Sequential separation of americium, curium, plutonium, neptunium and uranium in various matrices from the electrometallurgic treatment of spent-nuclear fuel
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M. W. Huntley
The separation of americium-241, curium-242/244, plutonium-238/239, neptunium-237, and uranium-234/235/238, in the same sample aliquot of clear acidic solution resulting from the electrometallurgical treatment of spent nuclear fuel has been investigated. Using ion exchange techniques in 10 M HCl media, it was determined that good separation can be achieved to resolve each isotope via alpha spectroscopy. The resin used was AG 1-x8 chloride form supplied by BioRad® Laboratories. The retention and eluting conditions for each isotope were determined using tracer techniques and will be presented. Based on this work, an analytical procedure for the sequential separation of Am, Cm, Pu, Np, and U, in various sample matrices recovered from the demonstration project is presented.
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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
