METHOD OF SEPARATING MOLYBDENUM-99 FROM FUEL OF A SOLUTION REACTOR AND DEVICE FOR ITS IMPLEMENTATION Russian patent published in 2020 - IPC G21G4/08 G21G1/02 C01G39/00 B01D15/08 

FIELD: medicine; physics.

SUBSTANCE: invention relates to production of medical isotopes, in particular, Mo-99. Method involves feeding an irradiated solution containing iodine, molybdenum and other uranium fission products into the sorption column, passing the irradiated fuel solution from bottom to top through the sorption column, feeding the desorbing solution onto the sorption column, removing iodine from the obtained eluate and purifying the eluate. Irradiated solution is passed in portions through a sorption column with return of each portion into a reactor, after which residues of the irradiated solution are removed from the sorption column with distilled water. After removing iodine, the eluate is acidified and dried; the dried product undergoes fine purification from an acidic solution on an inorganic sorbent. Distilled water with residues of irradiated solution after washing of sorption column is returned to reactor. Device for separating molybdenum-99 from fuel of a solution reactor includes a sorption system comprising at least one sorption column, means for feeding into the sorption column an irradiated fuel solution containing iodine, molybdenum and other fission products, means for feeding into the sorption column a reagent for desorption of molybdenum, a means for removing iodine from the eluate obtained from the sorption column, and an agent for cleaning the eluate. Sorption system consists of at least two circuits and a means of moving the sorption column between these circuits. First circuit is intended for sorption of molybdenum, and the second circuit is intended for desorption of molybdenum, at the same time the sorption circuit is interconnected with the reactor, and the desorption circuit is interconnected with the agent for supply of reagent for desorption of molybdenum and the agent for removal of iodine from the eluate.

EFFECT: technical result is purity of final Mo-99 preparation, reduced time consumption for technological process and increased efficiency of installation, increased radiation safety.

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