Process for the elution of ion exchange resins in uranium recovery

Patent · Tue Jul 28 00:00:00 EDT 1981

OSTI ID:6041125

Yan, T

Process for the recovery of uranium from a pregnant lixiviant employed in uranium leaching operations in which the uranium is concentrated by ion exchange resin. The ion exchange resin is eluted with an eluant containing 0.05-0.5 molar ammonium carbonate. The eluant also contains a base such as ammonium hydroxide in an amount sufficient to increase the ph to a value within the range of 9.0-11.0, thus increasing the carbonate/bicarbonate ratio. This enables the use of a relatively small quantity of ammonium carbonate to provide the desired carbonate ion concentration during the elution step.

• Assignee: Mobil Corp
• Patent Number(s): US 4280985
• OSTI ID: 6041125
• Country of Publication: United States
• Language: English

Related Subjects

050400* -- Nuclear Fuels-- Feed Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105 -- Separation Procedures
ACTINIDES
ADSORPTION
AMMONIUM CARBONATES
AMMONIUM COMPOUNDS
AMMONIUM HYDROXIDES
CARBON COMPOUNDS
CARBONATES
DISSOLUTION
ELEMENTS
HYDROGEN COMPOUNDS
HYDROXIDES
ION EXCHANGE
LEACHING
MANAGEMENT
MATERIALS RECOVERY
METALS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
PH VALUE
POLYMERS
PROCESSING
RECOVERY
RESINS
SEPARATION PROCESSES
SORPTION
URANIUM
WASTE MANAGEMENT
WASTE PROCESSING