
Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors
The Coriou Effect
Description
Key Features
- Up-to-date reviews of recent research findings from leading experts in the field
- Authoritative and comprehensively reviewed by the Working Party 4 on Nuclear Corrosion
- Showcases the excellent quality and technical accomplishments of Henri Coriou and CEA
Readership
Nuclear metallurgists, materials scientists and engineers, nuclear facility operators and regulators, consultants, researchers and academics working in this field.
Table of Contents
Part I Historical Perspectives on Stress Corrosion Cracking of Nickel-Based Alloys
1. The Coriou Effect
2. The Saga of Alloy 600 at the CEA
3. The Inconel Affair at EDF or ‘Coriou’s Syndrome’
4. Coriou’s Cracking in Japanese PWRs and its MitigationPart II Stress Corrosion Cracking in Nickel-Based Alloys
5. Understanding and Prediction of Stress Corrosion Cracking (SCC) in Nickel-Based Alloys in Boiling and Pressurised Water Reactor Environments
6. The Electrochemical Nature of Stress Corrosion Cracking (SCC)
7. Stress Corrosion Cracking (SCC) and Hydrogen Embrittlement
8. Intergranular Oxide Penetration of Alloy 600 in Pressurized Water Reactor Primary Water Environment
9. Stress Corrosion Cracking of Alloy 600: Overviews and Experimental TechniquesPart III Appendix
1.1 ISO (International Organization for Standardization) Published Standards
1.2 ISO Standards Under Publication
1.3 ASTM (American Society for Testing and Materials) Standards
Product details
- No. of pages: 384
- Language: English
- Copyright: © Woodhead Publishing 2016
- Published: January 30, 2016
- Imprint: Woodhead Publishing
- eBook ISBN: 9780081000625
About the Editors
Damien FERON
Affiliations and Expertise
Roger Staehle
Affiliations and Expertise
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