“华龙一号”核电厂堆内构件钴基合金堆焊优化设计  

Study on Optimum Design of Cobalt-Based Alloy Surfacing Welding in the RVI of HPR1000

作　　者：王庆田[1] 蒋兴钧[1] 郭宝超 李浩[1] 吴冰洁 王仲辉[1] 陈昕 WANG Qing-tian;JIANG Xing-jun;GUO Bao-chao;LI Hao;WU Bing-jie;WANG Zhong-hui;CHEN Xin(Key Laboratory of Reactor System Design Technology,Nuclear Power Institute of China,Chengdu,Sichuan Prov.610213,China;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：《中国核电》2020年第1期17-22,共6页China Nuclear Power

摘　　要：核反应堆堆内构件的左、右嵌入件与导向销以及径向支承键与U形嵌入件需进行钴基合金堆焊以保证耐磨性能。前期核电项目采用手工钨极氩弧堆焊,堆焊层会出现不同程度的气孔、夹杂甚至裂纹,导致较多不符合项的产生。在大量吸取前期核电厂堆焊经验教训的基础上,本文对堆内构件钴基合金堆焊从设计和工艺方面进行了优化改进,改进后的检验结果显示,堆焊层质量大大提高,表层硬度均匀,硬度线过渡柔和,堆焊层缺陷大大减少。The left and right inserts,guide pins of the reactor vessel internals as well as the radial support and U-shaped inserts require cobalt-based alloy surfacing welding to ensure the wear resistance.In the early stage,manual tungsten-arc welding was used in nuclear power projects,but the surfacing welding had many defects such as porosities,inclusions and even cracks,resulting in a large number of non-conformance reports.The paper brings out design and process measures of cobalt-based alloy surfacing welding on the basis of drawing a lot of experience and lessons from previous surfacing welding.After the design and process improvement,the property of surfacing welding layer is much better than that of before surfacing welding,including better uniformity of hardness,softer hardness line,and lower defects.

关 键 词：钴基合金 堆焊 缺陷 改进 

分 类 号：TM623[电气工程—电力系统及自动化]