Solvent wash solution

Patent · Tue Jun 17 04:00:00 EDT 1986

OSTI ID:5668280

Neace, J C

This patent describes a process for removing diluent degradation products from a solvent extraction solution comprising an admixture of an organic extractant for uranium and plutonium and a non-polar organic liquid diluent, which has been used to recover uranium and plutonium from spent nuclear fuel. Comprising combining a wash solution consisting of: (a) water; and (b) a positive amount up to about, an including, 50 volume percent of at least one highly-polar water-miscible organic solvent, based on the total volume of the water and the highly-polar organic solvent, with the solvent extraction solution after uranium and plutonium values have been stripped from the solvent extraction solution, the diluent degradation products dissolving in the highly-polar organic solvent and the extractant and diluent of the extraction solution not dissolving in the highly-polar organic solvent, and separating the highly-polar organic solvent and the extraction solution to obtain a purified extraction solution.

• Assignee: Dept. of Energy, Washington, DC
• Patent Number(s): US 4595529
• OSTI ID: 5668280
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
DISPERSIONS
DISSOLUTION
ELEMENTS
ENERGY SOURCES
EXTRACTION
FUELS
HYDROGEN COMPOUNDS
MATERIALS
METALS
MIXTURES
NUCLEAR FUELS
ORGANIC SOLVENTS
OXYGEN COMPOUNDS
PLUTONIUM
QUANTITY RATIO
REACTOR MATERIALS
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
SOLVENTS
SPENT FUELS
TRANSURANIUM ELEMENTS
URANIUM
WATER