Stress Corrosion Cracking of Nickel Based Alloys in Water-co

Erscheinungsjahr 2016
ISBN: 978-0-08-100049-6
Verlag: Elsevier Science & Technology

Buch, Englisch, 384 Seiten, Format (B × H): 159 mm x 237 mm, Gewicht: 742 g

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.

Zielgruppe

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

Autoren/Hrsg.

Feron, Damien

Staehle, Roger W

Fachgebiete

• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Festigkeitslehre, Belastbarkeit
• Technische Wissenschaften Verfahrenstechnik | Chemieingenieurwesen | Biotechnologie Metallurgie
• Technische Wissenschaften Energietechnik | Elektrotechnik Atomenergietechnik
• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Materialwissenschaft: Metallische Werkstoffe

Inhaltsverzeichnis

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

Über Autor(innen)

Staehle, Roger W
Roger Staehle is very well-known and has been active in the nuclear corrosion community for over 60 years. He is a Retired Professor of the Department of Chemical Engineering and Materials Science at the University of Minnesota and an industrial consultant. He has edited 29 volumes and published 220 papers. among other honors, he was elected to the (US) National Academy of Engineering and received the Willis Rodney Whitney Award. He has consulted for many industries, including the nuclear one, and for governments in the United States, Japan, China and Korea.