Combined vitrification of chloride and phosphate wastes by pyroelectrochemical reprocessing of nuclear fuel

The results of an investigation of the combined vitrification of chloride and phosphate wastes, which were obtained as a result of experimental reprocessing of irradiated nuclear fuel by the pyroelectrochemical method, are presented. The optimal composition of the glass matrix is determined, the cha...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2006-12, Vol.101 (6), p.894-896
Hauptverfasser: Lavrinovich, Yu. G., Kuzin, M. A., Kormilitsyn, M. V., Tomilin, S. V., Gribakin, E. Yu, Zakharova, L. V.
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Sprache:eng
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Zusammenfassung:The results of an investigation of the combined vitrification of chloride and phosphate wastes, which were obtained as a result of experimental reprocessing of irradiated nuclear fuel by the pyroelectrochemical method, are presented. The optimal composition of the glass matrix is determined, the characteristics of the model and real samples obtained are presented, and the hydrolytic stability and the thermal stability of the samples are studied. The proposed method of combined vitrification makes it possible to salvage more than 1.5 times more wastes per unit mass of the glass block than separate vitrification.[PUBLICATION ABSTRACT]
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-006-0187-0