STP1175

    Exploratory Studies of the Effects of Irradiation Temperature on Mechanical Properties of Structural Steels amd Welds

    Published: Jan 1994


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    Abstract

    The influence of irradiation temperature on the extent of change in Charpy-V (Cv) notch ductility and tension test properties of low alloy structural steels and welds was explored for reactor vessel applications. Specimens were irradiated at 288°C and 316°C in temperature-controlled assemblies in the Ford Nuclear Reactor (FNR) at the University of Michigan. Irradiation at 316°C to 7.9 × 1018 n/cm2, E > 1 MeV, produced 41-J temperature elevations that were on average 51% of those produced by 260°C irradiation. Thermal aging at 316°C for 5000 h had little effect on Cv and tension test properties. NRC Regulatory Guide 1.99 Rev. 2 projections for irradiation-induced embrittlement at 288°C are compared to the experiment measurements.

    Keywords:

    pressure vessel steels, nuclear reactors, low alloy steels, submerged arc welds, radiation embrittlement, notch ductility, tensile properties, radiation sensitivity, neutron irradiation, Regulatory Guide 1.99


    Author Information:

    Hawthorne, JR
    Materials Engineering, Lanham, MD


    Paper ID: STP23944S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP23944S


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