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Effect of Stainless Steel Can/Glass-ceramic Interaction Layer on Aqueous Durability

Published online by Cambridge University Press:  19 October 2011

Peter McGlinn ,
Yingjie Zhang ,
Huijun Li  and
Timothy E. Payne
Peter McGlinn
Affiliation:
pjm@ansto.gov.au, Australian Nuclear Science & Technology Organisation, Institute of Materials & Engineering Science, New Illawarra Road, Lucas Heights, 2234, Australia, 61 2 9717 9093, 61 2 9543 7179
Yingjie Zhang
Affiliation:
yzx@ansto.gov.au, Australian Nuclear Science & Technology Organisation, New Illawarra Road, Lucas Heights, N/A, Australia
Huijun Li
Affiliation:
hlx@ansto.gov.au, Australian Nuclear Science & Technology Organisation, New Illawarra Road, Lucas Heights, N/A, Australia
Timothy E. Payne
Affiliation:
tep@ansto.gov.au, Australian Nuclear Science & Technology Organisation, New Illawarra Road, Lucas Heights, N/A, Australia
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Abstract

Calcined high-level radioactive waste (HLW) stored at the Idaho National Laboratory (INL) will eventually be immobilised in a suitable wasteform before disposal. A tailored glass-ceramic wasteform, produced by hot isostatic pressing in stainless steel (SS) cans, has been developed at ANSTO as a cost-saving alternative to glass which would improve waste loading and density, and reduce waste volume. We have studied the SS/wasteform interactions under HIPing conditions to understand whether such interactions would have any detrimental effect on long-term wasteform stability. This has been demonstrated by carrying out aqueous durability tests, under near-neutral and alkaline conditions, on the wasteform at the interaction layer, and on the wasteform distal to this reaction edge. Reaction during HIPing resulted in Cr diffusion from the can wall into the wasteform, however without any detectable detrimental impact on the HIP can or the aqueous durability of the wasteform.

Keywords

ceramichot isostatic pressing (HIP)surface reaction
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 985: Symposium NN – Scientific Basis for Nuclear Waste Management XXX , 2006 , 0985-NN04-07
Copyright
Copyright © Materials Research Society 2007

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References

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