摘要
在压水堆核电厂中,主管道奥氏体不锈钢焊缝长期在其热老化敏感温度(280~325℃)下运行,为了研究主管道奥氏体不锈钢焊缝在核电厂运行温度下的热老化性能,开展了铁素体含量为10.7%的316LN不锈钢主管道焊缝在325、365、400℃下的低温热老化行为研究。结果表明:经6000 h热老化后,焊缝中铁素体相和奥氏体相中的主要元素含量没有发生明显变化,焊缝显微硬度快速增加但奥氏体相显微硬度没有发生变化,焊缝冲击功显著下降、拉伸性能变化较小。
Austenitic stainless steel welds in PWR main pipe are susceptible to thermal aging embrittlement at reactor operating temperature of 280-325℃ after a long service life.In order to obtain thermal aging embrittlement of 316LN austenitic stainless steel weld at reactor operating temperature, In this study, thermal aging embrittlement of types 316LN austenitic stainless steel weld with 10.7% ferrite was investigated on basis of embrittlement properties after aging up to 6,000h at 325,365 and 400℃. The result show that,no change in the main alloy elements contents in ferrite and austenite.Large increase in the microhardness of weld was observed with no change in austenite hardness. The impact toughness was significantly degraded after aging.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2014年第4期102-105,共4页
Nuclear Power Engineering
关键词
热老化脆化
奥氏体不锈钢
显微硬度
冲击韧性
Thermal aging embrittlement, Austenitic stainless steel,Microhardness, Impact toughness