Materials Irradiation Testing in Support of the European Fusion Programme

Abstract

The objectives and planned schedule of the Next European Torus (NET) programme are outlined and the selection of materials for some of the principal components (first wall and tritium breeding blanket, first wall protection, impurity control system and insulators) is discussed in the light of the currently envisaged parameters. The materials irradiation programmes which are either being implemented or are proposed to provide essential data for the detailed design and construction of NET and for assessing component performance and endurance are summarized. Finally, the longer-term programme which should be undertaken to enhance the knowledge of the behaviour of materials in a fusion environment and to guide the development of materials for a DEMO fusion power reactor is indicated.