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Direct burn-up determination of fast reactor mixed oxide (MOX) fuel by preferential evaporation of interfering elements

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Abstract

Spent fuel of uranium–plutonium mixed oxide (MOX) from sodium cooled Fast Breeder Test Reactor (FBTR) was analyzed for at.% burn-up by preferential evaporation method. A sequential pattern of analysis of fission monitor Nd and heavy elements, U and Pu provided an un-interfered isotopic composition. Concentrations of individual elements were determined by isotopic dilution mass spectrometry. The proposed method provides at.% burn-up with an uncertainty of about 4% (compared to ASTM method), is less time consuming, does not involve any chemical separation, reduction in radioactive waste and substantial reduction in the radiation exposure to analyst.

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Authors and Affiliations

  1. Chemistry Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, 603102, India

    R. Sajimol, S. Bera, N. Sivaraman & M. Joseph

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  1. R. Sajimol
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  2. S. Bera
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  3. N. Sivaraman
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  4. M. Joseph
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Correspondence to M. Joseph.

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Sajimol, R., Bera, S., Sivaraman, N. et al. Direct burn-up determination of fast reactor mixed oxide (MOX) fuel by preferential evaporation of interfering elements. J Radioanal Nucl Chem 311, 1593–1603 (2017). https://doi.org/10.1007/s10967-016-5152-3

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  • DOI: https://doi.org/10.1007/s10967-016-5152-3

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