Separation of Pu-Am from an aqueous waste by successive oxalate and lead oxalate precipitations

Journal Article · Fri Jan 01 00:00:00 EST 1982 · Sep. Sci. Technol.; (United States)

DOI:https://doi.org/10.1080/01496398208055631· OSTI ID:5734911

Akatsu, J

Decontamination of an aqueous waste of Pu and Am was carried out stepwise by making an oxalate and then a lead oxalate precipitate. The alpha radioactivity was reduced from 6.8 mCi/L to 10 ..mu..Ci/L by these techniques. The precipitates obtained were dissolved in 7 M nitric acid solution, from which Pu and 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 prior to its separation by the cation column. The overall recovery yields were about 90% for both Pu and Am.

• Research Organization: Japan Atomic Energy Research Inst., Japan
• OSTI ID: 5734911
• Journal Information: Sep. Sci. Technol.; (United States), Vol. 17:12
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
AMERICIUM
SEPARATION PROCESSES
PLUTONIUM
RADIOACTIVE WASTE PROCESSING
LIQUID WASTES
ALPHA SOURCES
AQUEOUS SOLUTIONS
DECONTAMINATION
ION EXCHANGE CHROMATOGRAPHY
LEAD COMPLEXES
OXALATES
PRECIPITATION
ACTINIDES
CARBOXYLIC ACID SALTS
CHROMATOGRAPHY
CLEANING
COMPLEXES
DISPERSIONS
ELEMENTS
ION SOURCES
MANAGEMENT
METALS
MIXTURES
PARTICLE SOURCES
PROCESSING
RADIATION SOURCES
SOLUTIONS
TRANSPLUTONIUM ELEMENTS
TRANSURANIUM ELEMENTS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
052001* - Nuclear Fuels- Waste Processing