Fatigue Life and Crack Growth Mechanisms of the Type 316LN Austenitic Stainless Steel in 310°C Deoxygenated Water
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.2007.9711340
Reference16 articles.
1. Statistical models for estimating fatigue strain-life behavior of pressure boundary materials in light water reactor environments
2. NUREG/CR-5704, ANL-98/31;Chopra O. K.,1999
3. NUREG/CR-6909, ANL-06/08;Chopra O. K.,2006
4. A Proposal of Fatigue Life Correction Factor Fen for Austenitic Stainless Steels in LWR Water Environments
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