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The main prerequisites for creating and developing industrial radiochemical production in the USSR and the Russian Federation is reviewed. The history of spent nuclear fuel (SNF) management in relation to the RT-1 and RT-2 plants, the features and tasks of the plants are considered from the position of today. Current specifics of the platforms of the Mayak Production Association, the Mining and Chemical Complex and the Siberian Chemical Combine of the closed nuclear fuel cycle of the Russian Federation was analyzed. Topical issues are formulated on SNF reprocessing and radioactive waste management technologies.

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Abstract. The technological flowchart of purification of medium-and low-activity waste from Co-60 and Cs-137 is developed and introduced. The developed purification scheme has been successfully tested using genuine medium-and low-level liquid radioactive waste of radiochemical production containing complexing and colloid forming components (complexons, surfactants). The optimal conditions of the presented method of purification ensure reduction of the residual specific activity of 60Co and 137Cs radionuclides in the solution to less than 0,9 Bq per litre.