Materials design data for reduced activation martensitic steel type EUROFER

A. A.F. Tavassoli, Ana Alamo, L. Bedel, L. Forest, J. M. Gentzbittel, J. W. Rensman, E. Diegele, R. Lindau, M. Schirra, R. Schmitt, H. C. Schneider, C. Petersen, A. M. Lancha, Pilar Fernandez, G. Filacchioni, M. F. Maday, K. Mergia, N. Boukos, Baluc, P. SpätigE. Alves, E. Lucon

    Research outputpeer-review

    Abstract

    Materials design limits derived so far from the data generated in Europe for the reduced activation ferritic/martensitic (RAFM) steel type Eurofer are presented. These data address the short-term needs of the ITER Test Blanket Modules and a DEMOnstration fusion reactor. Products tested include plates, bars, tubes, TIG and EB welds, as well as powder consolidated blocks and solid-solid HIP joints. Effects of thermal ageing and low dose neutron irradiation are also included. Results are sorted and screened according to design code requirements before being introduced in reference databases. From the physical properties databases, variations of magnetic properties, modulus of elasticity, density, thermal conductivity, thermal diffusivity, specific heat, mean and instantaneous linear coefficients of thermal expansion versus temperature are derived. From the tensile and creep properties databases design allowable stresses are derived. From the instrumented Charpy impact and fracture toughness databases, ductile to brittle transition temperature, toughness and behavior of materials in different fracture modes are evaluated. From the fatigue database, total strain range versus number of cycles to failure curves are plotted and used to derive fatigue design curves. Cyclic curves are also derived and compared with monotonic hardening curves. Finally, irradiated and aged materials data are compared to ensure that the safety margins incorporated in unirradiated design limits are not exceeded.

    Original languageEnglish
    Title of host publicationProceedings of the 11th International Conference on Fusion Reactor Materials (ICFRM-11)
    Pages257-262
    Number of pages6
    Volume329-333
    Edition1-3 PART A
    DOIs
    StatePublished - 1 Aug 2004
    Event2003 - ICFRM-11: 11th International Conference on Fusion Reactor Materials - Kyoto
    Duration: 7 Dec 200312 Dec 2003

    Publication series

    NameJournal of Nuclear Materials
    PublisherElsevier
    ISSN (Print)0022-3115

    Conference

    Conference2003 - ICFRM-11
    Country/TerritoryJapan
    CityKyoto
    Period2003-12-072003-12-12

    ASJC Scopus subject areas

    • Nuclear and High Energy Physics
    • General Materials Science
    • Nuclear Energy and Engineering

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