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Removal of uranium from sulfate leach liquor of salcrete deposits using tri-n-octyl amine

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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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Authors and Affiliations

  1. Nuclear Materials Authority, P.O. Box 530, Maadi-Kattameya, Cairo, Egypt

    A. M. Daher & A. H. Ali

  2. Department of Chemistry, Faculty of Science, Zagazig University, Zagazig, Egypt

    S. Abdel Wanees & H. M. A. Kellah

Authors
  1. A. M. Daher
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  2. S. Abdel Wanees
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  3. H. M. A. Kellah
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  4. A. H. Ali
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Correspondence to A. H. Ali.

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Daher, A.M., Wanees, S.A., Kellah, H.M.A. et al. Removal of uranium from sulfate leach liquor of salcrete deposits using tri-n-octyl amine. J Radioanal Nucl Chem 299, 493–499 (2014). https://doi.org/10.1007/s10967-013-2762-x

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  • DOI: https://doi.org/10.1007/s10967-013-2762-x

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