Separation of Pu-Am from the leachant of a deposit in an acid digestion solution by calcium oxalate coprecipitation
Pu and Am were recovered from the deposit in a synthetic acid digestion solution. After being leached out from the deposit with water, they were separated from the resultant solution by Ca-oxalate coprecipitation. The alpha radioactivity in the solution was reduced from about 4 mCi/L to 0.1 ..mu..Ci/L by the technique. The precipitate obtained was dissolved in 7 M nitric acid solution, from which Pu-Am were separated by the use of anion and cation exchange resin columns, respectively. The coprecipitation technique was also utilized for the concentration of Am in the effluent of the anion column prior to its separation by a cation column. The overall recovery efficiencies of Pu and Am were about 80 and 85%, respectively.
- Research Organization:
- Japan Atomic Energy Research Inst., Tokai-Mura Ibaraki-Ken, Japan
- OSTI ID:
- 5633520
- Journal Information:
- Sep. Sci. Technol.; (United States), Journal Name: Sep. Sci. Technol.; (United States) Vol. 18:2; ISSN SSTED
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
ALKALINE EARTH METAL COMPOUNDS
AMERICIUM
CALCIUM COMPOUNDS
CARBOXYLIC ACID SALTS
COPRECIPITATION
DISSOLUTION
ELEMENTS
ION EXCHANGE MATERIALS
LEACHING
MANAGEMENT
MATERIALS
MATERIALS RECOVERY
METALS
OXALATES
PLUTONIUM
PRECIPITATION
PROCESSING
RADIOACTIVITY
RECOVERY
SEPARATION PROCESSES
TRANSPLUTONIUM ELEMENTS
TRANSURANIUM ELEMENTS
WASTE MANAGEMENT
WASTE PROCESSING