The microstructure and tensile properties of fuel pin cladding fabricated from ferritic 1Cr13Mo2NbVB steel irradiated in the BN-350 fast reactor up to a peak dose of 60 dpa at temperatures of 285 to 710°C have been investigated. A peak swelling of 0.3% was found after neutron irradiation to 47 dpa at an irradiation temperature of420°C. Irradiation-induced precipitates of α′, chi, and M2X phases have been observed and characterized. The largest strengthening and embrittlement of the steel were found after irradiation at T < 350°C. For dislocation loops, voids, and α′-particles, temperature and dose dependences of sizes and number densities were established. The dose and temperature dependencies of tensile strength and ductility are reported.
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