The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components
By drawing together the current theoretical and experimental understanding of the phenomena of delayed hydride cracking (DHC) in zirconium alloys, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking
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Manfred P. Puls
The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components Delayed Hydride Cracking
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Manfred P. Puls MPP Consulting Oakville, ON Canada
ISSN 1612-1317 ISBN 978-1-4471-4194-5 DOI 10.1007/978-1-4471-4195-2
ISSN 1868-1212 (electronic) ISBN 978-1-4471-4195-2 (eBook)
Springer London Heidelberg New York Dordrecht Library of Congress Control Number: 2012940465 Springer-Verlag London 2012 This work is subject to copyright. All rights are reserved by the Publisher, whether the whole or part of the material is concerned, specifically the rights of translation, reprinting, reuse of illustrations, recitation, broadcasting, reproduction on microfilms or in any other physical way, and transmission or information storage and retrieval, electronic adaptation, computer software, or by similar or dissimilar methodology now known or hereafter developed. Exempted from this legal reservation are brief excerpts in connection with reviews or scholarly analysis or material supplied specifically for the purpose of being entered and executed on a computer system, for exclusive use by the purchaser of the work. Duplication of this publication or parts thereof is permitted only under the provisions of the Copyright Law of the Publisher’s location, in its current version, and permission for use must always be obtained from Springer. Permissions for use may be obtained through RightsLink at the Copyright Clearance Center. Violations are liable to prosecution under the respective Copyright Law. The use of general descriptive names, registered names, trademarks, service marks, etc. in this publication does not imply, even in the absence of a specific statement, that such names are exempt from the relevant protective laws and regulations and therefore free for general use. While the advice and information in this book are believed to be true and accurate at the date of publication, neither the authors nor the editors nor the publisher can accept any legal responsibility for any errors or omissions that may be made. The publisher makes no warranty, express or implied, with respect to the material contained herein. Printed on acid-free paper Springer is part of Springer Science+Business Media (www.springer.com)
To my family: Wife Gloria; children Larissa and Nicholas; grandchildren Alexander, Jessica, Pascale, Benjamin and twins Ashton and Brayden
Preface
Zirconium alloys are widely used in nuclear reactors, their most challenging applications being as cladding for nuclear fuel in Pressurized and Boiling Water Reactors (PWR and BWR, respectively) and as pressure tubes in CANDUTM and Pressurized Heavy Water (PHW) reactors. The possible failure of these components has consequences to the safe and economic operation of these reactors. Data and understanding to prevent any such failures is, therefore, of great importance to the nuclear industry. It was recognized early on in the development of the design of nuclear reactors that these allo
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