From Materials Development to their Test in IFMIF: an Overview

N. Baluc, R. Schäublin, P. Spätig, J. Theile, M.Q. Tran

Ecole Polytechnique Fédérale de Lausanne (EPFL), Centre de Recherches en Physique des
Plasmas, Association Euratom-Confédération Suisse, Switzerland

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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.