失水事故下锆合金包壳塑性变形及失效行为研究进展  

Research Progress of the Plastic Deformation and Failure Behavior of the Zirconium Alloy Cladding During LOCA

作　　者：杨育峰 崔怡然 杨忠波[1] YANG Yufeng;CUI Yiran;YANG Zhongbo(State Key Laboratory of Advanced Nuclear Energy Technology,Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]中国核动力研究设计院先进核能技术全国重点实验室,成都610213

出　　处：《材料导报》2024年第S02期308-317,共10页Materials Reports

基　　金：中核集团集中研发项目(中核科发〔2021〕248号);中核集团青年英才项目资金资助(中核科发〔2023〕384号)。

摘　　要：锆合金是目前轻水堆广泛使用的燃料元件包壳材料,失水事故(LOCA)下燃料包壳的性能是目前国内外科学家广泛关注的重点。随着更高的燃耗要求和国产锆合金的推广,国产锆合金在高燃耗下的LOCA中的塑性变形及失效性能成为当前重点关注的方向之一。本文归纳了近年来国内外对LOCA工况下锆合金塑性变形及失效行为的重要研究成果,总结了锆合金的氧化、氢化、脆化过程,及温度、应力、合金元素、预氧化、预氢化、淬火温度等因素对LOCA工况下锆合金塑性变形及失效的影响,讨论了塑性变形失效的微观机制,提出了后续进一步深入研究的方向。Zirconium alloy is a widely used fuel element cladding material in light water reactor(LWR).The performance of fuel cladding under loss of coolant accident(LOCA)is the focus of scientists at home and abroad.With the higher burnup requirements and the promotion of domestic zirconium alloys,the plastic deformation and failure properties of domestic zirconium alloys in LOCA with high burnup have become one of the focus directions at present.In this paper,the important research results on plastic deformation and failure behavior of zirconium alloys under LOCA conditions are summarized.The oxidation,hydrogenation and embrittlement processes of zirconium alloy,as well as the effects of temperature,stress,alloying elements,pre-oxidation,pre-hydrogenation and quenching temperature on the plastic deformation and failure of zirconium alloy under LOCA conditions are summarized.The microscopic mechanism of plastic deformation failure is discussed,and further research directions are proposed.

关 键 词：失水事故 燃料元件包壳 锆合金 塑性变形 二次氢化 氧化 淬火 微观分析 

分 类 号：TL341[核科学技术—核技术及应用]