LOCA事故工况下锆包壳的高温氧化行为研究进展  

Research Progress on High Temperature Oxidation Behavior of Zirconium Cladding under LOCA Condition

作　　者：赵琬倩 贾玉振 裴静远 李国庆 吕俊男 张君松 廖京京 彭倩[1] Zhao Wanqian;Jia Yuzhen;Pei Jingyuan;Li Guoqing;Lyu Junnan;Zhang Junsong;Liao Jingjing;Peng Qian(Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]中国核动力研究设计院反应堆燃料及材料重点实验室,成都610213

出　　处：《核动力工程》2023年第S01期119-124,共6页Nuclear Power Engineering

基　　金：国家自然科学基金项目(52101104)。

摘　　要：锆合金是被广泛地用于水冷动力堆反应的包壳材料。锆合金包壳在失水事故(LOCA)极端事故工况下的高温行为成为国内外学者研究和讨论的热点。本文综述了近年来国内外锆合金的高温氧化行为研究进展,详述了氧化动力学特征、氧化失稳现象和氧化转折机理,同时概述了近10年中国核动力研究设计院(NPIC)的相关研究工作。本文报道的研究进展,尤其是对于转折机理的探讨,可为进一步提高国产化新型锆合金使用性能提供研发指导。Zirconium alloy is a cladding material widely used in water-cooled power reactor.The high temperature behavior of zirconium alloy cladding under the extreme accident condition of loss of coolant accident(LOCA) has become a hot topic of research and being discussed at home and abroad.This paper summarizes the worldwide current research progress on high temperature oxidation behavior of zirconium alloy.The oxidation kinetics characteristics,breakaway oxidation behavior,and the oxidation transition mechanism are described in detail.Meanwhile,the research work of Nuclear Power Institute of China for nearly recent ten years has also been overviewed.The research progress reported in this paper,especially the discussion on the oxidation transition mechanism,will provide a theoretical guidance for developing domestic new zirconium alloys in the further.

关 键 词：锆合金 包壳 失水事故(LOCA) 事故工况 氧化行为 转折机理 

分 类 号：TL334[核科学技术—核技术及应用]