New grades of inorganic sorbents based on natural materials and artificial materials (thermoxide sorbents) suitable for extraction of Cs-137 from liquid radioactive waste have been developed. The technology of selective extraction of Mo-99 from spent nuclear fuel for scientific and medical purposes using inorganic sorbents, previously developed by the Department of Radiochemistry of UGTU, has been optimized. Ag-sorbents based on thermoxide-5 carrier were developed and optimal conditions of I-131 extraction by these sorbents from aqueous solutions were determined. The technology of Mo-99 production was supplemented with a new stage of I-131 extraction from alkaline concentrate Mo-99 after desorption operation.
The technology of selective extraction of molybdenum-99 from nuclear fuel waste for scientific and medical purposes with the use of inorganic sorbents has been developed. Inorganic sorbents based on titanium and zirconium hydroxides with anion-exchange properties were synthesized, their radiation stability and sorption properties with respect to uranium and molybdenum in sulfuric acid solutions were studied. In order to obtain Mo-99 concentrate of required radionuclide purity the sorption behavior of uranium and iodine in the process of Mo-99 extraction from solution fuel was studied. Work on synthesis and study of properties of sorbents based on natural aluminosilicates suitable for decontamination of liquid radioactive waste was continued.
