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Prediction Model for Corrosion Fatigue Lives of Austenitic Stainless Steels in Pressurized Water Reactor Environments

host posted on January 01, 2012 00:00
J. Xiao, S. Y. Qiu, and Y. Chen et al.
A basic problem of austenitic stainless steels applied in pressurized water reactors (PWR) is degradation by corrosion fatigue. This paper proposes a prediction model (Nuclear Power Institute of China [NPIC] model) to estimate corrosion fatigue lives of austenitic stainless steels in PWR environme ... [Corrosion 68, 015004 (2012)] published Sun Jan 01, 2012.

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