Inconel Alloy 600*, a nickel-base alloy containing nominally 15% chromium and 7% iron by weight has seen limited but successful use as a structural material in commercial boiling water nuclear reactors (BWR). Laboratory experiments have shown that intergranular crack initiation in smooth specimens stressed beyond yield requires exposure for thousands of hours to water at 288 C, the reactor operating temperature, but crevices can reduce this time dramatically (1).
Subject
Anions,
Water,
Diffusion,
Nickel based alloys,
Tubes,
Autoclaves,
Acidity,
Crevices,
Ion concentrations,
Impurities,
Metals,
Oxygen,
Electrode potential
© 1978 Association for Materials Protection and Performance (AMPP). All rights reserved. No part of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means (electronic, mechanical, photocopying, recording, or otherwise) without the prior written permission of AMPP. Positions and opinions advanced in this work are those of the author(s) and not necessarily those of AMPP. Responsibility for the content of the work lies solely with the author(s).
1978
Association for Materials Protection and Performance (AMPP)
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