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The Interaction Between Nuclear Waste Glasses and Clay-II

Published online by Cambridge University Press:  21 February 2011

P. Van Iseghem ,
K. Berghman  and
W. Timmermans
P. Van Iseghem
Affiliation:
SCK/CEN, Boeretang 200, B-2400 Mol, Belgium
K. Berghman
Affiliation:
SCK/CEN, Boeretang 200, B-2400 Mol, Belgium
W. Timmermans
Affiliation:
SCK/CEN, Boeretang 200, B-2400 Mol, Belgium
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Abstract

The interaction between simulated HLW glasses and clay has been investigated, as part of a larger programme to evaluate the performance of vitrified HLW in repository conditions. Experimental conditions were carefully chosen to simulate repository conditions as close as possible. The glass corrosion seems to be controlled by a diffusion process, but there are indications of a (small) final corrosion rate. The leaching of 134Cs, 90Sr, 239Pu and 241Am is characterized by extremely small mobile concentrations leached (for 239pu and 241Am, below detection limit). The presence of a gamma irradiation field does not increase the glass dissolution. The production of radiolythic hydrogen is strongly reduced by the presence of clay.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 291
Copyright
Copyright © Materials Research Society 1990

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References

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