MARC Record from marc_columbia

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001 12131914
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008 160202t20162016enkab ob 001 0 eng d
035 $a(OCoLC)ocn936379392
035 $a(NNC)12131914
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015 $aGBB611149$2bnb
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019 $a939262207$a1229549671
020 $a9780081000625$q(electronic bk.)
020 $a0081000626$q(electronic bk.)
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020 $a9780081000496
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035 $a(OCoLC)936379392$z(OCoLC)939262207$z(OCoLC)1229549671
037 $a9780081000625$bIngram Content Group
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049 $aZCUA
245 00 $aStress corrosion cracking of nickel-based alloys in water-cooled nuclear reactors :$bthe coriou effect /$cedited by D. Féron, R.W. Staehle.
264 1 $aDuxford, UK :$bElsevier, Woodhead Publishing,$c[2016]
264 4 $c©2016
300 $a1 online resource (xvi, 367 pages) :$billustrations (some color), map.
336 $atext$btxt$2rdacontent
337 $acomputer$bc$2rdamedia
338 $aonline resource$bcr$2rdacarrier
490 1 $aWoodhead Publishing series in EFC ;$vnumber 67
588 0 $aOnline resource; title from PDF title page (EBSCO, viewed February 10, 2016).
504 $aIncludes bibliographical references and index.
520 $aStress 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.
505 0 $aFront 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.
505 8 $a1.1.3 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.
505 8 $a1.2.2.4 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.
505 8 $a1.4 Coriou and the Commissariat à l'Énergie 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.
505 8 $a1.5 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 à l'Énergie Atomique; 2.1 Introduction; 2.2 Some benchmarks; 2.3 The use of Alloy 600.
506 $aAccess restricted to Ryerson students, faculty and staff.$5CaOTR
650 0 $aNickel alloys$xStress corrosion.
650 6 $aNickel$xAlliages$xCorrosion sous tension.
650 7 $aTECHNOLOGY & ENGINEERING$xEngineering (General)$2bisacsh
650 7 $aTECHNOLOGY & ENGINEERING$xReference.$2bisacsh
650 7 $aNickel alloys$xStress corrosion.$2fast$0(OCoLC)fst01037477
655 0 $aElectronic books.
655 4 $aElectronic books.
700 1 $aFéron, D.,$eeditor.
700 1 $aStaehle, R. W.,$d1934-2017,$eeditor.
776 08 $iPrint version:$aFeron, Damien.$tStress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors : The Coriou Effect.$d: Elsevier Science, ©2016$z9780081000496
830 0 $aWoodhead Publishing series in EFC ;$vno. 67.
856 40 $uhttp://www.columbia.edu/cgi-bin/cul/resolve?clio12131914.001$zACADEMIC - Metals & Metallurgy
856 40 $uhttp://www.columbia.edu/cgi-bin/cul/resolve?clio12131914.002$zACADEMIC - Electrical & Power Engineering
852 8 $blweb$hEBOOKS