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Current R&D activities on materials for fusion power reactors are mainly focused on plasma facing, structural and tritium breeding materials for plasma facing (first wall, divertor) and breeding blanket components. Most of these activities are being performed in Europe, Japan, the People's Republic of China, Russia and the USA. They relate to the development of new high temperature, radiation resistant materials, the development of coatings that will act as erosion, corrosion, permeation and/or electrical/MHD barriers, characterization of candidate materials in terms of mechanical and physical properties, assessment of irradiation effects, compatibility experiments, development of reliable joints, and development and/or validation of design rules. Priorities defined worldwide in the field of materials for fusion power reactors are summarized, as well as the main achievements obtained during the last few years and the near-term perspectives in the different investigation areas.

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Transmission electron microscopy (TEM) as well as corresponding analytical techniques, such as high resolution TEM (HRTEM), energy dispersive X-ray (EDX) analysis, electron energy loss spectroscopy (EELS) and elemental mapping via a Gatan imaging filter (GIF), have been used to study the complex precipitation morphology of the commercial Fe-Cr-Al based oxide dispersion strengthened (ODS) alloy PM 2000. Formation of homogeneously distributed Y-Al-O ODS particles from Y 2 O 3 added to the metal powder is shown. Besides these ODS particles, a large amount of complex Y-Al-O/Al 2 O 3 and Y-Al-O/TiC as well as pure Al 2 O 3 inclusions with sizes significantly larger than ODS particles have been identified. A typical feature is the growth of Al 2 O 3 and Y-Al-O particles on the surface of small Ti(C,N) nuclei. Some implications of the results obtained from the mechanical properties of PM 2000 steel are discussed.