Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange
Patent
·
OSTI ID:6325158
A process is described for recovering uranium from a pregnant lixiviant containing uranium values and a certain portion of molybdenum values comprising passing the pregnant lixiviant through an anion-exchange resin to capture the uranium and molybdenum values on the resin, eluting the uranium and molybdenum values from the resin with a salt solution, passing the eluate through a weak acid cationic resin in its hydrogen form to capture the uranium values on the resin and treating and resulting eluate to precipitate uranium therefrom to produce the familiar ''yellow-cake.
- Assignee:
- Mobil Corp
- Patent Number(s):
- US 4375452
- OSTI ID:
- 6325158
- 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
ACTINIDE COMPOUNDS
ACTINIDES
CHALCOGENIDES
DISPERSIONS
ELEMENTS
ION EXCHANGE
LEACHATES
METALS
MINING
MIXTURES
MOLYBDENUM
ORE PROCESSING
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXIDES
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
PROCESSING
RECOVERY
RESINS
SOLUTION MINING
SOLUTIONS
TRANSITION ELEMENTS
URANIUM
URANIUM COMPOUNDS
URANIUM OXIDES
URANIUM OXIDES U3O8
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
ACTINIDES
CHALCOGENIDES
DISPERSIONS
ELEMENTS
ION EXCHANGE
LEACHATES
METALS
MINING
MIXTURES
MOLYBDENUM
ORE PROCESSING
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXIDES
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
PROCESSING
RECOVERY
RESINS
SOLUTION MINING
SOLUTIONS
TRANSITION ELEMENTS
URANIUM
URANIUM COMPOUNDS
URANIUM OXIDES
URANIUM OXIDES U3O8