Solvent wash solution

Patent · Tue Mar 13 04:00:00 EST 1984

OSTI ID:6196128

Neace, J C

A process is claimed for removing diluent degradation products from a solvent extraction solution, which has been used to recover uranium and plutonium from spent nuclear fuel. A wash solution and the solvent extraction solution are combined. The wash solution contains (a) water and (b) up to about, and including, 50 vol % of at least one-polar water-miscible organic solvent based on the total volume of the water and the highly-polar organic solvent. The wash solution also preferably contains at least one inorganic salt. The diluent degradation products dissolve in the highly-polar organic solvent and the organic solvent extraction solvent do not dissolve in the highly-polar organic solvent. The highly-polar organic solvent and the extraction solvent are separated.

• DOE Contract Number: AC09-83SR11036
• Assignee: Dept. of Energy
• Patent Number(s): None
• Application Number: ON: TI85006414
• OSTI ID: 6196128
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BUTYL PHOSPHATES
DISPERSIONS
ESTERS
MIXTURES
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
ORGANIC SOLVENTS
PHOSPHORIC ACID ESTERS
PROCESS SOLUTIONS
PUREX PROCESS
PURIFICATION
REPROCESSING
SEPARATION PROCESSES
SOLUTIONS
SOLVENTS
TBP