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Irradiation of experimental fuel assemblies with uranium-plutonium nitride fuel and shells made of ferritic- martensitic steel EP823-Sh is conducted in order to ensure normal operation of BREST-OD-300 fuel rods in the BOR-60 and BN-600 reactors. This article presents the results of an investigation of the short-time mechanical properties of fuel rod cladding made of EP823-Sh steel after irradiation in BOR-60 and BN-600 reactors at temperatures 315–610°C up to maximum damaging dose 94 dpa, obtained for circular and longitudinal segmented samples. Empirical temperature dependences are proposed for the ultimate strength and total relative elongation of the irradiated EP823-Sh steel. [ABSTRACT FROM AUTHOR]

Reactor tests in BN-600 and post-reactor studies of experimental FA of fuel rods with mixed nitride fuel and different cladding are being conducted in Project Breakthrough. In the present article, the irradiation parameters of fuel rods with mixed nitride fuel and cladding made from ChS68-ID c.d. austenitic steel are presented: maximum linear power density 38.3 kW/m, maximum fuel burnup 7.5% h.a., and maximum damage dose 73.6 dpa. No depressurization of the fuel elements was recorded. The results of post-reactor examination (PIE) of the irradiated fuel rods are presented – swelling, gas release from fuel, and mechanical and corrosion characteristics of the cladding. [ABSTRACT FROM AUTHOR]