Corrosion in Pressurized Water Reactors-Reference-Cited by-同舟云学术

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Corrosion in Pressurized Water Reactors

Published:2006 Issue: Volume: Page:362-385
ISSN:
Container-title:Corrosion: Environments and Industries
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ASM International

Reference114 articles.

1. A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends;Bamford,2003

2. Maintenance Strategy of Inconel Components in PWR Primary Systems in France;Champigny

3. Corrosion and Stress Corrosion Cracking of Bolting Materials in Light Water Reactors;Czajkowski,1984

Cited by 18 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. General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants;Journal of Nuclear Materials;2019-10

2. Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature water;Corrosion Science;2019-08

3. Radiation and Thermomechanical Degradation Effects in Reactor Structural Alloys;Structural Alloys for Nuclear Energy Applications;2019

4. Austenitic Stainless Steels;Structural Alloys for Nuclear Energy Applications;2019

5. Effects of Hydrogen Contents on Oxidation Behavior of Alloy 690TT and Associated Boron Accumulation within Oxides in High-Temperature Water;Scanning;2018-06-10

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