Inconel690(TT)合金在压水堆二回路水环境下的腐蚀疲劳裂纹扩展行为研究  

Corrosion Fatigue Cracking Behavior of Inconel 690(TT) in Secondary Water of Pressurized Water Reactors

作　　者：肖军[1] 陈璐瑶[1] 付正鸿[2] 邱绍宇[1] 陈勇[1] 林震霞[1] 

机构地区：[1]中国核动力研究设计院反应堆燃料及材料重点实验室,成都610041 [2]西华大学材料科学与工程学院,成都610039

出　　处：《核动力工程》2015年第4期83-85,共3页Nuclear Power Engineering

摘　　要：Inconel 690(TT)合金是压水反应堆蒸汽发生器传热管的关键材料之一,在压水反应堆工况下具有腐蚀疲劳开裂的风险。本文在裂纹尖端小范围屈服的条件下,研究了Inconel 690(TT)合金在模拟二回路水介质环境下的腐蚀疲劳裂纹扩展行为。研究发现:相对于室温情况下,模拟二回路水介质对疲劳裂纹扩展速率有最大3倍左右的加速作用;模拟二回水介质对疲劳裂纹扩展速率的加速作用受腐蚀疲劳裂纹非平面生长的影响,并与应力强度因子范围、最大应力强度因子及应力比密切相关。Inconel 690 （TT） is one of the key materials for tubes of steam generators for pressurized water reactors, where it is susceptible to corrosion fatigue cracking. In this paper, the corrosion fatigue cracking behavior of Inconel 690 （TT） was investigated under small scale yielding conditions, in the simulated secondary water of pressurized water reactor. It was observed that the fatigue crack growth rate was accelerated by a maximum factor up to 3 in the simulated secondary water, comparing to that in room temperature air. In addition, it was found that the accelerating effect was influenced by out-of-plane cracking of corrosion fatigue cracks and also correlated with stress intensity factor range, maximum stress intensity factor and stress ratio.

关 键 词：INCONEL 690(TT)合金 压水反应堆 小范围屈服 腐蚀疲劳 

分 类 号：TL333[核科学技术—核技术及应用]