Method of separating and recovering uranium and related cations from spent Purex-type systems

Patent · Wed Feb 25 00:00:00 EST 1987

OSTI ID:6656147

Mailen, J C; Tallent, O K

A process for separating uranium and related cations from a spent Purex-type solvent extraction system which contains degradation complexes of tributylphosphate wherein the system is subjected to an ion-exchange process prior to a sodium carbonate scrubbing step. A further embodiment comprises recovery of the separated uranium and related cations. 5 figs.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: AC05-84OR21400
• Assignee: Dept. of Energy
• Patent Number(s): PATENTS-US-A6018550
• Application Number: ON: DE89000096
• OSTI ID: 6656147
• Resource Relation: Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
CATIONS
SEPARATION PROCESSES
URANIUM
INVENTIONS
PUREX PROCESS
RECOVERY
REPROCESSING
SCRUBBING
SODIUM CARBONATES
SOLVENT EXTRACTION
SPENT FUELS
ACTINIDES
ALKALI METAL COMPOUNDS
CARBON COMPOUNDS
CARBONATES
CHARGED PARTICLES
ELEMENTS
ENERGY SOURCES
EXTRACTION
FUELS
IONS
MATERIALS
METALS
NUCLEAR FUELS
OXYGEN COMPOUNDS
REACTOR MATERIALS
SODIUM COMPOUNDS
050800* - Nuclear Fuels- Spent Fuels Reprocessing