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An Aluminumsilicate Ceramic Nuclear Waste Form

Published online by Cambridge University Press:  25 February 2011

A. Loida
A. Loida*
Affiliation:
Kernforschungszentrum Karlsruhe, Institut für Nukleare Entsorgungstechnik, P.O.Box 3640, D—7500 Karlsruhe, Federal Republic of Germany
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Abstract

Aluminum silicate based ceramics were studied as matrix materials for the immobilizationof real TRU—wastes, as well as simulated high-level and TRU—waste mixtures. As observed by XRD and electron microscopy, isolation of radionuclides is achieved either by encapsulation of radiophases by aluminumsilicate matrix phases and by incorporation into host phases in the matrix. TRU—leach rates were found to be on the order of 5*10–3 and 1*10–2 gm–2 d–1 at room temperature after one year in MgCl2 —rich salt solution. By doping the ceramic matrix with 20 weight percent PuO2 an accumulated α-dose of 8.33*109 Gy (1*1019 α-decays*g–1) was reached after 3 years. The microstructure and the lattice constants ofthe matrix phases were not affected by a-irradiation.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 257: Symposium – Scientific Basis for Nuclear Waste Management XV , 1991 , 219
Copyright
Copyright © Materials Research Society 1992

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References

REFERENCES

1. Pentinghaus, H., Proceedings of the American Nuclear Society International Meeting,Niagara Falls,NY, USA Sept.14-18,1986, edited by Pope, J.M. et al. , p.1166–1173 Google Scholar
2. Kelm, M., Pentinghaus, H., Oser, B., Chemische Vorgänge bei der Verglasung von HAWC, 7.Statusbericht des Projekts Wiederaufarbeitung und Abfallbehandlung des Kernforschungszentrums Karlsruhe,1988, p.367–391, KfK 4476Google Scholar
3. Ringwood, A.E., Kesson, S.E., Reeve, K.D., Levins, D.M., Ramm, E.J., in Radioactive Waste Forms for the Future, North Holland, Amsterdam, 1988, p.233 Google Scholar
4. Krause, H., RECOD 87, Paris, 1987 5. Loida, A. and Schubert, G., CEC-report EURI1030DE(1988), Brussels, LuxembourgGoogle Scholar
6. Hespe, E.D.,At.Energy Rev.,9, (1971), p.195fGoogle Scholar
7. Lutze, W., in Radioactive Waste Forms for the Future, North Holland, Amsterdam, 1988, p.72fGoogle Scholar
8. Vernaz, E., Loida, A., Malow, G., Marples, J.A.C., Matzke, Hj., in Radioactive Waste Management and Disposal, ed.by Cecille, L., Elsevier Applied Science, London and New York, 1991, p.302 f.Google Scholar