ИСТИНА

A new electrochemical method for extracting technetium from solutions of radioactive waste and SNF is proposed. The electrolyte proposed for the electrochemical extraction of technetium makes it possible to selectively isolate from the technetium solution a highly oxidized state. Depending on the current density from the SNF and RW solutions, it is possible to isolate molybdenum in the form of metal oxide coatings. Such an approach should reduce the amount of waste to be disposed of.Radiochemical reprocessing of spent nuclear fuel (SNF) includes dozens of technologies for processing both introduced into the industry and passing laboratory tests. They meet all safety requirements, give a high degree of separation of the target radionuclides contained in SNF and assume the disposal of radioactive waste (RW) in various forms. Industrially implemented processes of water-chemical SNF processing usually include dissolving the opened fuel in nitric acid and further purification by extracting TBP in hydrocarbon diluents. Purification is focused primarily on the separation of uranium and plutonium. For some fission products (PD), including 99Tc, separation methods have been developed, the improvement of which can make it a valuable product. After the extraction of U and Pu, the washing solutions contain tangible amounts of technetium, usually in a highly oxidized state. They are still connected with the first cycle of raffinate and sent for residue, vitrification and disposal. It is also possible to prepare targets for further transmutation. Trace amounts of technetium compounds are found even in purified oxides of uranium and plutonium. Technetium is a problem PD in the reprocessing of spent nuclear fuel, accumulating with an output of ≈ 6%. Methods of extracting it from solutions usually extraction or precipitation, electrochemically from the formed acid solutions of technetium is poorly isolated.