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

Patent ·
OSTI ID:6656147
;

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 Lab., TN (USA)
DOE Contract Number:
AC05-84OR21400
Assignee:
Dept. of Energy
Patent Number(s):
PATENTS-US-A6018550
Application Number:
ON: DE89000096
OSTI ID:
6656147
Country of Publication:
United States
Language:
English

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Related Subjects

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