Stress Corrosion Cracking of Nickel Based Alloys in Water cooled Nuclear Reactors The Coriou Effect 1st Edition by Damien Feron,Roger W Staehle ISBN 0081000499 978-0081000496

Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors The Coriou Effect 1st Edition by Damien Feron, Roger W. Staehle – Ebook PDF Instant Download/Delivery: 0081000499, 978-0081000496

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Product details:

ISBN 10: 0081000499

ISBN 13: 978-0081000496

Author: Damien Feron, Roger W. Staehle

Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses.

Nickel alloys are more resistant to SCC as well as high temperatures and have been widely used in more challenging environments such as nuclear power plants. However, these alloys can suffer SCC under certain conditions, resulting in component failure. A key figure in understanding the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France’s leading center for nuclear research. This book assesses his work in the context of the latest research on SCC in nickel alloys in nuclear power plants.

• 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

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 Mitigation

Part 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 Techniques

Part 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

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Tags: Damien Feron, Roger W Staehle, Stress Corrosion Cracking, of Nickel Based Alloys in, Water cooled Nuclear Reactors