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

    Published: Jan 1992

      Format Pages Price  
    PDF () 10 $25   ADD TO CART
    Complete Source PDF (28M) 10 $264   ADD TO CART


    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.


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

    Author Information:

    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,

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP17939S

    CrossRef ASTM International is a member of CrossRef.