Prediction Model for Corrosion Fatigue Lives of Austenitic Stainless Steels in Pressurized Water Reactor Environments-Reference-Cited by-同舟云学术

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

Published:2012-01 Issue:1 Volume:68 Page:015004-1-015004-5
ISSN:0010-9312
Container-title:CORROSION
language:en
Short-container-title:CORROSION

Author:

Xiao J.,Qiu S.Y.,Chen Y.,Xu Q.

Publisher

NACE International

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Link

http://corrosionjournal.org/doi/pdf/10.5006/1.3674294

Cited by 6 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Fatigue Crack Growth of Z2CND18-12N Austenitic Stainless Steel and Its Heat-Affected Zone in a Dissimilar Metal Weld Joint in 325°C Water;Corrosion;2022-07-19

2. Corrosion fatigue crack growth behavior of 316NG heat affected zone in simulated pressurized water reactor environment;Journal of Nuclear Materials;2020-08

3. Effects of Boiling Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels;Journal of Pressure Vessel Technology;2016-02-22

4. Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels;Journal of Pressure Vessel Technology;2015-12-01

5. Technical Note:Frequency Dependence of Fatigue Crack Growth Rate of Alloy 690TT in High-Temperature Boron-Lithium Water;CORROSION;2015-10

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