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

被引：8

作者：

Xiao, J. ^{[1
]}

Qiu, S. Y. ^{[1
]}

Chen, Y. ^{[1
]}

Xu, Q. ^{[1
]}

机构：

[1] Nucl Power Inst China, Sci & Technol Reactor Fuel & Mat Lab, Chengdu 610041, Peoples R China

来源：

CORROSION | 2012年 / 68卷 / 01期

关键词：

austenitic stainless steel; corrosion fatigue mechanism; corrosion fatigue processes; NPIC model; pressurized water reactor environments;

D O I：

10.5006/1.3674294

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

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 environments. The NPIC model is built on a corrosion fatigue mechanism and indicates the corrosion fatigue processes better than the ANL model proposed by Argonne National Laboratory. Both the NPIC and ANL models are somewhat conservative in their predictions.

引用

页数：5

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