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Title: IMPROVEMENTS IN AND RELATING TO URANIUM EXTRACTION PROCESSES

Patent ·
OSTI ID:4144733

A method is outlined for separating uranium from leach alkali carbonate solutions obtained from uranium ores. e.g.. shales. The method consists of the following steps: (1) ozone is passed into the solution at 20 C for 10 to 15 min. and the solution is filtered with powdered filtering aids: (2) the solution, pH 9.5 to 11.5. is introduced into a basic anion exchange column of the quaternary ammonium type, e.g.. Amberlite IRA 410. the uranium being fixed in the form of a tetravalent uranyl carbonate complex: (3) when the column is saturated with uranium. the uranium is eluted with an aqueous solution of NaCl or NaNO/sub 3/. the eluant is acidified. and CaCl/sub 2/ or Ca(NO/sub 3/)/sub 2/ is added to precipitate insoluble calcium salts: (4) after filtration and adjustment to a uranium content of 40 to 80 g/l and an acidity of 0.1 N. the uranium is extracted with an immiscible solvent. e.g.. a mixture of paraffin and tributyl phosphate: and (5) the uranium extract is washed with water to form an aqueous solution of uranyl chloride or nitrate, which may be concentrated by evaporation to give the final solution The ozone used in (1) serves the dual purpose of oxidizing impurities and coagulating colloidal particles. The eluant from (2) is recycled for use in leaching uranium ore, and the aqueous phase from (4) is recycled as the eluant for eluting uranium as in (3). (D.L.C.)

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-14-024213
OSTI ID:
4144733
Report Number(s):
GB 845842
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United Kingdom
Language:
English