【作者】 肖军； 邱绍宇； 林震霞； 陈勇；

【Author】 XIAO Jun;QIU Shao-yu;LIN Zhen-xia;CHEN Yong;Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China;

【机构】 中国核动力研究设计院反应堆燃料及材料重点实验室；

【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,在反应堆环境下服役时,可能产生腐蚀疲劳开裂。本文在裂纹尖端处于小范围屈服条件下,研究了压水反应堆环境对Inconel 690(TT)合金腐蚀疲劳裂纹扩展行为的影响,发现反应堆环境对腐蚀疲劳裂纹扩展速率有显著的加速作用,并且模拟一回路水介质环境对腐蚀疲劳裂纹扩展速率的影响大于模拟二回路水介质环境。此外,腐蚀疲劳裂纹非平面生长与反应堆水介质环境相关,并且对腐蚀疲劳裂纹扩展行为产生重要影响。更多还原

【Abstract】 Inconel 690(TT) is one of the key materials for tubes of steam generators for pressurized water reactor,where it is susceptible to corrosion fatigue cracking.In this paper,influence of pressurized water reactor environments on corrosion fatigue cracking behavior of Inconel 690(TT)was investigated under small scale yielding conditions.It was found that the accelerating effect of pressurized water reactor environments on corrosion fatigue crack growth rates was significant and this effect was more pronounced in the simulated primary water.In addition,out-of-plane cracking of corrosion fatigue cracks was correlated with pressurized water reactor environments and influenced the corrosion fatigue cracking behavior significantly.更多还原