Experiments performed at the Mayak Production Assiciation to determine the 232U content in spent BN-600 fuel are analyzed. Calculations show that to within the limits of error the concentration largely agrees with the measured value, which makes it possible to use the calculations for a preliminary assessment of the 232U content in batches of uranium regenerated from reprocessed spent BN-600 FA.
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Translated from Atomnaya Énergiya, Vol. 127, No. 3, pp. 137–140, September, 2019.
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Nevinitsa, V.A., Kolupaev, D.N. 232U Content Determination in Spent FA from Fast Reactor with a Uranium Load. At Energy 127, 149–152 (2020). https://doi.org/10.1007/s10512-020-00602-w
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DOI: https://doi.org/10.1007/s10512-020-00602-w