兵器工业

690合金在压水堆环境中的腐蚀疲劳裂纹扩展行为

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  • 上海交通大学 核科学与工程学院, 上海 200240

网络出版日期: 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

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

Online published: 2017-11-30

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.

本文引用格式

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, 2017 , 51(11) : 1281 -1286 . DOI: 10.16183/j.cnki.jsjtu.2017.11.001

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.

参考文献

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