Cr涂层包壳管开裂行为的研究进展  

Research Progress on the Cracking Behavior of Cr-coated Cladding for Accident-tolerant Fuel During Service

作　　者：黄莫一杰 高士鑫 尹泓卜 胡述伟 张坤[1] 陈平[1] Huang Moyijie;Gao Shixin;Yin Hongbu;Hu Shuwei;Zhang Kun;Chen Ping(Nuclear Power Institute of China,Sichuan,610200;School of Mechanical and Electrical Engineering,Central South University,Hu'nan,410083)

机构地区：[1]中国核动力研究设计院,四川610200 [2]中南大学机电工程学院,湖南410083

出　　处：《当代化工研究》2024年第12期20-23,共4页Modern Chemical Research

摘　　要：耐事故燃料相比于核电站传统的(UO_(2)/Zr)体系,可以有效地在核反应堆的正常工况中提升反应堆安全性,同时也能抵御更长时间的极限事故,由于其制造工艺成熟,经济效益较高,Cr涂层锆合金包壳在近期被认为是ATF在包壳管上部署的主流方案。但Cr涂层包壳管在服役工况下的开裂行为与失效机制却还未被深入地研究和分析,本文将以正常服役工况和典型事故工况为目标导向,收集总结国内外Cr涂层堆外性能试验的相关数据,就Cr涂层包壳的失效机制预防提出一些建议,以期为后续国内Cr涂层包壳性能优化设计提供一定的数据和理论支持。Compared to the traditional(UO_(2)/Zr)system in nuclear power plants,accident-tolerant fuel(ATF)can effectively enhance the safety of nuclear reactors under normal working conditions and withstand longer durations of extreme accidents.Due to its mature manufacturing process and higher economic benefits,Cr-coated zirconium alloy cladding is considered the mainstream option for ATF deployment on cladding tubes.However,the cracking behavior and failure mechanisms of Cr-coated cladding under service conditions have not been thoroughly studied and analyzed.This paper aims to target both normal service conditions and typical accident conditions.By collecting and summarizing relevant data from domestic and foreign out-of-pile performance tests of Cr-coated cladding,this paper will propose suggestion for preventing the failure mechanisms of Cr-coated cladding.The goal is to provide certain data and theoretical support for the subsequent domestic optimization design of Cr-coated cladding performance.

关 键 词：ATF Cr涂层包壳管 核能材料 

分 类 号：TL[核科学技术]