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    Synthesis and structure of Ce1−xEuxPO4 solid solutions for minor actinides immobilization
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    Americium, plutonium, and uranium ions were successfully removed from acidic waste solutions using several types of extraction chromatographic resins. These resins might be applied to convert the bulk of transuranic (TRU) wastes, which contain actinides, to low-level radioactive wastes. Because disposal of low-level wastes is much less expensive than TRU wastes, economic incentives exist for actinide removal. Both batch equilibrium extraction measurements and column elution measurements were used to evaluate the effectiveness of the resins for actinide removal. Resins containing adsorbed octyl (phenyl)-N,N-diisobutylcarbamoylmethlyphosphine oxide (CMPO) were the most effective in removing americium from the solutions. Plutonium and uranium were more readily extracted than americium. Higher acid concentrations lowered actinide extraction by the resins due to competition between HNO{sub 3} and actinide nitrates for the extractant. As expected, high nitrate concentrations improved extraction. Iron (a major component of much TRU wastes) lowered americium extraction due to competition for the extractant. Column extraction measurements showed that actinide extraction by the resins is rapid. Near equilibrium conditions exist in the columns at useful flow rates.
    Citations (8)
    AbstractDue to the similar chemical properties between the neighboring trivalent actinide elements americium and curium, their extraction behavior is often perceived as indistinguishable. In this work, the characterization of seven extraction chromatography resins (TEVA, TRU, DGA(N), Actinide, Ln, Ln2, and Ln3) for these trivalent actinides from acidic matrices (HNO3, HCl, and HBr) has provided some evidence to the contrary. In most cases, Am(III) and Cm(III) exhibit identical extraction properties. However, separation is possible with TRU and DGA(N) resins as demonstrated in this study. The extraction shows a strong dependency on the specific anion in solution that follows the order NO3−>Br−>Cl−.Keywords: extraction chromatographyamericiumcuriumcharacterizationseparation
    Curium
    Article Spectroelectrochemical Studies of the Actinides: Stabilization of Americium(IV) in Aqueous Carbonate Solution was published on May 1, 1982 in the journal Radiochimica Acta (volume 31, issue 3-4).
    Citations (34)
    A novel separation process for recovering transuranic actinides has been tested in centrifugal contactors using a surrogate feed solution. This "TRU-SANEX" (transuranic element-selective actinide extraction) process uses solvent extraction between nitric acid and an organic phase containing 0.2 mol/L N,N,N′,N′-tetraoctyl diglycolamide with 0.5 mol/L N,N′-dimethyl-N,N′-dioctylhexylethoxy-malonamide to co-extract actinides and lanthanides followed by separate sections for plutonium–neptunium and americium–curium stripping. Overall, good performance was achieved with good recoveries of plutonium and americium in the products and only small amounts of cross-contamination between products. Decontamination factors for selected lanthanides in the americium–curium product ranged from ~40 to >1300.
    Curium
    Neptunium
    Transuranium element
    Nitric acid
    Human decontamination
    Stripping (fiber)
    A novel bis(1,2,4-triazin-3-yl)-dppz (dipyridophenazine) BTPhen ligand has been synthesised and screened for its ability to selectively extract Am(III) selectively from Eu(III) from 0.001 M – 2 M HNO3. The ligand showed preferential extraction for Am(III) over Eu(III) as the [HNO3] increased towards 2 M with a reported separation factor (SFAm/Eu) of ∼225. The synthesis towards the dppz-BTPhen ligand employs a truncated synthetic approach, involving two one-pot reactions. Keywords: Actinide, lanthanide, spent nuclear fuel reprocessing, solvent extraction, BTPhen, americium, Europium.
    Europium