SEPARATION OF BARIUM VALUES FROM URANYL NITRATE SOLUTIONS
The separation of radioactive barium values from a uranyl nitrate solution of neutron-irradiated uranium is described. The 10 to 20% uranyl nitrate solution is passed through a flrst column of a cation exchange resin under conditions favoring the adsorption of barium and certain other cations. The loaded resin is first washed with dilute sulfuric acid to remove a portion of the other cations, and then wash with a citric acid solution at pH of 5 to 7 to recover the barium along with a lesser amount of the other cations. The PH of the resulting eluate is adjusted to about 2.3 to 3.5 and diluted prior to passing through a smaller second column of exchange resin. The loaded resin is first washed with a citric acid solution at a pH of 3 to elute undesired cations and then with citric acid solution at a pH of 6 to eluts the barium, which is substantially free of undesired cations.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-13-015172
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2875024
- OSTI ID:
- 4240853
- Country of Publication:
- United States
- Language:
- English
Similar Records
CONVERSION OF URANYL SULFATE TO NITRATE BY ION EXCHANGE
Purification of uranium by selective sorption of uranyl chloride on anion resin
Related Subjects
ADSORPTION
BARIUM
BARIUM ISOTOPES
BARIUM NITRATES
CATIONS
CHEMICAL REACTIONS
CHEMISTRY
CITRIC ACID
DECONTAMINATION
EXTRACTION COLUMNS
FISSION PRODUCTS
IMPURITIES
ION EXCHANGE
ION EXCHANGE MATERIALS
IRRADIATION
LIQUID FLOW
LITHIUM HYDRIDES
MECHANICAL PROPERTIES
NEUTRON BEAMS
OPERATION
PATENT
PERFORMANCE
QUANTITY RATIO
RADIOISOTOPES
RECOVERY
REFINING
SEPARATION PROCESSES
SOLUTIONS
SULFURIC ACID
TABLES
URANYL NITRATES
WATER