Abstract
The conditions for thermochemical operations of fuel cladding embrittlement and oxidation of spent nuclear fuel with a burn-up of 60 GW day t−1 U on a Mini-Khrust installation with UO2 loading of up to 450 g were checked. The yields of volatile and gaseous activation and fission products (3H, 14C, 129I, 137Cs) released in the course of these operations were found to be 99.6, 53.8, 36.3, and less than 1%, respectively. The use of head-end thermochemical operations in fuel reprocessing allows selective recovery of tritium to more than 99%, which is the main prerequisite for the reduction of liquid radioactive waste in spent nuclear fuel reprocessing technology.
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Original Russian Text © M.M. Metalidi, S.V. Shapovalov, R.V. Ismailov, M.I. Skriplev, V.I. Beznosyuk, Yu.S. Fedorov, 2015, published in Radiokhimiya, 2015, Vol. 57, No. 1, pp. 86–89.
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Metalidi, M.M., Shapovalov, S.V., Ismailov, R.V. et al. Thermochemical embrittlement of the zirconium cladding of a fuel rod and oxidative recrystallization of the fuel material in the course of spent nuclear fuel reprocessing. Radiochemistry 57, 98–102 (2015). https://doi.org/10.1134/S1066362215010154
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DOI: https://doi.org/10.1134/S1066362215010154