Mechanical Behavior of Neutron Inrradiated High Cr Ferritic-Martensitic Steels

Abderrahim Al Mazouzi, Enrico Lucon, Hamid Aït Abderrahim

    Research outputpeer-review


    High Chromium Ferritic-Martensitic steels are candidate materials for the target spallation source and the fuel cladding tubes in the European demonstrator of the accelerator driven system (ADS). In this work, we will present new results obtained from the irradiation campaign that has been performed in the BR2 reactor within the SPIRE project to assess the mechanical behaviour of several standard 9-12%Cr steels. The irradiations have been performed up to 4.5 dpa at 200°C. A quantitative assessment of the effects of neutron irradiation, in terms of both hardening ) and embrittlement is presented, based on the comparison with the unirradiated
    Original languageEnglish
    Pages (from-to)73-74
    JournalThe Journal of The Minerals, Metals & Materials Society
    Issue number3
    StatePublished - 14 Oct 2005

    Cite this