Thermal testing of shortened fuel rods with 42KhNM chromium–nickel alloy cladding, pre-irradiated in the MIR reactor to fission product content 0.9 g/cm3, was conducted at SSC RIAR. The mechanism of fuel rod depressurization was determined. It was shown that depressurization is associated with changes occurring in the fuel kernel at an elevated temperature, while in the 42KhNM alloy cladding practically no structural changes occur on holding for 1 h at 600°C. A relation is obtained for evaluating the possibility of and time to depressurization of a fuel rod at a specified temperature taking preliminary irradiation into account.
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Translated from Atomnaya Énergiya, Vol. 130, No. 4, pp. 208–211, April, 2021.
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Kulakov, G.V., Konovalov, Y.V., Vatulin, A.V. et al. High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding. At Energy 130, 220–223 (2021). https://doi.org/10.1007/s10512-021-00798-5
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DOI: https://doi.org/10.1007/s10512-021-00798-5