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

The Coriou Effect

Nonfiction, Science & Nature, Technology, Metallurgy, Engineering, Mechanical
Cover of the book Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors by , Elsevier Science
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Author: ISBN: 9780081000625
Publisher: Elsevier Science Publication: January 30, 2016
Imprint: Woodhead Publishing Language: English
Author:
ISBN: 9780081000625
Publisher: Elsevier Science
Publication: January 30, 2016
Imprint: Woodhead Publishing
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 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
View on Amazon View on AbeBooks View on Kobo View on B.Depository View on eBay View on Walmart

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.

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