STP956: The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys

    Braski, DN
    Research staff member, Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN

    Pages: 20    Published: Jan 1987


    Abstract

    Specimens of V-15Cr-5Ti, VANSTAR-7, and V-3Ti-1Si were encapsulated in molybdenum alloy tubes containing 7Li to prevent interstitial pickup and irradiated in the Fast Flux Test Facility (FFTF), using Materials Open Test Assembly (MOTA) experiments, to a damage level of 40 displacements per atom (dpa). The irradiation temperatures were 420, 520, and 600°C. For a better simulation of fusion reactor conditions, helium was preimplanted in some specimens using a modified version of the “tritium trick.” The V-15Cr-5Ti alloy was most susceptible to irradiation hardening and helium embrittlement, followed by VANSTAR-7, and V-3Ti-1Si. VANSTAR-7 exhibited a relatively high maximum void swelling of ∼6% at 520°C while V-15Cr-5Ti and V-3Ti-1Si had values of <0.3% at all three temperatures. The V-3Ti-1Si clearly outperformed the other two vanadium alloys in resisting the effects of neutron irradiation.

    Keywords:

    vanadium alloys, neutron irradiation, irradiation hardening, helium embrittlement, void swelling


    Paper ID: STP25656S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP25656S


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