核电设备不锈钢堆焊层的铁素体含量  

Ferrite content in austenitic stainless steel cladding of nuclear power components

作　　者：左波[1] 余燕[1] 张茂龙 

机构地区：[1]上海核工程研究设计院,上海200233 [2]上海电气核电设备有限公司,上海200245

出　　处：《焊接技术》2012年第8期10-12,78,共3页Welding Technology

摘　　要：针对化学分析法和磁性法测得的核电设备不锈钢堆焊层铁素体含量的差异,以及焊接工艺参数和焊后热处理对铁素体含量的影响规律,采用3种焊接方法在16MND5低合金钢上堆焊309L+308L进行试验研究。结果表明:磁性法和化学分析法得到的铁素体含量数据之间存在一定的差距;道间温度和焊接电流的提高会使铁素体含量降低;焊后热处理会降低铁素体含量,热处理温度提高和热处理时间的延长会使铁素体含量进一步降低。The ferrite contents date determined by chemical analysis and by magnetic method was different and the welding procedure parameters and the PWHT(post weld heat treatment) should influence the ferrite contents in the stainless steel cladding of nuclear power plants.In this paper,a series of tests that clad 309L+ 308L on 16MND5 low alloy steel were performed.The results showed that the difference of ferrite contents determined by magnetic method and chemical analysis.The increasing of interpass temperature and welding current led to the decreasing of ferrite contents in the cladding.The PWHT decreased the ferrite contents.Moreover,the rising of PWHT temperature and the expanding of PWHT holding time led to the further deceasing of ferrite contents.The research was significant for the design and manufacture of nuclear components.

关 键 词：奥氏体不锈钢 堆焊层 铁素体 

分 类 号：TG115[金属学及工艺—物理冶金] TL48[金属学及工艺—金属学]