Constant load stress corrosion tests were conducted on Type 304SS, which had been irradiated to fast neutron fluences in the range from 0.12-3.00x1021 n/cm2 (E > 1 MeV) in two BWRs. The material originated from three different heats and product forms. Since some of the test specimens had fractured in a creviced region outside of the gage section, times-to-failure (TTF) and %IGSCC were evaluated in terms of starting material, crevice vs. non-crevice failures, stress level, and fluence. Expected variations of TTF and %IGSCC with stress and fluence were stronger in the case of gage section (non-crevice) failures than in the case of crevice failures. The threshold fast neutron fluence for IASCC was found to lie between 0.27 and 0.38x1021 n/cm2 (E > 1 MeV), while the threshold stress is 7.8 ksi, or lower.

Subject
Constant load, Water, Materials, Intergranular stress corrosion cracking, Boiling water reactors, Reactors, Autoclaves, Rods, Irradiation assisted stress corrosion cracking, Stress, Crevices, Tubing, Pressure
Keywords:
stainless steel, irradiation-assisted stress corrosion cracking, constant load test, threshold fast neutron fluence, threshold stress, boiling water reactor, crevice, time-to-failure, %IGSCC
© 1991 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).
1991
Association for Materials Protection and Performance (AMPP)
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