SEPARATION OF BARIUM VALUES FROM URANYL NITRATE SOLUTIONS
Abstract
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.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4240853
- Patent Number(s):
- 2875024
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
- NSA Number:
- NSA-13-015172
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; ACIDITY; ADSORPTION; BARIUM; BARIUM ISOTOPES; BARIUM NITRATES; CATIONS; CHEMICAL REACTIONS; 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
Citation Formats
Tompkins, E R. SEPARATION OF BARIUM VALUES FROM URANYL NITRATE SOLUTIONS. United States: N. p., 1959.
Web.
Tompkins, E R. SEPARATION OF BARIUM VALUES FROM URANYL NITRATE SOLUTIONS. United States.
Tompkins, E R. Tue .
"SEPARATION OF BARIUM VALUES FROM URANYL NITRATE SOLUTIONS". United States.
@article{osti_4240853,
title = {SEPARATION OF BARIUM VALUES FROM URANYL NITRATE SOLUTIONS},
author = {Tompkins, E R},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {2}
}