Selective permeation of plutonium(IV) through supported liquid membrane containing 2-ethylhexyl 2-ethylhexyl phosphonic acid as ion carrier |
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| Institution: | 1. Ben-Gurion University of the Negev, Department of Nuclear Engineering, P.O. Box 653, Beer-Sheva 84105, Israel;2. Department of Nuclear Engineering and Radiological Sciences, The University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109, USA;3. National Research Council of Canada, Ionizing Radiation Standards Laboratory, Ottawa, ON K1A 0R6, Canada;1. CSIRO Agriculture Flagship, GPO Box 1600, Canberra, ACT 2601, Australia;2. Faculty of Veterinary and Agricultural Sciences, the University of Melbourne, Parkville, 3010 Victoria, Australia;3. School Agriculture, Food and Wine, The University of Adelaide, PMB 1, Glen Osmond, SA 5064, Australia;4. Embrapa Agrobiologia, Rodovia BR 465, Km 47, Seropédica, 23891-000 Rio de Janeiro, Brazil;1. Faculty of Veterinary and Agricultural Sciences, The University of Melbourne, Parkville 3010, Victoria, Australia;2. State Key Laboratory of Urban and Regional Ecology, Research Centre for Eco-environmental Science, Chinese Academy of Sciences, Beijing 100085, PR China;3. CSIRO Agriculture & Food, PO Box 1600, Canberra, ACT 2601, Australia |
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| Abstract: | The selective transport of plutonium across supported liquid membrane using an indigenously synthesized 2-ethylhexyl 2-ethylhexyl phosphonic acid (KSM-17, equivalent to PC 88A) dissolved in dodecane as carrier has been investigated in this work. Laminar type polypropylene hydrophobic microporous membranes were used as solid supports. Transport experiments were carried out to evaluate the effect of varied hydrodynamic and chemical compositions of the system, i.e., stirring speed, carrier concentration, anionic composition (e.g. SO2−4, NO−3, PO3−4, ClO−4, Cl−) and acidity of source phase (SP) solution. Transport rates of plutonium from SP solutions of different anionic composition followed the order: ClO−4>NO−3>Cl−>SO2−4>PO3−4. Selective permeability of plutonium was observed in the presence of several cationic impurities such as Al, B, Be, Ca, Cd, Cr, Cu, Fe, Mg, Mn, Ni, Pb, Si, Zn, Ce, Dy, Eu, Gd and Sm. Using this technique, separation of plutonium from laboratory analytical waste was accomplished with an average flux 8.94×10−6 mol m−2 s−1 and with an enrichment factor greater than 2. The product solution obtained from this process was in oxalate medium with negligible contamination from other cationic and anionic impurities. From this solution, plutonium was precipitated as Pu-oxalate for further processing. Reusability of the membrane support was found to be satisfactory. |
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