnup spent nuclear fuel rods and their comparison

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-04-03 DOI:10.1016/j.nucengdes.2025.114032

Seyeon Kim, Sanghoon Lee

{"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.

Abstract Image

查看原文本刊更多论文

高燃耗乏燃料棒的简化模型及其比较

乏核燃料的有效管理需要保持其结构完整性，安全准则强调保护包层免受可能导致燃料棒严重失效的机械和物理损伤。根据nuregg -1864，可导致包层失效的塑性应变在1.0 ~ 4.0%的范围内。实验数据是用脱燃料包壳试样进行的加压管试验获得的，不能反映真实液滴冲击时球团-包壳相互作用产生的复杂应力状态。然而，在较复杂的应力状态下，辐照熔覆层的破坏判据并不容易得到。在本研究中，我们基于两个新的断裂准则和nuregg -2224中提出的抗弯刚度修正，对SNF杆简化模型的适用性进行了对比分析。这两种新的破坏准则分别利用基于曲率的塑性弯曲应变和通过包层厚度的膜加弯曲应力。在三种模型中，基于膜加弯曲应力破坏准则的简化模型在动态冲击应用中最为保守。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

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.