A necessary step in preparation of high-level radioactive tank waste for safe disposal is removal of nonradioactive organic and inorganic components from washed waste. The oxidizing and alkaline nature of most wastes allows the removal of the organic components as water vapor, carbon dioxide, and ammonia gas merely by heating the wastes to no more than 350°C. Type 316L stainless steel (UNS S31603), a 21Cr-13.5Mo-Ni alloy (UNS N06022), and 0.8Ni-0.3Mo-Ti alloy (UNS R53400) were candidate materials for reactors in which the oxidation could be performed. Slow-strain-rate tests were performed on these three materials at a strain rate of 10-6 sec-1 in a diluted waste type solution containing 4.1% NO2, 3.7% NO3, 1% OH, and 0.22% TIC. All three materials showed intergranular stress corrosion cracking with substantial losses in ductility and strength.

Subject
Materials, Intergranular stress corrosion cracking, Stainless alloys, Reactors, Nickel based alloys, Autoclaves, Nickel chromium molybdenum alloys, Stress, Mechanical failure, Stainless steel, Titanium alloys, Wastes, Stress corrosion cracking
Keywords:
Liquid high-level waste, titanium, Ni-Cr-Mo Alloy, SCC, stress corrosion cracking, slow strain rate test, SSRT
© 1998 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).
1998
Association for Materials Protection and Performance (AMPP)
You do not currently have access to this content.