Process for the stabilization of radioactive wastes
First Claim
1. In a process for the stabilization of radioactive wastes in a glass matrix, wherein a glass smelt enriched with the radioactive waste is solidified through cooling;
- the improvement comprising contacting a thinly-fluid glass smelt at a maximal temperature of 1200°
C. together with the radioactive waste within a final repository container prior to cooling thereof, with a solid viscosity- increasing oxide along at least the surface of the smelt for a period for an at least partial dissolution of the oxide in the smelt.
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Abstract
A process for the consolidation or stabilization of radioactive wastes in a glass matrix, wherein a glass smelt which has been enriched with the active material is solidified through cooling. The process is distinguished in that the maximally 1200° C. hot gas smelt with the active waste within the final respository container is brought into contact prior to its cooling, at least along its surface, with a solid viscosity-increasing oxide up to at least a partial dissolution thereof. Among such oxides are aluminum oxide and zirconium oxide, wherein unsintered aluminum oxide is preferred.
23 Citations
11 Claims
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1. In a process for the stabilization of radioactive wastes in a glass matrix, wherein a glass smelt enriched with the radioactive waste is solidified through cooling;
- the improvement comprising contacting a thinly-fluid glass smelt at a maximal temperature of 1200°
C. together with the radioactive waste within a final repository container prior to cooling thereof, with a solid viscosity- increasing oxide along at least the surface of the smelt for a period for an at least partial dissolution of the oxide in the smelt. - View Dependent Claims (2, 3, 4, 5, 6, 7, 8, 9, 10, 11)
- the improvement comprising contacting a thinly-fluid glass smelt at a maximal temperature of 1200°
Specification