Recovery of uranium from mixed plutonium-uranium residues by an extraction chromatography process

Technical Report · Sat May 15 04:00:00 EDT 1982

OSTI ID:5226277

Martella, L L; Navratil, J D

An extraction chromatographic process has been developed for recovering uranium from uranium-plutonium residues. The process utilizes a column of amberlite XAD-4 resin impregnated with tributyl phosphate to selectively sorb uranium from a 5 M HNO/sub 3/ solution containing U(VI) and Pu(III). During the eight demonstration runs, the average uranium processing was 69 mg U/ml resin. The retention of plutonium from the mixed uranium-plutonium solution was less than 0.06 g Pu/l resin, which met uranium product purity requirements of > 0.5 wt % plutonium.

• Research Organization: Rockwell International Corp., Golden, CO (USA). Rocky Flats Plant
• DOE Contract Number: AC04-76DP03533
• OSTI ID: 5226277
• Report Number(s): RFP-3289; ON: DE82015997
• Country of Publication: United States
• Language: English

Related Subjects

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37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105* -- Separation Procedures
ACTINIDES
BUTYL PHOSPHATES
CHEMICAL ANALYSIS
CHROMATOGRAPHY
DATA
ELEMENTS
ESTERS
EXPERIMENTAL DATA
EXTRACTION CHROMATOGRAPHY
HYDROGEN COMPOUNDS
INFORMATION
INORGANIC ACIDS
METALS
MODIFICATIONS
NITRIC ACID
NUMERICAL DATA
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PHOSPHORIC ACID ESTERS
PLUTONIUM
POLYMERS
PUREX PROCESS
QUANTITATIVE CHEMICAL ANALYSIS
RECOVERY
REPROCESSING
RESIDUES
RESINS
SEPARATION PROCESSES
SOLVENT PROPERTIES
TBP
TRANSURANIUM ELEMENTS
URANIUM