A computerized database, EPRI Database on Environmentally Assisted Cracking (EDEAC), has been established to assemble stress-corrosion cracking and corrosion fatigue crack growth data on materials of interest to the nuclear power generation industry. The database is currently being used to review the basis for the existing ASME reference fatigue crack growth curves for low alloy ferritic steels used for reactor pressure vessels. Also, correlations between fatigue crack growth rate and stress intensity factor range with corrections for frequency, stress ratio, and temperature for austenitic stainless steels in air are also being developed using the data contained in EDEAC.

Subject
Pressure vessels, Crack growth, Corrosion fatigue, Water, Materials, Nuclear power, Stress intensity, Reactors, Fatigue crack growth rate, Stress, Steel, Stainless steel, Fatigue
© 1986 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).
1986
Association for Materials Protection and Performance (AMPP)
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