THE SEPARATION OF PLUTONIUM FROM URANIUM

Patent · Wed Feb 28 04:00:00 EST 1962

OSTI ID:4810629

A process for the separation of Pu from irradiated U is given which is a modification of the tributyl phosphate extraction-stripping procedure. Tributyl phosphate (TBP) decomposes by hydrolysis and radiolysis to form dibutyl phosphate (DBP) which complexes Pu and makes stripping difficult. The modification consists of regulating the flow rate of the solvent extractant and the stripping solution and/or the time of contact between them so that insoluble a raised dot goes here)2TBP by reaction with UO/sub 2/(NO/sub 3/)/sub 2/(Faye a raised dot goes here)2TBP. When the concentration of the DBP complex in the solvent extractant phase exceeds 0.01 vol%, it is also necessary to hold up the fiow - for a period of time to permit conversion of the DBP cormplex into the TBP complex. Ferrous ions or hydroxylamine nitrate may be used in the stripping solution to reduce Pu/sup 4+/ to Pu/sup 3+/ to improve the stripping, but in the former case non-aliphatic hydrocarbon diluents must be used as the TBP solvent. (D.L.C.)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-16-010117
• OSTI ID: 4810629
• Report Number(s): GB 890410
• Country of Publication: United Kingdom
• Language: English

Related Subjects

AMINES
BUTYL PHOSPHATES
CHEMISTRY
COMPLEXES
DECOMPOSITION
FLUID FLOW
HYDROLYSIS
IONIZATION
IONS
IRON
NITRATES
PATENT
PLUTONIUM
RADIATION CHEMISTRY
RADIOLYSIS
REDUCTION
SEPARATION PROCESSES
SOLUTIONS
SOLVENT EXTRACTION
STRIPPING
URANIUM
URANIUM OXIDES