Ultimate disposal of high-level atomic waste by incorporation in glass

Vitreous matrices for containment of standard radioactive wastes from CIRUS reactor, the Tarapur Atomic Power Station and the Rajasthan Atomic Power Station, have been developed and the chemical and physical properties have been evaluated. The non-standard CIRUS waste collected at the initial period may be accommodated in these compositions or a separate work may be needed for accommodating the high percentage of alpha active material in such wastes. The studies on glass compositions have been done in such a way that the diagrams may be useful for incorporating Purex wastes generated in all countries. (author)