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Burial Effects on Nuclear Waste Glass

Published online by Cambridge University Press:  15 February 2011

Larry L. Hench ,
Lars Werme  and
Alexander Lodding
Larry L. Hench
Affiliation:
Department of Materials Science and Engineering, University of Florida, Gainesville, Florida, USA
Lars Werme
Affiliation:
SKBF/KBS, Stockholm, Sweden
Alexander Lodding
Affiliation:
Chalmers University of Technology, Gothenburg, Sweden
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Extract

The purpose of this experiment was to evaluate the effects of various components of the SKBF/KBS nuclear waste storage system on the leaching of the vitreous waste form. Two cohfigurations of nuclear waste glasses, canisters, overpacks, and backfill mate-7ial were inserted into 5.6 cm x 3 m deep boreholes located at the 350 m level in the STRIPA mine. Some were maintained at 90°C. The others were allowed to equilibrate at the ambient temperature of the mine, approximately 8°C. Two borosilicate nuclear waste glass compositions (termed ABS 39 and ABS 41) compatible with the French AVM process containing 9 percent by weight of simulated fission products were compared. The two compositions ( Table 1) bracket the range of Si02/Na2O/B203 ratios likely to be selected for commercial vitrification operations at La Hague.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 11: Symposium – Scientific Basis for Nuclear Waste Management V , 1981 , 153
Copyright
Copyright © Materials Research Society 1982

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References

REFERENCES

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