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Showing 1 to 5 of 5 for “"HT9"”.

  1. The relationship between mechanical properties and microstructure of HT9 steel

    … flux), and corrosion from liquid metal coolants. HT9, a ferritic/martensitic alloy, was used in previous fast research reactors (such as EBR-II and FFTF). However, it needs validation before it can be selected for use in the more extreme environments of Gen–IV reactors. This dissertation presents …

    uiuc Repository record for The relationship between mechanical properties and microstructure of HT9 steel (opens in a new tab)

  2. Characterization of bending fatigue mini-specimens for nuclear materials

    … were made of austenitic SS304, SS316, HT9 ferritic martensitic steel, and Incoloy alloy MA956 oxide dispersion strengthens (ODS). A comparison between the mini-specimens and the standard specimen ASTM B593 had similar design but a smaller size. The bending fatigue machine VSS-40H was …

    must-thes Repository record for Characterization of bending fatigue mini-specimens for nuclear materials (opens in a new tab)

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

    The 12Cr1MoWV (wt%) ferritic/martensitic steel HT9 is a candidate material for fuel cladding in advanced nuclear reactors, such as the Versatile Test Reactor, currently under development. As such, understanding the relationship between microstructure and mechanical properties in the context of …

    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)

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

    … 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. Utilizing …

    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)

  5. Probabilistic transient analysis of fuel choices for sodium fast reactors

    … cladding type (stainless steel 316, D9 or HT9), linear power, plutonium enrichment and burnup. This thesis improves the modeling accuracy of eutectic formation through the application of multivariable regression using a database of fuel/cladding eutectic experiments and determines that the …

    mit Repository record for Probabilistic transient analysis of fuel choices for sodium fast reactors (opens in a new tab)