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R7T7 Nuclear Waste Glass Behavior in Moist Clay: Role of the Clay Mass/Glass Surface Area Ratio

Published online by Cambridge University Press:  21 February 2011

N. Godon
Affiliation:
CEN-Valrhô, SDHA, BP 171, 30205 Bagnols-sur-Cèze Cedex, France
E. Vernaz
Affiliation:
CEN-Valrhô, SDHA, BP 171, 30205 Bagnols-sur-Cèze Cedex, France
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Abstract

R7T7 glass alteration was investigated in the presence of various moist clays. In contact with smectite 4a, selected in France as a potential engineered barrier material, the glass was significantly corroded: after 6 months the glass corrosion rate was practically the same as the initial alteration rate in double-distilled water. Substantially lower alteration was observed in contact with bentonite 6 activated by sodium carbonate.

Smectite 4a consumes silicon released by glass corrosion, and thus retards the rise to high silicon concentrations in solution at which the glass corrosion rate diminishes. Glass can therefore in some cases be altered as much in moist clay as in water with high renewal rates. Other experiments with smaller quantities of smectite 4a showed that the phenomenon becomes less important in time: its duration is proportional to the ratio between the clay mass (C) and the glass surface area (SA). Comparing the results of studies at different C/SA ratios indicates that low glass corrosion rates are obtained more slowly at higher C/SA ratios.

Tests with 239Pu-doped R7T7 glass also showed that the radionuclide retention factor in the alteration film at the glass surface is only 6, compared with a factor of nearly 50 in double-distilled water.

Type
Research Article
Copyright
Copyright © Materials Research Society 1990

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References

REFERENCES

[1] Nogués, J.L., Vernaz, E., Jacquet-Francillon, N. and Pasquini, S., in Scientific Basis for Nuclear Waste Management (Mater. Res. Soc. Proc.) 44, 195204 (1984).Google Scholar
[2] Godon, N., Vernaz, E., Thomassin, J.H. and Touray, J.C., in Scientific Basisfor Nuclear Waste Management (Mater. Res. Soc. Proc.) 127, 97104 (1989).Google Scholar
[3] Coulon, H., Lajudie, A., Debrabant, P., Atabek, R., Jorda, M. and André-Jehan, R., in Scientific Basis for Nuclear Waste Management (Mater. Res. Soc. Proc.) 84, 813824 (1987).Google Scholar
[4] Foster, M.D., in Geochimica et Cosmochimica Acta 3, 143154 (1953).Google Scholar
[5] Fillet, S., PhD Thesis: University of Montpellier, France (1987).Google Scholar
[6] Tardy, Y., Duplay, J. and Fritz, B., SKB Technical Report 87-20.Google Scholar
[7] Godon, N., PhD Thesis: University of Orléans, France (1988).Google Scholar
[8] Siever, R. and Woodford, N., Geochimica et Cosmochimica Acta, 37, 18511880 (1973).Google Scholar
[9] Pusch, R. and Karnlanol, O., SKB Technical Report 88-26.Google Scholar
[10] Grambow, B. and Lutze, W., in Scientific Basis for Nuclear Waste Management (Mater. Res. Soc. Proc.) 112, 531541 (1988).Google Scholar
[11] Vernaz, E., Advocat, T. and Dussossoy, J.L., presented at the 4th International Symp on Ceramics in Nuclear Waste Management (91st Am. Ceram. Soc. Meeting, 1989).Google Scholar
[12] Advocat, T., Crovisier, J.L., Fritz, B. and Vernaz, E., in Scientific Basis for Nuclear Waste Management (this volume) (Mater. Res. Soc. Proc.).Google Scholar
[13] Godon, N., Mestre, J.P. and Vernaz, E., Semiannual Report to the CEC, Contract FI 1F-180 F.Google Scholar