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Showing 1 to 5 of 5 for “"F/M steels"”.

  1. Irradiation damage in neutron-irradiated Fe-Cr model alloys

    Ferritic-martensitic (F-M) steels are considered as lead candidate structural materials for Generation IV fission reactors and future fusion reactors. Compared to austenitic stainless steels, these steels have superior properties in thermal conductivities and thermal expansion coefficients. In …

    uiuc Repository record for Irradiation damage in neutron-irradiated Fe-Cr model alloys (opens in a new tab)

  2. Advanced characterization of the early-stage evolution of microstructures and mechanical properties in neutron-irradiated commercial steels

    … of two types of Fe-Cr ferritic-martensitic (F-M) steels, HT9 and T91, were characterized. The materials were irradiated in the Advanced Test Reactor (ATR) at different temperatures and neutron fluences. Three temperature ranges and four neutron dose levels were investigated in this study. …

    uiuc Repository record for Advanced characterization of the early-stage evolution of microstructures and mechanical properties in neutron-irradiated commercial steels (opens in a new tab)

  3. Microstructure Evolution of Two Model Ferritic/Martensitic Steels Under Ion Irradiation In A Transmission Electron Microscope

    <p>Ferritic/martensitic steels are candidate materials for structural and cladding components designed for Generation IV reactors because of their superior resistance to radiation damage at the high operating temperatures envisioned in these reactors. To enable the development and optimization of …

    south-carolina Repository record for Microstructure Evolution of Two Model Ferritic/Martensitic Steels Under Ion Irradiation In A Transmission Electron Microscope (opens in a new tab)

  4. Role of nitrogen in the structure and properties of proton irradiated 12Cr1MoWV ferritic/martensitic steel for advanced nuclear reactor cores, The

    … context of irradiation environments for these steels is critical. Nitrogen content has been hypothesized to have a significant effect on the irradiated properties of alloy HT9. In this work, three otherwise similar alloys of HT9 with varying N contents (10 ppm, 190 ppm, 440 ppm N) are …

    colo-mines Repository record for Role of nitrogen in the structure and properties of proton irradiated 12Cr1MoWV ferritic/martensitic steel for advanced nuclear reactor cores, The (opens in a new tab)

  5. Radiation-induced microstructural and mechanical property modifications in advanced alloys

    … hardening behavior of neutron-irradiated F/M steels. The neutron radiation response of ferritic ODS steel MA957 was studied using TEM and APT. The size distribution of the Y–Ti–O nanoclusters became narrower with increasing dose, with concurrent decrease in the peak Ti and O concentrations. …

    uiuc Repository record for Radiation-induced microstructural and mechanical property modifications in advanced alloys (opens in a new tab)