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Hindi Research Article, J Nucl Ene Sci Power Generat Technol Vol: 2 Issue: 2
Solvent Extraction Separation of U (VI), Th (IV) and Cd (II) from Chloride Media by Trioctylmethylammonium Chloride and Bis (2-ethylhexyl) Phosphate
| M M Shehata1*, H H Mahmoud2 and S A Waly3 | |
| 1Accelerators and Ion Sources department, Nuclear Research Center - Atomic Energy Authority, Cairo, Egypt | |
| 2Central Laboratory for Elemental and Isotopic Analysis, Nuclear Research Center - Atomic Energy Authority, Cairo, Egypt | |
| 3Second Research Reactor, Nuclear Research Center - Atomic Energy Authority, Cairo, Egypt | |
| Corresponding author : M M Shehata Accelerators and Ion Sources department, Nuclear Research Center - Atomic Energy Authority, Cairo, Egypt E-mail: m_shehata2100@yahoo.com |
|
| Received: January 26, 2013 Accepted: May 04, 2013 Published: May 11, 2013 | |
| Citation: Shehata MM, Mahmoud HH, Waly SA (2013) Solvent Extraction Separation of U (VI), Th (IV) and Cd (II) from Chloride Media by Trioctylmethylammonium Chloride and Bis (2-ethylhexyl) Phosphate. J Nucl Ene Sci Power Generat Technol 2:2. doi:10.4172/2325-9809.1000109 |
Abstract
Solvent Extraction Separation of U (VI), Th (IV) and Cd (II) from Chloride Media by Trioctylmethylammonium Chloride and Bis (2-ethylhexyl) Phosphate
Solvent extraction of U (VI), Th (IV) and Cd (II) from chloride solutions with trioctylmethylammonium chloride (TOMACl), bis (2-ethylhexyl) phosphate (D2EHPA) and dimethylformamide in cyclohexane was investigated. The effect of the extractant, organic diluents, as well as HCl concentration on the extraction process was carried out. The influence of various stripping agents has also been investigated. The optimum conditions for separation of U (VI), Th (IV) and Cd (II) was found to be using 0.2 M trioctylmethyl ammonium chloride in cyclohexane in which uranium, cadmium and traces of thorium were extracted, and then uranium was stripping with H2O. The analysis was done using Inductively Coupled Plasma Atomic Emission Spectrometry (ICP-AES). The complete process of separation was carried out and the yield of U (VI) and Th (IV) was evaluated with percentage of recovery of 83 ± 2.5% and 75 ± 3% respectively.
