Synergistic extraction of uranium(VI) by bis(2,4,4-trimethylpentyl) phosphini acid in the presence of neutral oxo-donors
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R. Meera
Summary
The extraction behavior of uranium(VI) from nitric acid solutions has been investigated using mixtures of bis(2,4,4-trimethylpentyl)phosphinic acid (HBTMPP) and trialkylphosphine oxide (Cyanex 923 = TRPO), triphenylphosphine oxide (TPhPO) or tributylphosphate (TBP). The results demonstrate that uranium(VI) is extracted into xylene as UO2(BTMPP)2 with HBTMPP alone and as UO2(BTMPP)2·S (where S = TRPO, TPhPO or TBP) in the presence of neutral oxo-donors. The extraction equilibrium constants of the above extracted complexes have been deduced by non-linear regression analysis with the aid of suitable chemically based model developed taking into account aqueous phase complexation of metal ion with inorganic ligands and all plausible complexes extracted into the organic phase. The addition of a neutral oxo-donor to the metal chelate system significantly enhances the extraction efficiency of uranium(VI). Complexation strength of uranium(VI) with neutral oxo-donors follows the order: TRPO > TPhPO > TBP, which is also the basicity sequence of these ligands. The IR spectral studies of the extracted complexes were used to further clarify the nature of the extracted complexes.
© Oldenbourg Wissenschaftsverlag, München
Articles in the same Issue
- Photofission of 209Bi at intermediate energies
- Synergistic extraction of uranium(VI) by bis(2,4,4-trimethylpentyl) phosphini acid in the presence of neutral oxo-donors
- Analysis of 237Np in spent fuel solutions
- The solubilisation of Ru and U from condensation particles released b overheated nuclear fuel and maturated in air and in argon
- Contrary effects of the water radiolysis product H2O2 upon th dissolution of nuclear fuel in natural ground water and deionized water
- Accelerator mass spectrometry dating at Çatalhöyük
- Radiochemical separation of no-carrier-added radioniobium from zirconiu targets for application of 90Nb-labelled compounds
- Separation of pertechnetate from molybdate by anion-exchange chromatography: Recovery of 99mTc from (n, γ)99Mo and suitability for use in central radiopharmacy (CRPh)
- Synthesis, radiolabelling characteristics and biological evaluation of the derivatives of mercaptoacetyltriglycine
Articles in the same Issue
- Photofission of 209Bi at intermediate energies
- Synergistic extraction of uranium(VI) by bis(2,4,4-trimethylpentyl) phosphini acid in the presence of neutral oxo-donors
- Analysis of 237Np in spent fuel solutions
- The solubilisation of Ru and U from condensation particles released b overheated nuclear fuel and maturated in air and in argon
- Contrary effects of the water radiolysis product H2O2 upon th dissolution of nuclear fuel in natural ground water and deionized water
- Accelerator mass spectrometry dating at Çatalhöyük
- Radiochemical separation of no-carrier-added radioniobium from zirconiu targets for application of 90Nb-labelled compounds
- Separation of pertechnetate from molybdate by anion-exchange chromatography: Recovery of 99mTc from (n, γ)99Mo and suitability for use in central radiopharmacy (CRPh)
- Synthesis, radiolabelling characteristics and biological evaluation of the derivatives of mercaptoacetyltriglycine
