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Analysis of uranium in dissolver solution of fast reactor carbide fuel reprocessing

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Abstract

Uranium in simulated dissolver solution of FBTR mixed carbide fuel containing fission products is analyzed by modified Davies–Gray method. The uranium is analyzed after the sample is evaporated with 1 M H2SO4 and followed all the steps carried out by Davies–Gray method. The proposed method assures analysis of uranium in dissolver solution of FBTR fuel can be titrated directly without prior separation of fission products.

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Authors and Affiliations

  1. Reprocessing Research and Development Division, Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, 603102, India

    A. Chinnusamy, P. Velavendan, S. Ganesh, N. K. Pandey, U. K. Mudali & R. Natarajan

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  1. A. Chinnusamy
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  2. P. Velavendan
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  3. S. Ganesh
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  4. N. K. Pandey
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  5. U. K. Mudali
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  6. R. Natarajan
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Correspondence to A. Chinnusamy.

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Chinnusamy, A., Velavendan, P., Ganesh, S. et al. Analysis of uranium in dissolver solution of fast reactor carbide fuel reprocessing. J Radioanal Nucl Chem 300, 115–119 (2014). https://doi.org/10.1007/s10967-014-2951-2

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  • DOI: https://doi.org/10.1007/s10967-014-2951-2

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