FIELD: nuclear technology. SUBSTANCE: process is designed for processing of liquid high-activity waste formed by hydrometallurgical methods of regeneration of irradiated nuclear fuel. Vitrification of nonfractional liquid waste as well as of individual fractions is performed into borosilicate glass with high capacity for oxides of cesium-137 and strontium-90. For this boron carbide and amorphous silica which are difficult to solve in water and nitric acid and which do not have any ballast components are added to them. Then produced suspension is subjected to calcification followed by vitrification. EFFECT: enhanced efficiency of process, improved operational safety.
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