Oxidation of Pu(III) by nitric acid in tri-n-butyl phosphate solutions. Part II. Chemical methods for the suppression of oxidation to improve plutonium separation in contactor operation
A systematic method has been used to screen a number of potential stabilizers (holding reductants) for Pu(III) in tri-n-butyl phosphate/diluent solutions used in irradiated fuel reprocessing systems. The conditions assumed were similar to those used in solvent extraction contactor operations. Of the reagents tested, oximes as a group appeared to be very effective. Acetaldoxime, in particular, was selected for extensive tests and was used as a Pu(III) stabilizer, in both the aqueous and organic phases, in contactor runs for plutonium partition from thorium and uranium. In the best results, the plutonium loss to the thorium/uranium stream was 2.8 X 10/sup -5/ g/l or 0.0046%; without using acetaldoxime, the loss was 12%. Rates of plutonium reduction in 1.5 M nitric acid have been compared for a number of reducing agents under identical conditions. Some derivatives of hydroxylamine were found to be much more effective than hydroxylamine itself.
- Research Organization:
- Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba
- OSTI ID:
- 6155034
- Journal Information:
- Nucl. Technol.; (United States), Vol. 63:3
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PLUTONIUM
OXIDATION
REDUCTION
REPROCESSING
PLUTONIUM RECYCLE
AQUEOUS SOLUTIONS
HYDROXYLAMINE
NITRIC ACID
OXIMES
PROCESS SOLUTIONS
REAGENTS
SOLVENT EXTRACTION
STABILIZATION
TBP
THORIUM
URANIUM
ACTINIDES
AMINES
BUTYL PHOSPHATES
CHEMICAL REACTIONS
DISPERSIONS
ELEMENTS
ESTERS
EXTRACTION
FUEL CYCLE
HYDROGEN COMPOUNDS
HYDROXY COMPOUNDS
INORGANIC ACIDS
METALS
MIXTURES
ORGANIC COMPOUNDS
ORGANIC NITROGEN COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
SEPARATION PROCESSES
SOLUTIONS
TRANSURANIUM ELEMENTS
050800* - Nuclear Fuels- Spent Fuels Reprocessing