Investigation of the thermo-mehcanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory

Xiazi Xiao, Dmitry Terentyev, Alexander Bakaev, Long Yu, Zhaohui Jin, Huiling Duan

    Research outputpeer-review


    The thermo-mechanical behavior of non-irradiated (at 223 K, 302 K and 573 K) and neutron irradiated (at 573 K) Fe-2.5Cr, Fe-5Cr and Fe-9Cr alloys is studied by a self-consistent plasticity theory, which consists of constitutive equations describing the contribution of radiation defects at grain level, and the elasticviscoplastic self-consistent method to obtain polycrystalline behaviors. Attention is paid to two types of radiation-induced defects: interstitial dislocation loops and solute rich clusters, which are believed to be the main sources of hardening in Fe-Cr alloys at medium irradiation doses. Both the hardening mechanism and microstructural evolution are investigated by using available experimental data on microstructures, and implementing hardening rules derived from atomistic data. Good agreement with experimental data is achieved for both the yield stress and strain hardening of non-irradiated and irradiated Fe-Cr alloys by treating dislocation loops as strong thermally activated obstacles and solute rich clusters as weak shearable ones.
    Original languageEnglish
    Pages (from-to)123-133
    Number of pages10
    JournalJournal of Nuclear Materials
    StatePublished - 15 Aug 2016

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