STP1125: The Effect of Neutron Irradiation on the Microstructure and Tensile Properties of 1 Cr13Mo2NbVB Steel

    Dvoriashin, AM
    Institute of Physics and Power Engineering, Obninsk,

    Dmitriev, VD
    Institute of Physics and Power Engineering, Obninsk,

    Khabarov, VS
    Institute of Physics and Power Engineering, Obninsk,

    Pages: 10    Published: Jan 1992


    Abstract

    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.

    Keywords:

    ferritic steel, neutron irradiation, microstructure, tensile properties, irradiation temperature, displacement dose, dislocation loops, α′-phase, swelling


    Paper ID: STP17939S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP17939S


    CrossRef ASTM International is a member of CrossRef.