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    Irradiation Creep in Austenitic Stainless Steels at 60 to 400°C with a Fusion Reactor Helium to dpa Ratio

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    Irradiation creep was investigated in the alloys—prime candidate alloy (PCA), Japanese Fusion Energy Program (JPCA), and American Iron and Steel Institute (AISI) 316 (UNS S31600) stainless steel. Tubes pressurized to stress levels of 50 to 400 MPa were irradiated in the Oak Ridge Research Reactor (ORR) with the neutron spectrum tailored to achieve the fusion reactor helium:dpa value of 12 appm/dpa in AISI 316 stainless steel. Irradiation temperatures of 60, 330, and 400°C were investigated, and the irradiation produced 8 dpa and a maximum of about 100 appm helium. Irradiation creep rates of 2.2 to 14×104MPa1dpa1 were observed at 60°C. At 330 and 400°C irradiation creep rates of 1.3 to 3.5×104 were observed, similar to those found previously in similar experiments in the ORR. The low temperature irradiation creep was interpreted in terms of a new model for irradiation creep based on transient climb-enabled glide. The results are important in the design of experimental fusion reactors where temperatures below 100°C are being considered for the operation of high flux components.


    irradiation creep, fusion, stainless steel, creep

    Author Information:

    Grossbeck, Martin L.
    Research staff member, Oak Ridge National Laboratory, Oak Ridge, TN

    Mansur, L. K.
    Group leader, Oak Ridge National Laboratory, Oak Ridge, TN

    Tanaka, M. P.
    Principal research engineer, Japan Atomic Energy Research Institute, Tokyo,

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP49473S