核反应堆堆内构件用304H奥氏体不锈钢敏化非腐蚀条件下的性能研究  

Property Research of 304H Austenite Stainless Steel Used in RVI under Sensitizing But No Corrosion Circumstance

作　　者：王庆田[1] 胡朝威[1] 冷晓春 蒋兴钧[1] 王仲辉[1] WANG Qingtian;HU Chaowei;LENG Xiaochun;JIANG Xingjun;WANG Zhonghui(Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China;Shanghai No.1 Machine Tool works Co., Ltd., Shanghai 201306, China)

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]上海第一机床厂有限公司,上海201306

出　　处：《热加工工艺》2018年第22期101-105,共5页Hot Working Technology

摘　　要：介绍了压水型反应堆堆内构件常用的各种奥氏体不锈钢牌号,包括化学成分和力学性能差异。结合压水型反应堆堆内构件用材料的性能要求,分析了304H奥氏体不锈钢在敏化条件下的碳化铬Cr23C6在晶界的析出形态以及各种腐蚀介质对304H不锈钢性能的影响。研究了304H不锈钢在敏化非腐蚀条件下的力学性能。结果表明,敏化后的304H不锈钢,力学性能有一定程度的下降。Several types of austenite stainless steel usually used in Reactor Vessel Internals were introduced, including the difference between chemical composition and mechanical properties. Combining with the requirements of the properties of the materials used in reactor vessel internals, the precipitation states of Cr23C6 in 304H austenite stainless steel in grain boundary under sensitizing condition and the influences of different corrosion mediators on the properties of 304H austenite stainless steel were analyzed. The mechanical properties of 304H stainless steel in sensitizing but no corrosion circumstance were researched. The results show that the mechanical properties of 304H stainless steel after sensitizing decreases in a certain degree.

关 键 词：堆内构件 304H不锈钢 敏化 非腐蚀 性能 

分 类 号：TG172[金属学及工艺—金属表面处理]