Skip to main content
Elsevier

Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors

The Coriou Effect

  • 1st Edition, Volume 67 - January 30, 2016
  • Latest edition
  • Editors: Damien Feron, Roger W Staehle
  • Language: English

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… Read more

Description

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.

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 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

Product details

  • Edition: 1
  • Latest edition
  • Volume: 67
  • Published: February 19, 2016
  • Language: English

About the editors

DF

Damien Feron

Damien Féron has been Director of Research at CEA (French Atomic and Alternative Energies Commission) since 2007 and Professor at INSTN (The French School for Energy and Health Technology, University Paris-Saclay) since 2010. He has been working in the corrosion field for more than 40 years. He chaired the Working Party on Nuclear Corrosion (2003-2016) of the European Federation of Corrosion (EFC) and the Science and Technology Advisory Committee (STAC). He has been President of the EFC (2017-18) and the WCO (World Corrosion Organization) which is a non-governmental organization recognized by the United Nations (2019-2022). He has published more than 70 scientific papers and is editor or co-editor of 22 books or special issues in journals, mainly in the field of microbial corrosion, seawater corrosion and nuclear corrosion. During his career, he has received several national and international honors, including appointment as an Honorary Fellow from both NACE (USA) and the EFC, and the Lee Hsun Lecture Award in China. He was also nominated for the “Chevalier dans l’ordre des Palmes Académiques” (French National Honor) in 2017.
Affiliations and expertise
Director of Research, CEA and Professor, INSTN (Université Paris-Saclay), France

RS

Roger W Staehle

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.
Affiliations and expertise
Formerly University of Minnesota, USA

View book on ScienceDirect

Read Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors on ScienceDirect