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Estimation of neptunium in a fuel reprocessing plant

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Abstract

The solutions at various stages of the purex process used at Trombay have been analysed for their237Np content to know the path of neptunium in the process. The results of these analyses, though not very quantitative, revealed that in the co-decontamination cycle, neptunium is extracted along with uranium and plutonium almost quantitatively while in the partitioning cycle the extraction is reduced to about 50%. Analysis of various oxidation states of neptunium in the feed of the first cycle showed that neptunium is predominantly present as Np(V).

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Authors and Affiliations

  1. Fuel Reprocessing Division, Bhabha Atomic Research Centre, Trombay, Bombay, (India)

    N. Srinivasan

  2. Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Bombay, (India)

    M. V. Ramaniah, S. K. Patil & V. V. Ramakrishna

Authors
  1. N. Srinivasan
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  2. M. V. Ramaniah
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  3. S. K. Patil
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  4. V. V. Ramakrishna
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Srinivasan, N., Ramaniah, M.V., Patil, S.K. et al. Estimation of neptunium in a fuel reprocessing plant. J. Radioanal. Chem. 8, 223–229 (1971). https://doi.org/10.1007/BF02518186

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  • DOI: https://doi.org/10.1007/BF02518186

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