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Ion exchange resins of high loading capacity, high chloride tolerance and rapid elution for uranium recovery

Patent ·
OSTI ID:5750632
Ion exchange process for the recovery of uranium from a pregnant carbonate lixiviant employed in uranium leaching operations in which the lixiviant is passed over a precipitation inducing anionic ion exchange resin under conditions to load the resin predominantly with non-exchangeable uranium. Non-exchangeable uranium is then recovered from the resin by eluting the resin with an aqueous acid solution having a pH no greater than 2. The process is useful in those applications in which the lixiviant contains chloride ions which inhibit the adsorption of uranyl ions.
Assignee:
Mobil Corp
Patent Number(s):
US 4312838
OSTI ID:
5750632
Country of Publication:
United States
Language:
English

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Related Subjects

050400* -- Nuclear Fuels-- Feed Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
AQUEOUS SOLUTIONS
CARBON COMPOUNDS
CARBONATES
DISPERSIONS
DISSOLUTION
ELEMENTS
ION EXCHANGE
LEACHING
METALS
MIXTURES
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
PH VALUE
POLYMERS
RECOVERY
RESINS
SEPARATION PROCESSES
SOLUTIONS
URANIUM