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Comparative Study of Seven Glasses for Solidification of Nuclear Wastes

Published online by Cambridge University Press:  15 February 2011

J. L. Nogues ,
L. L. Hench  and
J. Zarzycki
J. L. Nogues
Affiliation:
Laboratoire des Verres-Universite des Sciences et Techniques du Languedoc, 34060 Montpellier Cedex (France);
L. L. Hench
Affiliation:
Ceramics Division, Department of Materials Science and Engineering, University of Florida, Gainesville, Florida, USA
J. Zarzycki
Affiliation:
Laboratoire des Verres-Universite des Sciences et Techniques du Languedoc, 34060 Montpellier Cedex (France);
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Extract

The relative leaching behavior of seven alkali borosilicate glasses considered for immobilization of high level radioactive wastes was compared using a static 90°C leach test similar to MCC-l. All compositions (Table I) were compatible with the low melting temperature, 1150*C, viscosity and other process variables required for the French AVM process. The quantity of simulated waste products was from 10.9-15.9 weight %.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 11: Symposium – Scientific Basis for Nuclear Waste Management V , 1981 , 211
Copyright
Copyright © Materials Research Society 1982

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References

REFERENCES

1. MCC-l Static Leach Test (1980) Materials Characterization Center, Battelle Pacific Northwest Laboratory, Richland, Washington.Google Scholar
2. Sanders, D. M. Person, W. B. and Hench, L. L. (1972) Appl. Spectroscopy, 26, 530–536.CrossRefGoogle Scholar
3. Clark, D. E. Pantano, C. G. and Hench, L. L. (1972) in Glass Corrosion, Books for Industry, New York, New York. Google Scholar
4. Sanders, D. M. and Hench, L. L. (1973) J. Am. Ceram. Soc. 56, 373–377.CrossRefGoogle Scholar