Abstract

A novel tripodal diglycolamide (T-DGA) extractant in a diluent mixture (10:1 n-dodecane– iso-decanol) was evaluated for the extraction of actinide ions such as UO 2 2+, Np(IV), Pu(IV), and Am(III) and fission product element ions such as Cs + and Sr 2+ from acidic feed solutions. Conditions for quantitative extraction and stripping were found out for the actinide ions other than UO 2 2+ which is poorly extracted. Solvent extraction studies were carried out at varying concentrations of the extractant and nitric acid using Am(III) and were compared with the results obtained with TODGA ( N, N, N′, N′-tetraoctyldiglycolamide), a representative diglycolamide extractant proposed for actinide partitioning. The extracted species was found out to be Am(NO 3) 3·2T-DGA (o) at higher T-DGA concentrations, while mixed 1:1 and 1:2 species were observed at lower T-DGA concentrations. The prevalence of 1:2 species in the present case as compared to the 1:1 species reported in a similar system was attributed to the low dielectric constant diluent medium used in the present study. Supported liquid membrane studies were also carried out using the T-DGA under varying feed acidities, carrier extractant concentration and compared with TODGA under identical conditions. The transport rates are dependent on the strippant used in the receiver phase and a 0.01 M EDTA solution (pH 3.0) was found to yield quantitative transport of Am(III) using T-DGA as compared to dilute nitric acid, which was efficiently used for the TODGA system in an earlier study. The transport efficiency of the carrier solvent system was Am(III) > Pu(IV) ≫ Np(IV) > UO 2 2+. The diffusion parameters were calculated for the T-DGA system and compared with the experimentally determined parameters.

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