Overview of the Structural Materials Program for Fusion Reactors Under EFDA

The Fusion Materials Topical Group (FMTG) coordinates, under the European Fusion Development Agreement (EFDA), the EU effort on the development of structural and protection materials for the very demanding operating conditions of a future DEMO reactor. The reference documents for this program are the European Roadmap for Fusion and the Materials Assessment Group (MAG) report. The FMTG work or EFDA work is structured as follows: a) Integrated radiation effects modelling and experimental validation: focused on the development of a conceptual and quantitative framework for the interpretation of experimental tests on steels and iron-based alloys and tungsten and tungsten alloys and predicting the performance of these materials under DEMO-relevant operating conditions. b) High heat flux materials: focused on the development of materials for armour applications (W alloys), structural applications for low and high temperature cooling concepts (Cu-based alloys, W-based alloys), materials technologies (joining, fabrication), and testing of prototype of cooling structures. c) Nano-structured oxide dispersion strengthened (ODS) ferritic steel development: focused on the development of an ODS ferritic steel with high tensile and creep strength and sufficient ductility and fracture toughness up to about 750°C, as well as good radiation resistance. d) Materials database status and needs for DEMO conceptual design activities: focused on the assessment and analysis of fusion materials available data, identifying areas of uncertainties and conditions (relevant to the design) where data are either missing or unreliable.