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Characterization of Highly Active Waste Glasses Produced in a Hot Vitrification Pilot Plant

Published online by Cambridge University Press:  21 February 2011

C. Cantale ,
J-P. Glatz ,
E.H. Toscano ,
A. Donato ,
M. Coquerelle  and
J. Fuger
C. Cantale
Affiliation:
ENEA-Casaccia, Fuel Cycle Division, 00060-S.M. di Galeria, Rome, Italy
J-P. Glatz
Affiliation:
Commission of the European Communities, Joint Research Centre Karlsruhe, European Institute for Transuranium Elements, P.O. Box 2340, 7500-Karlsruhe, Federal Republic of, Germany
E.H. Toscano
Affiliation:
Commission of the European Communities, Joint Research Centre Karlsruhe, European Institute for Transuranium Elements, P.O. Box 2340, 7500-Karlsruhe, Federal Republic of, Germany
A. Donato
Affiliation:
ENEA-Casaccia, Fuel Cycle Division, 00060-S.M. di Galeria, Rome, Italy
M. Coquerelle
Affiliation:
Commission of the European Communities, Joint Research Centre Karlsruhe, European Institute for Transuranium Elements, P.O. Box 2340, 7500-Karlsruhe, Federal Republic of, Germany
J. Fuger
Affiliation:
Commission of the European Communities, Joint Research Centre Karlsruhe, European Institute for Transuranium Elements, P.O. Box 2340, 7500-Karlsruhe, Federal Republic of, Germany
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Abstract

Fully radioactive waste glasses produced in a hot vitrification pilot plant were characterized in the hot cells at the JRC-Karlsruhe. The work includes microstructural analysis before and after leaching by SOXHLET extractors (MCC-5S), as well as leachate and gel-layer chemical analysis. Partial devitrification, with phases enriched in metals and rare earths, was observed in one of the products. In the gel layers formed during the dissolution tests, enrichment in some elements (Fe,Ti,Gd,Nd,Ce) and depletion in glass constituents (Si,B,K,Ba,Ca,Na) as well as in Mo and Cs, were determined. This was in good qualitative agreement with the leachate chemical analysis.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 403
Copyright
Copyright © Materials Research Society 1990

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References

REFERENCES

1. Miyahara, K., Ashida, T., Yusa, Y., Sasaki, N. and Tsunoda, N., Mat.Res. Soc. Symp. Proc. 27, 121 (1988).Google Scholar
2. Bjorner, Inga-Kari, Christensen, H., Hermansson, H.P., Tsukamoto, M. and Werme, L., Mat.Res.Soc.Symp.Proc. 27, 113 (1988).Google Scholar
3. Pacaud, F., Jacquet-Francillon, N., Terki, A. and Fillet, C., Mat.Res. Soc. Symp. Proc. 27, 105 (1988).Google Scholar
4.JSS-Technical Report 87–01, SKB (1987).Google Scholar
5. Strazzer, A., Cortesi, P., Colombo, G.C. and Nannicini, R., RTI COMBMEPIS SVITE (1986).Google Scholar
6. Materials Characterization Center, MCC-5S SOXHLET Leach Test Method, (1981).Google Scholar
7. Cantale, C., Donato, A. and Guidi, G., RT COMB 84 1, (1984).Google Scholar
8. Lutze, W., in Radiactive waste forms for the future, Ed. by Lutze, W. and Ewing, R.C., North-Holland, 1988, pp. 93 and 100.Google Scholar
9. Yokoyama, H., Hermansson, H.-P, Christensen, H., -Björner, I. and Werme, L., in Scientific Basis for Nuclear Waste Management, Vol.44, Ed. by Jantzen, C.M., Stone, J.A. and Ewing, R.C., Boston, 1984, p. 601.Google Scholar
10. Vay, G.L. Mc and Pederson, L.R., J. Am. Ceram. Soc. 64 (1981) 154.Google Scholar