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Method of recovering uranium oxide from alcaline sodium uranyl carbonate solutions

Patent ·
OSTI ID:6482241
; ;
A method of recovering uranium dioxide from a sodium uranyl carbonate solution obtained by the alkaline carbonate leaching of uranium ore in which a solution is reacted at a temperature above 130/sup 0/ C. and at superatmospheric pressure with particular metallic iron. The precipitated UO/sub 2/ is recovered from the solution.
Assignee:
Metallgesellschaft Aktiengesellschaft, (Germany, Federal Republic of)
Patent Number(s):
US 4436704
OSTI ID:
6482241
Country of Publication:
United States
Language:
English

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Related Subjects

050300* -- Nuclear Fuels-- Mining-- (-1987)
050700 -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
ALKALI METAL COMPOUNDS
CARBON COMPOUNDS
CARBONATES
CHALCOGENIDES
ELEMENTS
FLUID FLOW
HEATING
HIGH TEMPERATURE
IRON
METALS
MINING
ORES
OXIDES
OXYGEN COMPOUNDS
PRECIPITATION
SEPARATION PROCESSES
SODIUM CARBONATES
SODIUM COMPOUNDS
SODIUM URANATES
SOLUTION MINING
TRANSITION ELEMENTS
TURBULENT FLOW
URANATES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM ORES
URANIUM OXIDES