Method of reducing radioactive waste and of recovering uranium f

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

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75103, 75121, 2523011W, 423 2, 423 11, 423 16, 423 17, G21F 930

Patent

active

042658616

ABSTRACT:
A method is described for reducing the volume of radioactive waste produced during the solution mining of uranium and for recovering uranium from it. The recovery leach, which contains uranium in solution and is supersaturated with calcium carbonate, is treated with bicarbonate and made basic which precipitates calcium carbonate and some of the uranium. The precipitated calcium carbonate is dissolved with acid and the uranium in the solution is removed by extraction or precipitation. The remaining solution is contacted with sulfate ions and barium or strontium ions to precipitate BaSO.sub.4.RaSO.sub.4 or SrSO.sub.4.RaSO.sub.4, the principal radioactive constituent in the solid waste product.

REFERENCES:
patent: 2812232 (1957-11-01), Delaplaine
patent: 3086841 (1963-04-01), Hart et al.
patent: 3792903 (1974-02-01), Rhoades
patent: 4054320 (1977-10-01), Learmont
Merritt, R. C., The Extractive Metallurgy of Uranium, Colo. School of Mines, Research Institute (1971) pp. 247, 248, 304-306.

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