Post-reactor studies of experimental fuel pins with mixed nitride uranium-plutonium fuel and EP823-Sh, ChS68-ID kh.d., and EK164-ID kh.d. steel cladding, which have been irradiated in BOR-60 and BN-600 reactors, indicated the nitriding and carburization of the cladding inner layer, which leads to an increase in its microhardness and a reduction in ductility characteristics. In fuel pin claddings, made of ChS68-ID kh.d. and EK164-ID kh.d. austenitic steel, the processes of carburization and nitriding correlate with sample destruction during mechanical tests. The present article generalizes and analyzes the results of post-reactor studies concerning the carburization and nitriding of the fuel pin claddings made of ChS68-ID kh.d., EK164-ID kh.d., and EP823-Sh steel. The carburization and nitriding of the cladding inner surface was studied by electron microprobe analysis using the cross-sections of fuel pins.
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Translated from Atomnaya Énergiya, Vol. 133, No. 2, pp. 88–92, August, 2022.
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Porollo, S.I., Marinenko, E.E., Kryukov, F.N. et al. Nitriding and Carburization of a Mixed Nitride Uranium-Plutonium Fuel Pin Cladding. At Energy 133, 92–97 (2022). https://doi.org/10.1007/s10512-023-00978-5
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DOI: https://doi.org/10.1007/s10512-023-00978-5