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Sorption of uranium from alkaline waste onto radiation grafted phosphoryl-g-Teflon matrix

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Abstract

High energy 60Co γ-radiation was used to graft glycidylmethacrylate onto Teflon scrap through mutual radiation grafting technique. The epoxy ring of grafted polyGMA chains were later converted to U selective phosphoryl group, chemically. The grafted matrix was used as solid–liquid adsorbent of uranium from alkaline waste solution. More than 98% recovery of uranium from alkaline waste (~pH 8) solution was achieved. The effect of grafting extent on adsorption kinetics was also investigated. The selectivity of uranium extraction over other fission products was established. The uptake of other fission products was <5% for equilibration time of ~1 h.

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Authors and Affiliations

  1. Fuel Reprocessing Division, Bhabha Atomic Research Centre, Trombay, Mumbai, 400 085, India

    S. T. Jadhav, S. K. Misra, P. S. Dhami & P. M. Gandhi

  2. Radiation Technology Development Division, Bhabha Atomic Research Centre, Trombay, Mumbai, 400 085, India

    C. V. Chaudhari & Y. K. Bhardwaj

Authors
  1. S. T. Jadhav
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  2. C. V. Chaudhari
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  3. Y. K. Bhardwaj
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  4. S. K. Misra
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  5. P. S. Dhami
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  6. P. M. Gandhi
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Correspondence to S. K. Misra.

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Jadhav, S.T., Chaudhari, C.V., Bhardwaj, Y.K. et al. Sorption of uranium from alkaline waste onto radiation grafted phosphoryl-g-Teflon matrix. J Radioanal Nucl Chem 312, 413–419 (2017). https://doi.org/10.1007/s10967-017-5236-8

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  • DOI: https://doi.org/10.1007/s10967-017-5236-8

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