Abstract
The uranium extraction from sulphate pregnant solution by Cyanex®272 in kerosene diluent was examined. The influence of parameters affecting the extraction mechanism including Cyanex®272 concentrations and equilibrium pH was investigated. At optimized conditions, the extraction efficiency of 97.1 ± 3% U(VI) by 0.3 mol/L Cyanex®272 at 27 ± 2 °C in the equilibrium pH range of 3–4 was achieved from the pregnant solution containing admixtures of 3596.3 mg/L U(VI), 31.47 mg/L Th(IV), 11.01 mg/L Fe(III), 68.70 mg/L Al(III), 7.29 mg/L Mn(II), 0.57 mg/L Ce(IV), 0.49 mg/L La(III), and 0.10 mg/L Pr(IV), respectively. Maximum stripping of U(VI) from the loaded organic phase was achieved using 0.5 mol/L Na2CO3 solution. Finally, uranium from uranyl solution recovered as sodium diuranate (Na2U2O7: 00-064-0473, density = 6.51 g/cm3, melting point = 1654 ± 2 °C) is capable to serve as intermediate in nuclear fuel cell.
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Acknowledgements
The authors wish to sincerely thank Dr. Oliver Rouher and Mrs. Christine Salomon of Cytec Industries, Rungis Cedex, France for their benevolence in supplying Cyanex®272 used in this study.
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Raji, M.A., Baba, A.A. & Abhilash Uranium extraction from sulphuric acid leach liquor by Cyanex®272 as intermediate in nuclear fuel cell. J Radioanal Nucl Chem 332, 4471–4476 (2023). https://doi.org/10.1007/s10967-023-09144-4
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DOI: https://doi.org/10.1007/s10967-023-09144-4