Effect of deformation level and orientation on SCC of 316L stainless steel in simulated light water environments-Reference-Cited by-同舟云学术

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Effect of deformation level and orientation on SCC of 316L stainless steel in simulated light water environments

Published:2020-04 Issue: Volume:531 Page:152038
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Du Donghai,Song Miao,Chen Kai,Zhang Lefu,Andresen Peter L.

Funder

National Key R&D Research

China Postdoctoral Science Foundation

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference40 articles.

1. Precursor evolution and stress corrosion cracking initiation of cold-worked Alloy 690 in simulated pressurized water reactor primary water;Zhai;Corrosion-US,2017

2. Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water;Du;Corros. Sci.,2016

3. SCC crack growth rate of cold worked 316L stainless steel in PWR environment;Du;J. Nucl. Mater.,2015

4. Stress Corrosion Crack Growth Rate Behavior of Various Grades of Cold Worked Stainless Steel in High Temperature Water;Andresen,2002

5. Cold work and temperature dependence of stress corrosion crack growth of austenitic stainless steels in hydrogenated and oxygenated high-temperature water;Arioka;Corrosion-US,2007

Cited by 17 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. Effect of cold work level on the crack propagation behaviour of 316LN stainless steel in high-temperature pressurized water;Journal of Nuclear Materials;2024-09

2. Effect of the triangular prism dent on stress corrosion cracking behavior of alloy 690TT heat transfer tube in a lead-containing alkaline solution;Journal of Nuclear Materials;2024-06

3. Effect of surface hemispherical dent depth on the microstructure evolution and stress corrosion cracking of heat transfer tubes in steam generator;Corrosion Science;2024-04

4. A review of stress corrosion cracking of austenitic stainless steels in PWR primary water;Journal of Nuclear Materials;2024-01

5. Revealing the effect of heat treatment on stress corrosion cracking behavior of Monel 400 alloy in hydrofluoric acid vapor environment;Corrosion Science;2023-05

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