Method of selective stripping of plutonium from organic solvents loaded with plutonium

Patent · Tue Sep 21 00:00:00 EDT 1976

OSTI ID:7143804

Bathellier, A; Germain, M

The method of selective stripping from plutonium-loaded organic solvents which may also contain uranium consists in passing the organic solvent in countercurrent contact with an aqueous solution of a salt of hydroxylamine and formic acid, the concentration of formic acid in the reaction medium being within the range of 1M to 5M. The method finds an application in the stripping of plutonium from trilaurylamine diluted in an aromatic hydrocarbon such as tert-butyl benzene or in the separation of uranium and plutonium contained in tributylphosphate diluted in an aliphatic hydrocarbon such as dodecane.

• Assignee: Commissariat a l'Energie Atomique
• Patent Number(s): US 3981961
• Application Number: TRN: 77-000030
• OSTI ID: 7143804
• Resource Relation: Patent Priority Date: Priority date 28 Dec 1972, France
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
PLUTONIUM
SOLVENT EXTRACTION
SPENT FUELS
REPROCESSING
AQUEOUS SOLUTIONS
DODECANE
FORMIC ACID
HYDROXYLAMINE
ORGANIC SOLVENTS
TBP
TRILAURYLAMINE
URANIUM
ACTINIDES
ALKANES
AMINES
BUTYL PHOSPHATES
CARBOXYLIC ACIDS
DISPERSIONS
ELEMENTS
ENERGY SOURCES
ESTERS
EXTRACTION
FUELS
HYDROCARBONS
METALS
MIXTURES
MONOCARBOXYLIC ACIDS
NUCLEAR FUELS
ORGANIC ACIDS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
REACTOR MATERIALS
SEPARATION PROCESSES
SOLUTIONS
SOLVENTS
TRANSURANIUM ELEMENTS
050800* - Nuclear Fuels- Spent Fuels Reprocessing