Untersuchung von Kohlenstoff-Werkstoffen und Wolfram-Legierungen für den Divertor zukünftiger Forschungsreaktoren

In future fusion devices the components and materials will be subjected to severe thermal loads due to particle and heat fluxes . In addition to these thermal loadings, the material damage caused by fast neutrons changes the physical and chemical properties of the materials. Carbon materials and tungsten alloys are seen as possible candidates for use in the region of the divertor where these extreme loadings will occur. In this work the thermal shock behaviour of different graphite grades, carbon fibre reinforced carbon materials and tungsten alloys have been investigated before and after neutron irradiation . Short time, pulsed, high heat flux loadings (thermal shock) occurring during plasma instabilities such as disruptions in tokamak operation, were simulated in a electron beam facility . The influence of neutron irradiation on the erosion behaviour of carbon materials and tungsten alloys was investigated . It was shown that neutron irradiation does not ficantly and therefore the use of these materials in a echers* anfred R6 Furthermore the screening and thermal fatigue behaviour of components was analysed and the egrity of the tested bond layers of CFC materials to metallic heat sinks under severe thermo-mechanical loadings was demonstrated. For the tungsten module tested in the same manner, however, catastrophic failure occurred during the screening tes