Separation of uranium from technetium in recovery of spent nuclear fuel

Patent · Tue Jul 09 00:00:00 EDT 1985

OSTI ID:6141476

Friedman, H A

A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO2S+) uranium and heptavalent technetium (TcO4-). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H2C2O4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.

• Assignee: Dept. of Energy
• Patent Number(s): US 4528165
• OSTI ID: 6141476
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
ACTINIDES
ADDITIVES
ALKANES
AQUEOUS SOLUTIONS
CARBOXYLIC ACIDS
CHALCOGENIDES
CHEMICAL REACTIONS
DICARBOXYLIC ACIDS
DISPERSIONS
DODECANE
ELEMENTS
ENERGY SOURCES
EXTRACTION
FUELS
HYDRAZINE
HYDROCARBONS
MATERIALS
METALS
MIXTURES
NITRATES
NITROGEN COMPOUNDS
NUCLEAR FUELS
ORGANIC ACIDS
ORGANIC COMPOUNDS
OXALIC ACID
OXIDES
OXYGEN COMPOUNDS
PHOSPHATES
PHOSPHORUS COMPOUNDS
PUREX PROCESS
REACTOR MATERIALS
RECOVERY
REDUCTION
REFRACTORY METAL COMPOUNDS
REPROCESSING
SEPARATION PROCESSES
SOLUTIONS
SOLVENT EXTRACTION
SPENT FUELS
TECHNETIUM
TECHNETIUM COMPOUNDS
TECHNETIUM OXIDES
TRANSITION ELEMENT COMPOUNDS
TRANSITION ELEMENTS
URANIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
URANYL COMPOUNDS
URANYL NITRATES