Process for recovering uranium from spent shale

Details Process for recovering uranium from spent shale Process for recovering uranium from spent shale

1983-04-07

1985-04-30

Miller, Edward A.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

423 20, C01G 4300

Patent

active

045143781

ABSTRACT:
A process for the recovery of uranium from spent shale by treating the spent shale with a compound selected from the group consisting of methanol, a mixture of methanol and water, and a mixture of methanol and sodium methoxide at between about 240.degree. and 450.degree. C. and atmospheric pressure or higher. The treated spent shale is then leached with an aqueous acid solution such as hydrochloric acid, sulfuric acid, or nitric acid to remove 90% of the uranium from the spent shale and the leached uranium is recovered from the acid solution in a manner known per se.

REFERENCES:
patent: 4120934 (1978-10-01), Mioen
patent: 4374096 (1983-02-01), Skeaff et al.

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