核用锆合金耐LOCA事故FeCrAl合金体系涂层的发展现状  

Development status of FeCrAl alloy coating system for LOCA accident of zirconium alloy cladding tube for nuclear

作　　者：陈靓瑜[1] 李楠 刘昊 芦笙[1] 姚增健 CHEN Liangyu;LI Nan;LIU Hao;LU Sheng;YAO Zengjian(School of Materials Science and Engineering,Jiangsu University of Science and Technology,Zhenjiang 212100,China;National Dies and Molds Quality Supervision Test Center,Kunshan 215300,China)

机构地区：[1]江苏科技大学材料科学与工程学院,镇江212100 [2]国家模具质量监督检验中心,昆山215300

出　　处：《江苏科技大学学报（自然科学版）》2023年第4期31-36,共6页Journal of Jiangsu University of Science and Technology:Natural Science Edition

基　　金：江苏省自然科学基金资助项目(SBK2020022404)。

摘　　要：锆合金是应用最为广泛的核反应堆堆芯包壳材料,然而2011年福岛核泄漏事故暴露了锆合金自身耐高温水蒸气腐蚀性能的不足,事故容错型包壳的研究便自此展开.在锆合金表面沉积涂层是提高锆合金包壳管容错能力的重要手段之一,FeCrAl合金由于其在火力发电领域良好的表现而一直备受关注,并迅速成为了包壳管候选材料之一.文中主要综述了锆合金涂层材料FeCrAl及其衍生材料的研究进展,为FeCrAl作为锆合金涂层的实际应用提供了一定的参考.Zirconium alloy is the most widely used nuclear reactor core-cladding material.However,the Fukushima nuclear leakage accident in 2011 exposed the deficiency in the high-temperature water vapor corrosion resistance of zirconium alloy.Since then,the research on ATF cladding has been carried out.Preparing coatings on the zirconium alloys is one of the important methods to improve their accident tolerance.FeCrAl alloy has attracted much attention because of its good performance in the field of thermal power generation,and has quickly become one of the candidate materials of cladding tubes.This work mainly summarizes the research progress of FeCrAl used as the coating materials on zirconium alloys as well as the derivatives of FeCrAl.This review would be referenced in the practical applications of FeCrAl as the coating of zirconium alloys.

关 键 词：锆合金 耐事故包壳管 FECRAL 高温氧化 制备工艺 

分 类 号：TG174.4[金属学及工艺—金属表面处理]