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Separation of uranium from technetium in recovery of spent nuclear fuel

Patent ·
OSTI ID:6206499
;

Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc/sup +7/ therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.

Assignee:
Dept. of Energy
Patent Number(s):
US 4443413
OSTI ID:
6206499
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
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105 -- Separation Procedures
ACTINIDES
AQUEOUS SOLUTIONS
DEMETALLIZATION
DISPERSIONS
ELEMENTS
ENERGY SOURCES
EXTRACTION
FUEL ELEMENTS
FUELS
HYDRAZINE
MATERIALS
METALS
MIXTURES
NITROGEN COMPOUNDS
NUCLEAR FUELS
OXYGEN COMPOUNDS
PHOSPHATES
PHOSPHORUS COMPOUNDS
PUREX PROCESS
REACTOR COMPONENTS
REACTOR MATERIALS
REPROCESSING
SEPARATION PROCESSES
SOLUTIONS
SOLVENT EXTRACTION
SPENT FUELS
TECHNETIUM
TRANSITION ELEMENTS
URANIUM