STP870: Evaluation of Ferritic Alloy Fe-2¼Cr-1Mo After Neutron Irradiation: Irradiation Creep and Swelling

    Gelles, DS
    Principal engineer and senior scientist, Westinghouse Hanford Company, Richland, WA

    Puigh, RJ
    Principal engineer and senior scientist, Westinghouse Hanford Company, Richland, WA

    Pages: 19    Published: Jan 1985


    Abstract

    Irradiation creep and swelling measurements are reported for Fe-2¼Cr-1Mo after irradiation by fast neutrons over the temperature range 390 to 560°C. Diameter change measurements on thin-walled pressurized tubes in a bainitic condition and density change measurements on rods in a nonstandard condition were made following irradiation in the Experimental Breeder Reactor II. The irradiation creep specimens were irradiated to a fluence of 5.7 × 1022 neutrons (n)/cm2 (E > 0.1 MeV) or 30 displacements per atom (dpa) and the swelling specimens were irradiated to a peak fluence of 2.4 × 1023 n/cm2 or 115 dpa. These results have been used as a basis to establish in-reactor creep and swelling correlations for 2¼Cr-1Mo in a bainitic condition. The correlations predict moderate swelling and moderate irradiation enhanced creep at 390°C. The in-reactor creep at 570°C indicates that thermal creep mechanisms become important at this irradiation temperature.

    Keywords:

    irradiation creep, thermal creep, swelling, swelling-enhanced creep, design correlations, swelling equation, in-reactor creep equation, radiation, Fe-2¼Cr-1Mo


    Paper ID: STP37350S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP37350S


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