Removal of uranium from sulfate leach liquor of salcrete deposits using tri-n-octyl amine |
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Authors: | A M Daher S Abdel Wanees H M A Kellah A H Ali |
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Institution: | 1. Nuclear Materials Authority, P.O. Box 530, Maadi-Kattameya, Cairo, Egypt 2. Department of Chemistry, Faculty of Science, Zagazig University, Zagazig, Egypt
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Abstract: | A uranyl sulfate leach liquor obtained by uranium leaching of a technological sample of salcrete deposits of Gabal Qatrani ore was subjected to uranium extraction using the liquid–liquid technique. Uranium was effectively extracted from sulfate leach liquor by (10 %) tri-n-octylamine (TOA)] dissolved in xylene as a diluent. The extraction efficiency was markedly enhanced as the concentration of TOA increases from 1 to 10 %. The relevant factors controlling the extraction process of uranium using tri-n-octylamine were studied. These factors include the effect of diluents used, TOA concentration, contact time, settling time and phase ratio (O/A) v/v. The optimum extraction conditions were chosen. Stripping of uranium from the loaded TOA has been carried out using 5 % Na2CO3 as an effective stripping agent. More than 97 % of uranium was extracted by 10 % TOA, at contact time 10 min, settling time 5 min, phase ratio (VO/VA) 1/1 and at room temperature. The feasibility of using the TOA for preconcentration-separation of uranium was assessed by stripping studies. The loaded uranium onto TOA has been stripped by 100 % when using 5 % Na2CO3 as an efficient eluting agent at 15 min contact time, 5 min settling time and phase ratio (O/A) 2/1. |
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