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Separation of uranium from technetium in recovery of spent nuclear fuel

Patent ·
OSTI ID:6982353
;

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.

DOE Contract Number:
AC05-84OR21400
Assignee:
Dept. of Energy
Patent Number(s):
None
Application Number:
ON: DE84011306
OSTI ID:
6982353
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
BUTYL PHOSPHATES
ELEMENTS
ENERGY SOURCES
ESTERS
EXTRACTION
FUELS
MATERIALS
METALS
NUCLEAR FUELS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
PUREX PROCESS
REACTOR MATERIALS
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
SPENT FUELS
TBP
TECHNETIUM
TRANSITION ELEMENTS
URANIUM