Recovery of uranium by extraction with polyurethane foam
Since open cell polyurethane foam can act as a viscous organic polyether of moderate dielectric constant, it was used in this study for the extraction of ..mu..g-amounts of uranium in nitric acid and in the presence of salting-out agents such as ammonium, calcium and aluminum nitrates. In addition the extraction characteristics of thorium were investigated for the purpose of using the results for a possible separation of uranium from thorium. Thorium was found to be more strongly extracted than uranium in 0.1 M nitric acid solution containing varying concentrations of ammonium nitrates. Also the influence of other variables were investigated and tabulated. Some of these are: distribution coefficients of uranium in 0.1 M nitric acid which contains varying overall nitrate molarities of ammonium, calcium and aluminum nitrates; effect of acidity on the distribution coefficient of uranium at the overall nitrate molarity of 7M; effect of uranium concentration on the distribution coefficient of uranium in 0.1M nitric acid solutions of 7M overall nitrate concentration; effect of shaking time on the distribution coefficient of uranium in 0.1M nitric acid solutions of 7M over all nitrate concentration; effect of methanol and ethanol on the distribution coefficients of uranium in 20 m1 mixtures of the alcohols with dilute nitric acid; distribution coefficients of uranium in 0.1M nitric acid solutions of 7M overall nitrate concentration using as extractant polyurethane foam impregnated with ethyl acetate; elution characteristics of uranium on a 0.5 g column of hexone impregnated polyurethane foam using 6M hydrochloric acid as the eluent. (ATT)
- Research Organization:
- Rockwell International Corp., Golden, CO (USA). Rocky Flats Plant; Vienna Univ. (Austria). Inst. for Analytical Chemistry
- DOE Contract Number:
- AC04-76DP03533
- OSTI ID:
- 5619929
- Report Number(s):
- RFP-3254; CONF-810899-1; ON: DE82003958
- Country of Publication:
- United States
- Language:
- English
Similar Records
ULTRAVIOLET SPECTROPHOTOMETRIC DETERMINATION OF URANIUM. Separation of Uranium from Bismuth Using Tris-(2-ethylhexyl)phosphine Oxide. Work completed, May 1958
Extraction of Irradiated Uranium with Methyl Cyclohexanone; EKSTRAKTSIYA OBLUCHENNOGO URANA METILTSIKLOGEKSANONOM
Related Subjects
400105* -- Separation Procedures
ACETIC ACID ESTERS
ACTINIDE COMPOUNDS
ACTINIDES
ALCOHOLS
ALKALINE EARTH METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM NITRATES
AMMONIUM COMPOUNDS
AMMONIUM NITRATES
CALCIUM COMPOUNDS
CALCIUM NITRATES
CARBOXYLIC ACID ESTERS
CHEMICAL ANALYSIS
COLLOIDS
DATA
DISPERSIONS
DISTRIBUTION FUNCTIONS
ELEMENTS
ESTERS
ETHANOL
EXPERIMENTAL DATA
EXTRACTION
FOAMS
FUNCTIONS
HYDROGEN COMPOUNDS
HYDROXY COMPOUNDS
INFORMATION
INORGANIC ACIDS
MATERIALS
METALS
METHANOL
NITRATES
NITRIC ACID
NITROGEN COMPOUNDS
NUMERICAL DATA
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
PLASTICS
POLYAMIDES
POLYMERS
POLYURETHANES
QUANTITATIVE CHEMICAL ANALYSIS
SEPARATION PROCESSES
SOLVENT EXTRACTION
SOLVENT PROPERTIES
SYNTHETIC MATERIALS
THORIUM
TRACE AMOUNTS
URANIUM
URANIUM COMPOUNDS
URANYL COMPOUNDS
URANYL NITRATES