Numerical Modeling for Coextraction of Tc(VII)with U(VI)by n-Octyl(phenyl)-N, N-diisobutylcarbamonylmethylphosphine Oxide from Nitric Acid Solution

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著者

    • TANAKA Satoru
    • Nuclear Engineering Research Laboratory, The University of Tokyo
    • TACHIMORI Shoichi
    • Department of Fuel Cycle Safety Research, Japan Atomic Energy Research Institute

抄録

The coextraction model of Tc(VII) and U(VI) from nitric acid solution was developed on a tributyl phosphate (TBP)/n-dodecane system involving n-octyl(pheny1)-N, N-diisobutylcarbamoyl-methylphosphine oxide (CMPO). Technetium was considered to be extracted by the formation of Tc-CMPO and U-Tc-CMPO complexes in the presence of uranium. The distribution coefficient of technetium in the presence of uranium was defined by taking these complexes into account, and expressed as a function of nitric acid concentration, free CMPO concentration, and distribution coefficient of uranium. The equation of the distribution coefficient derived was applied to the previous data obtained in the mixed system of CMPO-TBP-dodecane at the low nitric acid concentration. It was found that the distribution behavior of technetium in the presence of uranium could be successfully simulated by the present coextraction model.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 32(5), 450-455, 1995-05-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002072580
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • データ提供元
    CJP書誌  J-STAGE 
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