摘要
针对压水堆核电站堆内构件用304奥氏体不锈钢的焊缝在325,365,400℃热老化不同时间后的组织和力学性能进行了研究,并与热老化前的进行了对比。结果表明:热老化后,焊缝组织以及焊缝中铁素体相和奥氏体相中的主要元素含量均没有明显变化,焊缝的显微硬度明显增大,但奥氏体相的显微硬度没有明显变化,焊缝的冲击功显著下降,拉伸性能的变化较小;热老化温度越高,焊缝力学性能的变化越大。
The microstructure and mechanical properties of the weld of 304 austenitic stainless steel used in PWR（pressurized water reactor）nuclear powder plants reactor internals after thermal aging at 325 ℃,365 ℃ and400 ℃for different time were studied and compared with those before thermal aging.The results show that,after thermal aging,the microstructure in the weld and the main alloy elements contents in ferrite and austenite all had no obvious changes,the micro-hardness of the weld increased obviously but that of the austenite had no obvious changes,and the impact energy sharply decreased and the tensile properties changed less.The higher the thermal aging temperature,the greater the changes of the mechanical properties of the weld.
出处
《机械工程材料》
CAS
CSCD
北大核心
2014年第11期31-34,共4页
Materials For Mechanical Engineering
基金
国家科技重大专项资助项目(2011ZX06004-002)
关键词
热老化
奥氏体不锈钢
焊缝
显微硬度
冲击韧性
thermal aging
austenitic stainless steel
weld
micro-hardness
impact toughness
