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Oxidation and extraction of Am(VI) using a monoamidic extractant in 3D printed centrifugal contactors

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Abstract

A series of tests were performed using centrifugal contactors to evaluate the separation of Am(VI) from cerium, as well as to determine the efficiency of the contactors. All experiments were performed using 2-cm, acrylic 3D-printed centrifugal contactors. Solvent extraction tests were performed using 1 M N,N-di(2-ethylhexyl)butyramide (DEHBA)/dodecane and a nitric acid feed solution spiked with 243Am and 139Ce and oxidized with 60 mg mL−1 sodium bismuthate. Approximately 72% of the Am was extracted with a single contactor stage. Co-stripping of Am and Ce was demonstrated but attempts at selective stripping were not successful. Successful recycle of the used organic phase was demonstrated. Contactor efficiencies of 95–100% were obtained.

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Acknowledgements

Work was supported by the US Department of Energy, Assistant Secretary for Nuclear Energy, under the Nuclear Technology Research and Development Sigma Team for Advanced Actinide Recycle; DOE-Idaho Operations Office contract DE-AC07-05ID14517.

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Authors and Affiliations

  1. Aqueous Separations and Radiochemistry Department, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415, USA

    Jack D. Law, Bruce J. Mincher, Richard D. Tillotson, Nicholas C. Schmitt & Travis S. Grimes

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  1. Jack D. Law
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  2. Bruce J. Mincher
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  3. Richard D. Tillotson
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  4. Nicholas C. Schmitt
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  5. Travis S. Grimes
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Correspondence to Jack D. Law.

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Law, J.D., Mincher, B.J., Tillotson, R.D. et al. Oxidation and extraction of Am(VI) using a monoamidic extractant in 3D printed centrifugal contactors. J Radioanal Nucl Chem 318, 35–41 (2018). https://doi.org/10.1007/s10967-018-6126-4

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  • DOI: https://doi.org/10.1007/s10967-018-6126-4

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