摘要
锆合金表面改性研究是耐事故燃料包壳发展的一个主要方向,致力于解决高温水蒸气条件下锆合金与水严重反应、氧化腐蚀等问题。对近年来核用锆合金表面制备耐腐蚀涂层的研究进行了简要归纳总结,并对其进行了讨论和展望。
The research on surface modification of zirconium alloy is one of the main directions for the development of accident-resistant fuel cladding.It is committed to solving the problems of serious reaction between zirconium alloy and water,oxidation corrosion and so on under the condition of high temperature steam.In this paper,the research on the preparation of corrosion-resistant coatings on zirconium alloys for nuclear use in recent years is briefly summarized,and its discussion and prospect are discussed.
作者
李昀
邱长军
LI Yun;QIU Chang-jun(Mechanical Engineering School,University of South China,Hengyang Hunan 421001,China)
出处
《装备制造技术》
2019年第8期1-3,共3页
Equipment Manufacturing Technology
基金
国家科技重大专项(2015ZX06004001-002)
湖南省重点实验室基金(湘教发[2014]85)
关键词
锆合金
涂层
耐腐蚀性
抗氧化
zirconium alloy
coating
corrosion resistance
anti oxidation
