A comparison of the extraction of carrier-free 176,177W and 99Mo with that of U, Th, Am, Cm, La, Ce, Tm, Yb, Lu, and Hf into tri-n-octyl amine in toluene from nitric, phosphoric, and sulphuric acid media
-
M. Johansson
The extraction of carrier-free tungsten and molybdenum from nitric, phosphoric and sulphuric acid with 0.05 M TOA (tri-n-octyl amine, R3N) in toluene and 2.5% by volume 1-dodecanol has been studied. Their extraction behaviour has also been compared to hafnium, some trivalent lanthanides (lanthanum, cerium, thulium, ytterbium and lutetium) and some actinides (thorium, uranium, americium and curium). The extraction of these metal ions decreases in the order M4+>MO22+>M3+ from >1 M nitric acid solutions, if hafnium, which is on the form HfO2+, is disregarded. At low nitric acid concentrations tungsten and molybdenum are most likely extracted as tungstate or molybdate ions (R3NH)2·MO4, while at higher concentrations they are most likely extracted similar to uranium, i.e. on the form R3NH·MO2(NO3)3. Further, the extraction from phosphoric acid solutions decreases in the order M4+>MO22+>M3+, if the elements which are easily hydrolysed, hafnium, molybdenum and tungsten, are disregarded. The major extracted complex of tungsten contains one TOA and the minor two TOA. The extracted complex with one TOA is probably (R3NH)·WO2(H2PO4)3 or R3N·WO2(H2PO4)2, while that with two TOA more likely is (R3N)2H·WO2(H2PO4)3 or even the more hydrolysed species of tungsten (R3NH)2·WO4. For molybdenum, the extracted complexes seem reasonably similar. Disregarding HfO2+ the extraction decreases in the order MO22+>M4+>M3+ for the chosen range of sulphuric acid concentration.
© 2015 Oldenbourg Wissenschaftsverlag GmbH, Rosenheimer Str. 145, 81671 München
Articles in the same Issue
- Sequential separation of americium, curium, plutonium, neptunium and uranium in various matrices from the electrometallurgic treatment of spent-nuclear fuel
- Supercritical fluid extraction of plutonium and americium from soil using thenoyltrifluoroacetone and tributylphosphate complexation
- A comparison of the extraction of carrier-free 176,177W and 99Mo with that of U, Th, Am, Cm, La, Ce, Tm, Yb, Lu, and Hf into tri-n-octyl amine in toluene from nitric, phosphoric, and sulphuric acid media
- EXAFS investigation of uranium(VI) complexes formed at Bacillus cereus and Bacillus sphaericus surfaces
- Thorium isotope fractionation in the dissolution of inorganic samples by a microwave method
- Diffusion of 99Tc in granite: A small scale laboratory simulation experiment
- Migration of 99Tc in unsaturated Chinese loess under artificial rainfall condition: an in situ test
- Separation and speciation of fission products by zirconium phosphate prepared by solid-solid reaction
- Interaction study between Ca2+ and humic acids in brine media
- 223Ra for endoradiotherapeutic applications prepared from an immobilized 227Ac/227Th source
Articles in the same Issue
- Sequential separation of americium, curium, plutonium, neptunium and uranium in various matrices from the electrometallurgic treatment of spent-nuclear fuel
- Supercritical fluid extraction of plutonium and americium from soil using thenoyltrifluoroacetone and tributylphosphate complexation
- A comparison of the extraction of carrier-free 176,177W and 99Mo with that of U, Th, Am, Cm, La, Ce, Tm, Yb, Lu, and Hf into tri-n-octyl amine in toluene from nitric, phosphoric, and sulphuric acid media
- EXAFS investigation of uranium(VI) complexes formed at Bacillus cereus and Bacillus sphaericus surfaces
- Thorium isotope fractionation in the dissolution of inorganic samples by a microwave method
- Diffusion of 99Tc in granite: A small scale laboratory simulation experiment
- Migration of 99Tc in unsaturated Chinese loess under artificial rainfall condition: an in situ test
- Separation and speciation of fission products by zirconium phosphate prepared by solid-solid reaction
- Interaction study between Ca2+ and humic acids in brine media
- 223Ra for endoradiotherapeutic applications prepared from an immobilized 227Ac/227Th source
