核燃料包壳锆合金表面涂层研究进展  

Research Progress of Coating on Zirconium Alloy for Nuclear Fuel Cladding

作　　者：柏广海[1] 陈志林[1] 张晏玮[1] 刘二伟[1] 薛佳祥 余伟炜[1] 王荣山[1] 李锐 刘彤 

机构地区：[1]苏州热工研究院有限公司,江苏苏州215004 [2]中广核研究院有限公司,广东深圳518026

出　　处：《稀有金属材料与工程》2017年第7期2035-2040,共6页Rare Metal Materials and Engineering

基　　金：苏州市2016产业技术创新专项(SYG201634);国家自然科学基金(51271018;51502322)

摘　　要：锆合金表面涂层是提高核燃料包壳事故容错能力的重要途径之一。本文综述了锆合金表面涂层的研究进展,包括涂层种类、制备工艺、微观组织以及抗水蒸气氧化性能、耐腐蚀性能等,介绍了锆合金表面涂层种类选择的依据,探讨了涂层的制备工艺、微观组织与性能之间的关系,分析了当前研究中存在的若干问题及未来涂层的发展方向,为进一步促进核燃料包壳锆合金表面涂层的研究提供了有价值的参考。Coating on zirconium alloy is one of important ways to improve the properties of fuel cladding in nuclear power plant accidents. The research progress of the coating on the surface of zirconium alloy was summarized, including types, preparation process, microstructures, steam oxidation resistant properties and corrosion resistant properties. The selection basis of the coating, and the relationship between preparation process, microstructure and properties were discussed. Some problems in the present researches and development of the coating were analyzed. The results can provide valuable references for promoting development of the coating on nuclear fuel cladding.

关 键 词：燃料包壳 事故容错 锆合金 涂层 水蒸气氧化 

分 类 号：TG174.4[金属学及工艺—金属表面处理]