RECOVERY OF URANIUM IN CARBONATE SOLUTIONS WITH ANION EXCHANGE RESINS (in Spanish)
An ion exchange process for the recovery, purification, and concentration of the uranium contained in solutions with excess sodium carbonate, as is the case of the alkaline leaching of uranium ores, was studied. The studies were made on batch and column procedures. The results showed that of the resins studied Amberlite IRA 400 was the most convenient. Batch tests showed that the uranium exchange is a function of the uranium concentration and that the best recovery is made with the lowest possible concentration of the leaching agent, with suifate concentrations below 40 g/l and nitrate and chloride concentrations below 2 g/l, and with pH between 11.5 and 12. Column tests conftrm the previous conclusions. At the pH maximum V and Mo are poorly fixed. Five volumes of deionized water provide an efficient washing. A solution of 1.4M (NH/sub 4/)/sub 2/CO/sub 3/ and of 0.9M NaHCO/sub 3/ is used as eluant. A counter current washing is efficient. The optimum retention times are 4 to 8 min for the sorption and washing steps and 10 min for elution. For liquids with 5% carbonate, the resin has a capacity of 55 g U/l of humid and precipitated resin milk. 99% of the U processed is recovered in the elution with a purity higher than 98%. (tr-auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-17-010769
- OSTI ID:
- 4707543
- Journal Information:
- Rev. Fac. Cien. Quim., Univ. Nacl. La Plata, Vol. Vol: 33; Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- Country unknown/Code not available
- Language:
- Spanish
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