Unique measurements of in-core (and recirculation system) water chemistries, corrosion potentials and crack growth rates were made at a commercial Boiling Water Reactor. In-core crack growth rates were obtained on fracture mechanics specimens of initially furnace sensitized Type 304 and initially non-sensitized Types 304 and 304L stainless steels. The influence of radiation water chemistry on environmentally assisted cracking was isolated and modeled using the initially furnace sensitized specimen; subsequently, the effects of radiation induced segregation were modeled using the initially non-sensitized specimens. Modifications to an existing (ex-core) crack growth rate model were made which permit preliminary predictions of irradiation assisted cracking as a function of water chemistry, stressing, flux / fluence, etc.

Subject
Environmental cracking, Crack growth, Water, Modeling, Corrosion rate, Predicted corrosion rate, Chromium, Water chemistry, Corrosion cracking, Fatigue crack growth rate, Stress cracking, Stainless steel, Corrosion potential
© 1989 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).
1989
Association for Materials Protection and Performance (AMPP)
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