From materials development to their test in IFMIF: an overview
R&D; activities on fusion reactor materials in Switzerland focus on (1) the development of advanced metallic materials for structural applications in plasma-facing (first wall, divertor) and breeding blanket components of the future fusion power reactors, in particular oxide dispersion strengthened reduced activation ferritic steels and tungsten-base materials, (2) the modelling of radiation damage and radiation effects and (3) small specimen test technology for the future International Fusion Materials Irradiation Facility. The main objectives, examples of recent results and future activities are described in the case of these three R&D; areas.
Keywords: Material Irradiation Conditions ; Master-Curve Analysis ; Fracture-Toughness ; Molecular-Dynamics ; Mechanical-Properties ; Structural-Materials ; Transition-Metals ; Fusion Materials ; Eurofer97 Steel ; Bcc Tungsten
Record created on 2011-10-17, modified on 2016-08-09