In advanced steam generators for nuclear power stations, resistance to catastropic stress-corrosion cracking (SCC), induced by chloride or caustic contaminants, is a major consideration in the design and operation of equipment.1,2  Field testing facilities for examining materials of interest for steam generators were recently developed by the Oak Ridge National Laboratory (ORNL) in collaboration with Southern Nuclear Engineering (SNE), Dunedin, Florida. The present paper describes a test facility and techniques developed for conducting chloride stress-corrosion studies and gives early comparative results on a number of materials examined. Because stress corrosion is frequently associated with welds and adjoining thermally affected regions, this study emphasized weldments and thermal and surface treatments thereon. During this investigation the high-pressure Incoloy 800 loop in which the work was conducted developed leaks, and the loop was subsequently destructively analyzed to assess the causes of failures. The findings of this analysis are included.

Subject
Water, Materials, Nickel based alloys, Autoclaves, Weldments, Corrosion loops, Corrosion cracking, Stress cracking, Intergranular cracking, Deposit corrosion, Cracking, Steam, Chloride stress corrosion cracking
© 1974 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).
1974
Association for Materials Protection and Performance (AMPP)
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