STRIPPING OF URANIUM FROM TRI-N-OCTYLOAMINE EXTRACTS BY SODIUM CARBONATE SOLUTIONS

Journal Article · Tue Jan 01 04:00:00 EST 1963 · Nukleonika (Poland)

OSTI ID:4156896

Golinski, M; Korpak, W

Optimal parameters of uranium stripping from 0.1 M tri-n-octylamine(I) plus 3v% sec-n-octanol in kerosene were studied. Polish uranium ores were leached with 5% sulfuric acid and extracted with I. A 10% sodium carbonate solution was employed as the stripping agent. To obtain complete uranium stripping, it was necessary to supply to the system more sodium carbonate than stoichiometrically required. The phase separation depends on mixing conditions, extent of sodium carbonate concentration in aqueous phase, and ferric ion in organic phase. (auth)

• Research Organization: Inst. of Nuclear Research, Polich Academy of Sciences, Warsaw
• NSA Number: NSA-18-005426
• OSTI ID: 4156896
• Journal Information: Nukleonika (Poland), Journal Name: Nukleonika (Poland) Vol. Vol: 8; ISSN NUKLA
• Country of Publication: Country unknown/Code not available
• Language: Polish

Related Subjects

ALKYL RADICALS
ALUMINUM
ALUMINUM ALLOYS
ALUMINUM FLUORIDES
AMINES
ANODES
CATHODES
CHEMISTRY
ELECTROCHEMISTRY
ELECTROLYSIS
ENRICHMENT
FUEL ELEMENTS
LEACHING
NEUTRON BEAMS
ORE PROCESSING
PLUTONIUM
PLUTONIUM ALLOYS
REPROCESSING
SEPARATION PROCESSES
SODIUM CARBONATES
SODIUM FLUORIDES
SOLVENT EXTRACTION
SULFURIC ACID
URANIUM
URANIUM ALLOYS
URANIUM ORES
WASTE PROCESSING