Abstract
A procedure has been developed for the determination of 232U and 236Pu content by alpha spectrometry by ion-exchange isolation and purification of uranium and plutonium fractions from irradiated fuel solution. The proposed procedure has been utilized to determine weight concentrations of 232U and 236Pu in samples of uranium oxide fuel irradiated in VVER-1000 and RBMK-1000 reactors, as well as in mixed uranium-plutonium nitride fuel irradiated in a BN-600 reactor.
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Russian Text © The Author(s), 2020, published in Radiochemistry, 2020, Vol. 62, No. 1, pp. 66–72.
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Momotov, V.N., Erin, E.A., Volkov, A.Y. et al. Determination of 232U and 236Pu Weight Contents of Spent Nuclear Fuel. Radiochemistry 62, 95–100 (2020). https://doi.org/10.1134/S1066362220010129
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DOI: https://doi.org/10.1134/S1066362220010129