Prediction of stress corrosion cracking (SCC) in nuclear power systems

Author:

Andresen P.L.,Ford F.P.

Publisher

Elsevier

Reference163 articles.

1. Stress Corrosion Crack Initiation Process Model for BWR Plant Materials;Akashi,1995

2. Crack Growth Rate Behavior of Low Carbon Stainless Steels of Hardened Heat Affected Zone in PLR Piping Weld Joints;Ando,2007

3. The Effects of Surface Preparation, Stress and Deaeration on the Stress Corrosion Cracking of Type 304 Stainless Steel in Simulated BWR Start-Up Cycles;Andresen;Proc. Seminar on Countermeasures for Pipe Cracking in BWRs,1980

4. The Effects of Aqueous Impurities on Intergranular Stress Corrosion Cracking of Sensitized 304 Stainless Steel;Andresen,1983

5. Laboratory Results on Effects of Oxygen Control during a BWR Start up on the IGSCC of 304 Stainless Steel;Andresen;Proc. 2nd Seminar on Countermeasures for Pipe Cracking in BWRs,1984

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