690合金在压水堆环境中的腐蚀疲劳裂纹扩展行为

doi:10.16183/j.cnki.jsjtu.2017.11.001

上海交通大学学报（自然版） ›› 2017, Vol. 51 ›› Issue (11): 1281-1286.doi: 10.16183/j.cnki.jsjtu.2017.11.001

• 兵器工业 • 下一篇

690合金在压水堆环境中的腐蚀疲劳裂纹扩展行为

陈凯，杜东海，张乐福

上海交通大学核科学与工程学院，上海 200240

出版日期:2017-11-30 发布日期:2017-11-30
基金资助:
国家科技重大专项（项目号:2010ZX06004018）

Corrosion Fatigue Crack Growth Behavior of Alloy 690 in PressurizedWater Reactor Environment

CHEN Kai,DU Donghai,ZHANG Lefu

School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China

Online:2017-11-30 Published:2017-11-30

摘要/Abstract

摘要： 在模拟压水堆一回路环境下测得690合金的腐蚀疲劳裂纹扩展速率，腐蚀对疲劳裂纹扩展有促进作用.采用时域分析方法分析讨论了相关载荷参数(载荷比R，频率f，应力强度因子幅值ΔK)对腐蚀疲劳裂纹扩展的影响.试验结果采用FA(FordAndresen)模型和ANL(Argonne National Lab)经验公式进行拟合，试验值与预测值吻合较好.断口微观形貌表明，空气中的疲劳断口为穿晶断裂；高温水下的疲劳断口同时出现穿晶和沿晶特征，与FA模型的机制解释吻合.

关键词: 腐蚀疲劳, 690合金, 裂纹扩展速率

Abstract: Corrosion fatigue crack growth rates of Alloy 690 have been measured in air and simulated pressurizedwater reactor (PWR) environment, and environmental acceleration of fatigue crack growth is observed. The effects of loading parameters including loading ratio R, frequency f and amplitude of stress intensity factors ΔK have been discussed and summarized by the timedomain method. Furthermore, the obtained experimental results are compared with FA (FordAndresen) model and ANL (Argonne National Lab) empirical curve, and they could fit fairly well. Fracture surface morphology reveals tansgranular crack in air fatigue and tansgranular with intergranular crack in hotwater environment, which accords well with the description of FA model.

Key words: corrosion fatigue, alloy 690, crack growth rates

中图分类号:

TL 341

陈凯，杜东海，张乐福. 690合金在压水堆环境中的腐蚀疲劳裂纹扩展行为[J]. 上海交通大学学报（自然版）, 2017, 51(11): 1281-1286.

CHEN Kai,DU Donghai,ZHANG Lefu. Corrosion Fatigue Crack Growth Behavior of Alloy 690 in PressurizedWater Reactor Environment[J]. Journal of Shanghai Jiaotong University, 2017, 51(11): 1281-1286.

参考文献

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690合金在压水堆环境中的腐蚀疲劳裂纹扩展行为

Corrosion Fatigue Crack Growth Behavior of Alloy 690 in PressurizedWater Reactor Environment

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