Extraction of Irradiated Uranium with Methyl Cyclohexanone; EKSTRAKTSIYA OBLUCHENNOGO URANA METILTSIKLOGEKSANONOM
The use of a new solvent, methyl cyclohexanone, for extraction of irradiated uranium in the system water --nitric acid --salting-out sgent was investigated. The dependence of distribution coefficients of uranium and of beta and gamma activity of fission products on nitric acid, uranium, salting-out agent, and solvent concentration in equilibrium conditions was found. Comparison was made of the salting-out effect of ammonium, aluminum, and sodium nitrates. In the case of ammonium nitrate the distribution coefficients of uranium and beta and gnmma activity with those of tributyl phosphate in similar conditions were compared. It is true that in the csse of aluminum nitrate higher distribution coefficients of uranium were found, but at same time a less effective separation of uranium from the flssion products was achieved. The results obtained in the case of ammonium nitrate are comparable with results of tributyl phosphate extraction. (auth)
- Research Organization:
- Czechoslovakia
- NSA Number:
- NSA-13-006535
- OSTI ID:
- 4285435
- Report Number(s):
- A/CONF.15/P/2100
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
ALUMINUM NITRATES
AMMONIUM COMPOUNDS
BETA PARTICLES
BUTYL PHOSPHATES
CHEMISTRY
CYCLOALKANES
DISTRIBUTION
EFFICIENCY
FISSION PRODUCTS
GAMMA RADIATION
KETONES
METHYL RADICALS
NITRATES
NITRIC ACID
PRECIPITATION
RADIOACTIVITY
REPROCESSING
SODIUM NITRATES
SOLVENT EXTRACTION
URANYL NITRATES
WATER