Evaluation of the BR3 third core vessel steel specimens

P. De Meester, Philippe Van Asbroeck, José Van de Velde, Constantinus Van Loon, L. Laurent

    Research outputpeer-review

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    Abstract

    Second and third core pressure vessel steel samples have been tested after irradiation. The shift in N.D.T. -30 fr-lb. for samples being irradiated for an integrated dose up to 8.5 * 1020 nvt is 305° C. Considering the sample positions, it can be concluded that in the BR3 vessel after Vulcain core 2bis, brittleness could occur from the temperature range 60 - 95°C, and after Vulcain core 3 from the temperature range 70 - 100* C. It should therefore be preferable to avoid high pressure and specially sharp pressure transients even at relatively lo« absolute pressures, below that given temperature range increased by a safety factor.
    Original languageEnglish
    PublisherSCK CEN
    Number of pages22
    StatePublished - Jul 1971

    Publication series

    NameSCK CEN Reports
    PublisherSCK CEN
    No.BLG-459

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