Separation of uranium from technetium in recovery of spent nuclear fuel

Patent · Wed Aug 31 00:00:00 EDT 1983

OSTI ID:6982353

Pruett, D J; McTaggart, D R

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
• Application Number: ON: DE84011306
• OSTI ID: 6982353
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
TECHNETIUM
SEPARATION PROCESSES
URANIUM
SOLVENT EXTRACTION
PUREX PROCESS
SPENT FUELS
TBP
ACTINIDES
BUTYL PHOSPHATES
ELEMENTS
ENERGY SOURCES
ESTERS
EXTRACTION
FUELS
MATERIALS
METALS
NUCLEAR FUELS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
REACTOR MATERIALS
REPROCESSING
TRANSITION ELEMENTS
050800* - Nuclear Fuels- Spent Fuels Reprocessing
400105 - Separation Procedures