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Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors: The Coriou Effect de Damien Feron

Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors: The Coriou Effect: European Federation of Corrosion (EFC) Series, cartea 67

Editat de Damien Feron, Roger W Staehle
en Limba Engleză Hardback – 16 feb 2016
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
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Specificații

ISBN-13: 9780081000496
ISBN-10: 0081000499
Pagini: 384
Dimensiuni: 152 x 229 x 23 mm
Greutate: 0.76 kg
Editura: ELSEVIER SCIENCE
Seria European Federation of Corrosion (EFC) Series

Public țintă

Nuclear metallurgists, materials scientists and engineers, nuclear facility operators, regulators and consultants and researchers and academics working in this field.

Cuprins

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