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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

REFERENCES

[1] Lanza, F. and Ronsecco, C., in Scientific Basis for Radioactive Waste Management, Vol. V. Edited by Lutze, W., Plenum, New York, 1982, pp. 125–134.Google Scholar
[2] Iseghem, P. Van, Timmermans, W. and Batist, R. De, in Scientific Basis for Radioactive Waste Management, Vol. V. Edited by Lutze, W., Plenum, New York, 1982, pp. 219–227.Google Scholar
[3] Christensen, H., Hermansson, H.P., Clark, D.E. and Werme, L., in Advances in Ceramics 8, edited by Wicks, G. and Ross, W.. Am. Ceram. Soc. 1984, pp. 346–357.Google Scholar
[4] Godon, N., Vernaz, E., Thomassin, J.H. and Touray, J.C., in Scientific Basis for Nuclear Waste Management XII, Mat. Res. Soc. Symp. Proc. Vol. 127, edited by Lutze, W. and Ewing, R.C., Materials Research Society, Pittsburgh, 1989, pp. 97–104.Google Scholar
[5] Iseghem, P. Van, Batist, R. De and Wei-Yin, Li, in Advances in Ceramics, Vol. 20: Nuclear Waste Management II, edited by Clark, D.E., White, W.B. and Machiels, A.J.. Am. Ceram. Soc., 1986, pp. 627–637.Google Scholar
[6] Characterization of radioactive waste forms, Vol. 2, Progress Report for 1987, EUR 12077 (1989).Google Scholar
[7] Mertens, L.A., Lutze, W., Marples, J.A.C., Iseghem, P. Van and Vernaz, E., this conference.Google Scholar
[8] Henrion, P., Ilonsecour, M., and Fonteyne, A., “Application of Sorption Data to the Evaluation of Radioelement Migration in the Boom Clay Formation”, presented at the CEC scientific seminar on the Application of Distribution Coefficients to Radiological Assessment Models, Louvain-la-Neuve (Belgium), October 1985.Google Scholar
[9] Evaluation of conditioned waste and qualification of engineered barriers. Annual Progress Report 1988. EUR 12141 (1989).Google Scholar
[10] Lanza, F. and Saltelli, A., in Scientific Basis for Nuclear Waste Management VII, edited by Vay, G.Mc. Mat. Res. Soc. Symp. Vol. 26 (1984). Elsevier Science Publishing, pp. 605–612.Google Scholar
[11] Iseghem, P. Van and Batist, R. De, Riv. della Staz. Sperim. del Vetro nr. 5, 1984, pp. 163–170.Google Scholar
[12] Iseghem, P. Van and Grambow, B., in Scientific Basis for Nuclear Waste Management XI, Mat. Res. Soc. Symp. Proc. Vol. 112, edited by Apted, M.J. and Westerman, R.E.. Materials Research Society, Pittsburgh, 1988, pp. 631–639.Google Scholar
[13] Henrion, P., Monsecour, M., Fonteyne, A., Put, M. and Regge, P. De, in Rad. Waste Manag. and the Nucl. Fuel Cycle, Vol. 6, nrs 3-4 (1985), pp. 313–360.Google Scholar
[14] Marples, J.A.C., Lutze, W., Kawanishi, M. and Iseghem, P. Van, this conference.Google Scholar
[15] Pederson, L.R. and Vay, G.L. Mc., in J. Am. Cer. Soc., Vol. 66, no. 12 (1983), pp. 863–867.Google Scholar