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SiC f /SiC is identified as a potential structural material in a future DEMO fusion reactor due to its corrosion resistance, low neutron activation, chemical stability, attractive high temperature mechanical properties and reasonably good thermal conductivity. Last, but not least, SiC f /SiC composite is the only non-magnetic material among the candidate structural materials. Despite its promising properties, there are issues to be addressed under intensive neutron irradiation, such as decrease in thermal conductivity, swelling and degradation of the mechanical properties. Therefore, the main challenge in general is designing a composite material with high radiation resistance and optimum strength and thermal conductivity for applications in a fusion power reactor. This work addresses high temperature mechanical and physical property characterisation of unirradiated 2D and 3D Tyranno SA 3 fibre reinforced silicon carbide composites (SiC f /SiC). The paper summarizes the results of an extensive multiannual programme, started in 2004 and performed at NRG within the framework of the European Fusion Development Agreement (EFDA). The study serves as a pre-irradiation investigation and basis for comparison with the test results to be produced on irradiated SiC f /SiC material, as well as to qualify the test procedures to be used for post-irradiation examination. [ABSTRACT FROM AUTHOR]

The silicon carbide fiber-reinforced silicon carbide matrix (SiC/SiC) composite system for fusion applications has seen a continual evolution from development a fundamental understanding of the material system and its behavior in a hostile irradiation environment to the current effort which is directed at a broad-based program of technology maturation program. In essence, over the past few decades this material system has steadily moved from a laboratory curiosity to an engineering material, both for fusion structural applications and other high performance application such as aerospace. This paper outlines the recent international scientific and technological achievements towards the development of SiC/SiC composite material technologies for fusion application and discusses future research directions. It also reviews the materials system in the larger context of progress to maturity as an engineering material for both the larger nuclear community and broader engineering applications. [ABSTRACT FROM AUTHOR]