锆基合金包壳管保护涂层的材料、制备及特性  

Materials, Preparation and Properties of Zirconium Based Alloy Protective Coatings for Nuclear Fuels

作　　者：刘博韬 陈勇[1] 帅斌财 Liu Botao;Chen Yong;Shuai Bincai(College of Mechanical Engineering,University of South China,Hengyang,Hunan 421001,China)

机构地区：[1]南华大学机械工程学院,湖南衡阳421001

出　　处：《机电工程技术》2023年第1期126-128,137,共4页Mechanical & Electrical Engineering Technology

摘　　要：锆合金包壳管上制备保护涂层的主要目的是提高锆合金包壳在正常和事故中运行的可靠性和安全性。简述了锆基合金在核设施中的使用情况及锆合金自身特性,介绍了制备锆合金包壳保护涂层所使用的硅基,铬、铝基等不同材料及PVD、冷喷涂等涂层制备方法,并结合一些常规的机械性能评价及腐蚀和高温蒸汽氧化试验,分析了通过不同材料及制备方法制作的涂层的特性。指出了金属和陶瓷材料涂层在应用中所面临的挑战。最后根据锆合金包壳涂层的应用场景,总结出涂层所需的几点特性。The main purpose of preparing protective coating on zirconium alloy cladding pipe is to improve the reliability and safety of zirconium alloy cladding in normal and accident operation. The application of zirconium based alloy in nuclear facilities and the characteristics of zirconium alloy itself were briefly described, different materials and coating preparation methods such as silicon, chromium and aluminum used in the preparation of zirconium alloy cladding protective coating were introduced, and the characteristics of coatings made by different materials and preparation methods combined with some conventional mechanical property evaluation and corrosion and high temperature steam oxidation tests were analyzed. The challenges in the application of metal and ceramic coatings were pointed out. Finally, according to the application scenario of zirconium alloy cladding coating, several characteristics of the coating were summarized.

关 键 词：锆基合金 抗氧化性 耐腐蚀性 制备方法 

分 类 号：TG178[金属学及工艺—金属表面处理]