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The Effect of Gamma Radiation on the Dissolution of High-Level Waste Glass in Boom Clay

Published online by Cambridge University Press:  21 March 2011

K. Lemmens  and
P. Van Iseghem
K. Lemmens
Affiliation:
Waste and Disposal Department, SCK•CEN, Boeretang 200 B-2400 Mol, Belgium Email: [email protected]
P. Van Iseghem
Affiliation:
Waste and Disposal Department, SCK•CEN, Boeretang 200 B-2400 Mol, Belgium
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Abstract

The effect of γ-radiation on the dissolution of candidate high-level waste glasses was investigated in potential disposal environments at 90°C. The media consisted of mixtures of Boom Clay, bentonite clay and cement with clay water. During the experiments the pH of Boom Clay decreased, probably mainly by radiolytical oxidation of pyrite. The addition of bentonite, cement and glass buffered the pH decrease. Under radiation the glass mass losses decreased, whereas the leach rate of soluble elements was not influenced or appeared to increase. This is explained through the radiolytical acidification, and possibly by bubble formation in the glass.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 227
Copyright
Copyright © Materials Research Society 2001

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References

REFERENCES

1. Lajudie, A., Raynal, J., Petit, J.C., Toulhoat, P., in Glossary of Geology, edited by Gary, M., McAfee, R. Jr, and Wolf, C.L. (American Geological Instititute, Washington D.C., 1977).Google Scholar
2. Baeyens, B., Maes, A. , A. and Cremers, A., Radioactive Waste Management and the Nuclear Fuel Cycle 6 (3-4), 391–408 (1985).Google Scholar
3. Valcke, E., Sneyers, A., and Iseghem, P. Van in The effect of radiolytic degradation products of Eurobitum on the solubility and sorption of Pu and Am in Boom Clay, presented at the 2000 MRS Fall Meeting, Sydney, 2000 (unpublished).Google Scholar
4. Allen, O. A., The radiation chemistry of water and aqueous solutions (D. Van Nostrand Company, Inc., New Jersey,1961) pp. 142–172.Google Scholar
5. Sneyers, A., Labat, S., Iseghem, P. Van in Euradwaste 1999, Radioactive waste management strategies and issues, EUR 19143 EN, edited by Davies, C. (European Commission, Brussels, 2000), pp. 419–422.Google Scholar
6. Iseghem, Pierre Van, Valcke, Elie, Kursten, Bruno and Lodding, Alexander, “In situ testing of the chemical durability of vitrified high-level waste in a Boom Clay formation in Belgium: the effect of gamma radiation”, Proceedings of the 7th International Conference on Radioactive Waste Management and Environmental Remediation, ICEM'99 (ASME, 1999).Google Scholar
7. Andriambololona, Z., Godon, N., Vernaz, E., in Scientific Basis for Nuclear Waste Management XV, edited by Sombret, G., (Mater. Res. Soc. Symp. Proc. 257, 1992), pp.151–158.Google Scholar
8. Ewing, R.C., Weber, W.J. and Clinard, F.W. Jr, Progress in Nuclear Energy 29 (2), 63–127 (1995).Google Scholar
9. Pederson, L.R. and Vay, G.L. Mc., J. Am. Ceram. Soc. 66, 863 (1983).Google Scholar
10. McVay, G.L., Bradley, D.J., and Kircher, J.F., in Elemental Release from Glass and Spent Fuel, Pacific Northwest Laboratory Report ONWI-275 (1981).Google Scholar
11. Heuer, J.P., Gamma radiation of nuclear waste glasses., M.S. thesis (Department of Mechanical Engineering, University of California, Davis, 1987).Google Scholar