改善研究堆用铝合金包壳抗腐蚀性能的研究  

Research on Improving the Corrosion Resistance for Aluminum-alloy Cladding of Research and Test Reactor

作　　者：辛勇[1] 谢清清[1] 李垣明[1] 周毅[1] 蒋有荣[1] 杨勇[2] 王志斌[2] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,四川成都610213 [2]中核北方核燃料元件有限公司,内蒙古包头014035

出　　处：《核科学与工程》2015年第4期718-722,共5页Nuclear Science and Engineering

摘　　要：本文选择研究试验堆用6061Al合金进行阳极氧化和水煮表面预处理后,开展200℃、1.85 MPa的水腐蚀试验。试验结果表明随着预生膜厚度的增加,相同腐蚀时间下生成的氧化膜厚度越大,腐蚀增重也越大。相比于阳极氧化,水煮预处理的工艺较为简单,形成的预生膜厚度较小。从提高铝合金抗腐蚀性能的角度出发,应优先采用水煮预处理的方式。6061A1 alloy for research and test reactor was pretreated by anodizing and hydroxide, and then the specimens were corroded in water at 200 ℃ and 1.85 MPa. The results showed that with increasing of the thickness of pretreatment film, thickness of oxide film generated during corrosion increased, as will weight gain. Compared with anodizing, the process of hydroxide is simpler, and the thickness of pretreatment film is smaller. From the point of improving the corrosion resistance for aluminum alloy, hydroxide is preferred method.

关 键 词：研究堆 铝合金 预处理 

分 类 号：TL341[核科学技术—核技术及应用]