Sorption Extraction of Uranium from Fluorine-Containing Media During Reprocessing of Radiochemical Production Wastes

Experimental data on the sorption extraction of uranium from fluorine-containing solutions on different types of modern ion-exchange absorbers and structures in order to improve the technological schemes for reprocessing wastes from radiochemical production are presented. The primary technological relations are studied and the optimal indices in static and dynamic regimes of sorption-desorption extraction of uranium from model systems simulating production fluorine-containing solutions are determined. A chelate-forming aminophosphonic cation-exchanger Purolite S950 with uranium capacity up to 20% is recommended. It is shown that uranium concentration in the waste ≤0.003 g/liter can be obtained. It is found that uranium desorption by a 15% solution of sodium carbonate is a highly efficient process with desorption time 10 h and degree of uranium desorption 99.92%.