Hostname: page-component-8448b6f56d-m8qmq Total loading time: 0 Render date: 2024-04-17T22:23:43.223Z Has data issue: false hasContentIssue false
  • English
  • Français

In Situ Testing of Waste Glass in Clay

Published online by Cambridge University Press:  25 February 2011

Pierre Ph. Van Iseghem
Pierre Ph. Van Iseghem*
Affiliation:
Division of Waste Disposal, SCK/CEN, B-2400 Mol, Belgium
Get access

Abstract

The actual status of an in-situ test programme exposing different waste glass samples directly to Boom clay is reviewed. Corrosion test tubes have been retrieved after residence for 5 years at 16° C, 2 years at 90° C, and 5 years at 170° C. The corrosion is interpreted in terms of mass loss, surface analysis by SEM and profiling by EPMA and SIMS. At 16° C, glasses dissolve about 0.02 – 0.08 µm per year. At higher temperature dissolution is more than two orders of magnitude larger. A good agreement is obtained between the mass losses and the surface analyses. The advantages and limitations of the Belgian in-situ tests are compared with the conclusions of an international expert group.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 333: Symposium V – Scientific Basis for Nuclear Waste Management XVII , 1993 , 133
Copyright
Copyright © Materials Research Society 1994

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1 Manfroy, P., Heremans, R. and Bonne, A., in Proceedings Topical Meeting on High-Level Nuclear Waste Disposal, Publ. ANS, 1985, pp. 233–245.Google Scholar
2 Bonne, A., in Proceedings of the Workshop “In situ testing of radioactive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar
3 Casteels, F., Tas, H., Heremans, R., and Brabers, M., “Corrosion of Materials in a Clay Environment”. Proceedings of the International Seminar on Chemistry and Process Engineering for High-level, Liquid Waste Solidification, Jülich (Germany), 01–05 June 1981, Publ.: Jül-Conf-42 (vol. 2), June 1981, Ed. R. Odoj, E. Merz; ISSN 0344-5798.Google Scholar
4 Casteels, F., Dresselaers, J., Kelchtermans, J., De Batist, R., and Timmermans, W., “In Situ Testing and Corrosion Monitoring in a Geological Clay Formation”, pp. 277–288, EUR 9575, 1985.CrossRefGoogle Scholar
5 Van Iseghem, P., Labat, S. and Cornélls, B., in Proceedings of the Workshop “In situ testing of radioactive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar
6 Wicks, G. and Molecke, M.A., in Proceedings of the Workshop “In situ testing of radioactive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar
7 Cornélls, B. and Van Iseghem, P., in Proceedings of the Workshop “In situ testing of radioactive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar
8 Debruyn, W., Dresselaers, J., Vermeiren, Ph., Kelchtermans, J., and Tas, H., “Corrosion of container and infrastructure materials under clay repository conditions”, EUR 13667, 1991.Google Scholar
9 Van Iseghem, P., Timmermans, W., and Neerdael, B., in Scientific Basis for Nuclear Waste Management XIII, Mat. Res. Soc. Symp. Proc., Vol. 176, 1990, Mat. Res. Soc. Publ., pp. 283–289.CrossRefGoogle Scholar
10 Van Iseghem, P., Timmermans, W., Debruyn, W., Dresselaers, J., and Neerdael, B., in Advances in Ceramics, Vol. 20: Nuclear Waste Management II, Am. Cer. Soc. Ed., 1986, pp. 649–656.Google Scholar
11 Van Iseghem, P. and Hong, Chen, in Proceedings of the Workshop “In situ testing of radioactive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar
12 Van Iseghem, P. and Lemmens, K., in Geological Disposal of Spent Fuel and High Level and Alpha Bearing Wastes, IAEA-SM-326, 1993, pp. 209–223.Google Scholar
13 Lodding, A.R., Odelius, H. and Van Iseghem, P., in Proceedings of the Workshop “In situ testing of radioactive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar
14 Lodding, A.R., Clark, D.E. and Wicks, G.G., in Proceedings of the Workshop “In situ testing of radioactive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar
15 Werme, L.O., Odelius, H. and Lodding, A.R., in Proceedings of the Workshop “In situ testing of radioactive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar
16 Van Iseghem, P., De Batist, R. and Wei-Yin, Li, in Advances in Ceramics, vol. 20: Nuclear Waste ManagementII, Am. Cer. Soc. Ed., 1986, pp. 627–637.Google Scholar
17 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
18 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
19 Lutze, W. and Wicks, G.G., in Proceedings of the Workshop “In situ testing of radioac tive waste forms and engineered barriers”, Corsendonk (Belgium), 13–16 October 1992, Pre-print of EUR report.Google Scholar