Effect of low dose neutron irradiation on the tensile and fracture properties of SA 316L austenitic stainless steel

    Research outputpeer-review

    Abstract

    Austenitic stainless steels are extensively used in reactor component technology for both fission and fusion reactor systems. Although well characterized from many aspects, their fracture behavior upon irradiation is often poorly characterized. Literature data show that the most drastic changes resulting
    from irradiation damage are located in the low dose range, typically below 5 dpa. On the other hand, the experimental data scatter is large because of the variety of materials, their irradiation and their testing conditions. In the present work, the focus is on the range between 0 and 1 dpa where data are missing. We irradiated the SA 316L stainless steel in the high flux BR2 reactor at about 290°C to different neutron dose levels ranging from 0 to less than about 1 dpa. Tensile and precracked Charpy specimens were tested before and after irradiation at room and irradiation temperature. The test results are critically analyzed to provide better understanding of irradiation effects on the flow and fracture properties of austenitic stainless steels.
    Original languageEnglish
    Title of host publicationInternational Symposium Contribution of Materials Investigations and Operating Experience to LWRs’ Safety, Performance and Reliability
    Subtitle of host publicationFontevraud-10
    Pages1-14
    Number of pages14
    Edition2022
    StateAccepted/In press - 5 Oct 2022
    Event2022 - FONTEVRAUD 10: Contribution of Materials Investigations and Operating Experience to LWRs’ Safety, Performance and Reliability - Palais des Papes, Avignon
    Duration: 19 Sep 202222 Sep 2022
    https://www.sfen.org/evenement/fontevraud-10/

    Conference

    Conference2022 - FONTEVRAUD 10
    Abbreviated titleFontevraud 10
    Country/TerritoryFrance
    CityAvignon
    Period2022-09-192022-09-22
    Internet address

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