Vitrification of sulphate- and chloride-containing radioactive wastes in an electric furnace

Results of vitrification of medium-level activity radioactive wastes (RW) with up to 16% sulfate ions and 10% chloride ions are presented. The mixture was carried to electric furnace as 20-25% hymidity paste. The glass melt temperature is 1150 deg C. Bitumen was used as reducing agent. On the basis of data on radionuclide distribution between glass melt and lye it is stated that 40-50% of carried RW radionuclides passes into lye. Thus, vitrification of sulfate- and chloride-containing RW is inefficient. Conclusion on necessity of development of special sulfate-containing glasses for RW immobilization is made