The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated pressurized water reactor primary water

Author:

Yamazaki Seiya,Lu Zhanpeng,Ito Yuzuru,Takeda Yoichi,Shoji Tetsuo

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference30 articles.

1. Environment-assisted cracking in austenitic components

2. P.M. Scott, C. Benhamou, An overview of recent obervation and interpretation of IGSCC in nickel base alloys in PWR primary water, in: Proc. of the 10th Int. Symp. Environmental Degradation Materials Nuclear Power Systems-Water Reactors. NACE, 2001, CDROM.

3. P.M. Scott, P. Combrade, On the mechanism of stress corrosion crack initiation and growth in Alloy 600 exposed to PWR primary water, in: Proc. of the 11th Int. Symp. Environmental Degradation Materials Nuclear Power Systems-Water Reactors. ANS, 2003, pp. 29–38.

4. C. Amzallag, F. Vaillant, Stress corrosion cracking propagation rates in reactor vessel head penetrations in Alloy 600, in: Proc. 9th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors, TMS, 1999, pp. 235–241.

5. Effect of Temperature and Cold Work on the Crack Growth Rate of Alloy 600 in Primary Water

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