Wellcome

Stress corrosion cracking of nickel-based alloys in water-cooled nuclear reactors : the coriou effect / edited by D. F�eron, R.W. Staehle.

Contributor(s): F�eron, D [editor.] | Staehle, R. W, 1934-2017 [editor.]Material type: TextTextSeries: Woodhead Publishing series in EFC ; no. 67.Publisher: Duxford, UK : Elsevier, Woodhead Publishing, [2016]Copyright date: �2016Description: 1 online resource (xvi, 367 pages) : illustrations (some color), mapContent type: text Media type: computer Carrier type: online resourceISBN: 9780081000625; 0081000626; 0081000499; 9780081000496Subject(s): Nickel alloys -- Stress corrosion | TECHNOLOGY & ENGINEERING -- Engineering (General) | TECHNOLOGY & ENGINEERING -- Reference | Nickel alloys -- Stress corrosionGenre/Form: Electronic books.Additional physical formats: Print version:: Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors : The Coriou Effect.DDC classification: 620.1/88 LOC classification: TA480.N6Online resources: ScienceDirect
Contents:
Front Cover; Related titles; Stress Corrosion Cracking of Nickel-based Alloys in Water-cooled Nuclear Reactors; Copyright; Contents; List of contributors; Woodhead Publishing Series in EFC; Preface; One -- Historical perspectives onstress corrosion cracking ofnickel-based alloys; 1 -- Historical views on stress corrosion cracking of nickel-based alloys: the Coriou effect; Disclaimer; 1.1 Introduction; 1.1.1 The essence of the story; 1.1.2 Personal backgrounds (Coriou, Copson, Rickover); 1.1.2.1 Henri Coriou; 1.1.2.2 Harry Copson; 1.1.2.3 Hyman G. Rickover.
1.1.3 Beginnings of experiments for SCC1.1.4 Significance of early testing; 1.1.5 PWR system conditions, materials, and degradation; 1.1.5.1 Introduction; 1.1.5.2 Materials; 1.1.5.3 Bulk chemical environments; Primary bulk environment; Secondary bulk environment; 1.1.5.4 Local superheat condition; 1.1.5.5 Corrosion product expansion; 1.1.5.6 Temperature; 1.1.5.7 Stress; 1.2 Early nuclear ships and SCC; 1.2.1 Introduction; 1.2.2 Main early events; 1.2.2.1 Fermi and the pile; 1.2.2.2 Nautilus prototype and stress corrosion cracking; 1.2.2.3 The Nautilus and stress corrosion cracking.
1.2.2.4 Shippingport and stress corrosion cracking1.2.2.5 Fossil and nuclear differences; 1.2.3 Corrosion and Wear Handbook; 1.3 Principles and occurrences of corrosion; 1.3.1 Introduction; 1.3.2 Design/materials/operation/degradation: framework of Coriou; 1.3.3 Rickover: principles; 1.3.4 Early beliefs about the occurrence of SCC; 1.3.5 Principles of corrosion; 1.3.6 Corrosion testing; 1.3.7 Initiation and propagation; 1.3.8 Failure at Duane Arnold; 1.3.9 Extent of SCC in Alloy 600: modes and submodes; 1.3.10 Failures of Alloy 600.
1.4 Coriou and the Commissariat �a l'�Energie Atomique, 1955-19751.4.1 Introduction; 1.4.2 Pure deoxygenated water; 1.4.3 Chloride in pure deoxygenated water; 1.4.4 High-temperature steam; 1.4.5 Electrochemical potential; 1.4.6 Alkaline stress corrosion cracking; 1.4.7 Boiling MgCl2; 1.4.8 Temperature; 1.4.9 Stress and plastic strain; 1.4.10 Heat treatments: sensitization and thermal treatment; 1.4.11 Other work in support of Coriou; 1.4.11.1 Introduction; 1.4.12 Coriou's monitoring failures at early plants throughout the world; 1.4.13 Criticisms of Coriou; 1.4.14 Overview.
1.5 Copson and INCO: 1955-19751.5.1 Introduction; 1.5.2 1956-1961: the early Navy SCC problem; 1.5.3 1961-1968: the fruitless impurity cause for Coriou's SCC; 1.5.4 1968-1975: the development of alloy 690; 1.6 The lead story; 1.6.1 Introduction; 1.6.2 Coriou's rebuttal; 1.6.3 A brief history of lead-induced events; 1.6.4 Properties; 1.6.5 Overview of Pb work; 1.7 Conclusions; Acknowledgments; References; 2 -- The saga of Alloy 600 at the Commissariat �a l'�Energie Atomique; 2.1 Introduction; 2.2 Some benchmarks; 2.3 The use of Alloy 600.
Summary: 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 CorrosionShowcases the excellent quality and technical accomplishments of Henri Coriou and CEA.
Item type:
Tags from this library: No tags from this library for this title. Log in to add tags.
Holdings
Item type Current library Call number Status Date due Barcode
Ebooks Ebooks Mysore University Main Library
Not for loan EBKELV108

Online resource; title from PDF title page (EBSCO, viewed February 10, 2016).

Includes bibliographical references and index.

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 CorrosionShowcases the excellent quality and technical accomplishments of Henri Coriou and CEA.

Front Cover; Related titles; Stress Corrosion Cracking of Nickel-based Alloys in Water-cooled Nuclear Reactors; Copyright; Contents; List of contributors; Woodhead Publishing Series in EFC; Preface; One -- Historical perspectives onstress corrosion cracking ofnickel-based alloys; 1 -- Historical views on stress corrosion cracking of nickel-based alloys: the Coriou effect; Disclaimer; 1.1 Introduction; 1.1.1 The essence of the story; 1.1.2 Personal backgrounds (Coriou, Copson, Rickover); 1.1.2.1 Henri Coriou; 1.1.2.2 Harry Copson; 1.1.2.3 Hyman G. Rickover.

1.1.3 Beginnings of experiments for SCC1.1.4 Significance of early testing; 1.1.5 PWR system conditions, materials, and degradation; 1.1.5.1 Introduction; 1.1.5.2 Materials; 1.1.5.3 Bulk chemical environments; Primary bulk environment; Secondary bulk environment; 1.1.5.4 Local superheat condition; 1.1.5.5 Corrosion product expansion; 1.1.5.6 Temperature; 1.1.5.7 Stress; 1.2 Early nuclear ships and SCC; 1.2.1 Introduction; 1.2.2 Main early events; 1.2.2.1 Fermi and the pile; 1.2.2.2 Nautilus prototype and stress corrosion cracking; 1.2.2.3 The Nautilus and stress corrosion cracking.

1.2.2.4 Shippingport and stress corrosion cracking1.2.2.5 Fossil and nuclear differences; 1.2.3 Corrosion and Wear Handbook; 1.3 Principles and occurrences of corrosion; 1.3.1 Introduction; 1.3.2 Design/materials/operation/degradation: framework of Coriou; 1.3.3 Rickover: principles; 1.3.4 Early beliefs about the occurrence of SCC; 1.3.5 Principles of corrosion; 1.3.6 Corrosion testing; 1.3.7 Initiation and propagation; 1.3.8 Failure at Duane Arnold; 1.3.9 Extent of SCC in Alloy 600: modes and submodes; 1.3.10 Failures of Alloy 600.

1.4 Coriou and the Commissariat �a l'�Energie Atomique, 1955-19751.4.1 Introduction; 1.4.2 Pure deoxygenated water; 1.4.3 Chloride in pure deoxygenated water; 1.4.4 High-temperature steam; 1.4.5 Electrochemical potential; 1.4.6 Alkaline stress corrosion cracking; 1.4.7 Boiling MgCl2; 1.4.8 Temperature; 1.4.9 Stress and plastic strain; 1.4.10 Heat treatments: sensitization and thermal treatment; 1.4.11 Other work in support of Coriou; 1.4.11.1 Introduction; 1.4.12 Coriou's monitoring failures at early plants throughout the world; 1.4.13 Criticisms of Coriou; 1.4.14 Overview.

1.5 Copson and INCO: 1955-19751.5.1 Introduction; 1.5.2 1956-1961: the early Navy SCC problem; 1.5.3 1961-1968: the fruitless impurity cause for Coriou's SCC; 1.5.4 1968-1975: the development of alloy 690; 1.6 The lead story; 1.6.1 Introduction; 1.6.2 Coriou's rebuttal; 1.6.3 A brief history of lead-induced events; 1.6.4 Properties; 1.6.5 Overview of Pb work; 1.7 Conclusions; Acknowledgments; References; 2 -- The saga of Alloy 600 at the Commissariat �a l'�Energie Atomique; 2.1 Introduction; 2.2 Some benchmarks; 2.3 The use of Alloy 600.

Access restricted to Ryerson students, faculty and staff. CaOTR

There are no comments on this title.

to post a comment.

No. of hits (from 9th Mar 12) :

web counter

Powered by Koha