Irradiation of Fusion Materials in the BR2 Reactor: the FRISCO-F Experiment

Enrico Lucon, Johan Schuurmans

    Research outputpeer-review


    Tensile and miniature Compact Tension specimens of eight high chromium steels of fusion relevance have been irradiated in the BR2 reactor in the framework of a collaborative project between Oak Ridge National Laboratory (ORNL) and SCK•CEN. All samples have been irradiated at a nominal temperature of 300 °C in the in-pile section 2 (IPS-2) for five cycles (02/2005 to 01/2006) up to an average fast neutron fluence of 8.02 × 10^20 n/cm² or 1.20 dpa. The rig was rotated three times by 180° in order to reduce the radial and azimuthal neutron flux gradients.
    Original languageEnglish
    PublisherSCK CEN
    Number of pages9
    StatePublished - 19 Jun 2006

    Publication series

    NameSCK•CEN Reports
    PublisherStudiecentrum voor Kernenergie

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