Abstract
The production of the radiopharmaceutical “Sodium pertechnetate 99mTc, solution for injection” from the transported 99mTc generator is a complex multi-stage process that includes the collection and disposal of radioactive waste generated at various technological stages of production, as well as after the return of the generator used in clinics. Currently, natural molybdenum oxide is used for the development of the parent isotope 99Mo at the WWR-K reactor, but as the need for 99mTc generators in Kazakhstan increases, the question arises about the use of expensive molybdenum oxide enriched with the isotope 98Mo, therefore, the task of regenerating irradiated molybdenum arises. The paper presents experimental data on the choice of an optimal leaching system for the isolation of molybdenum-98 from spent 99Mo/99mTc generators.
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