Analysis on Crack Fatigue Growth Calculation for Nuclear Power Plant In-service Inspection

被引：0

作者：

Yang, Cheng ^{[1
]}

Zhang, Xueliang ^{[1
]}

Xia, Peng ^{[1
]}

机构：

[1] Suzhou Nucl Power Res Inst, Tech Dept, In Serv Inspect, Suzhou, Peoples R China

来源：

2016 THE 3RD INTERNATIONAL CONFERENCE ON MECHATRONICS AND MECHANICAL ENGINEERING (ICMME 2016) | 2017年 / 95卷

关键词：

D O I：

10.1051/matecconf/20179515006

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

Fatigue is the common failure mode for nuclear mechanical components during operation which could induce crack initiation and growth. In order to predict the behaviour of fatigue crack propagating, fatigue calculation is introduced. A new method of crack fatigue growth calculation has been presented in this paper according to French RSE-M Rules. Regarding this method, detail analysis on key formulas selecting, essential calculation factors of occurrences combination, K-value calculation and mechanic modelling, characterization interval option has been performed. One fatigue crack growth calculation example of dissimilar weld of Reactor Pressure Vessel outlet nozzle to the safe end has been taken and the result demonstrates a good expectation.

引用

页数：5

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