Testing of neutron-irradiated plasma facing components

in order to study degradation effects of neutrons on plasma-facing material s and joints, actively-cooled CFC monoblock mock-ups were irradiated in the High Flux Reactor in Petten up to 0.35 dpa at 350 and 750 degrees C. Later , these samples were tested by means of an electron beam facility under sta tic and cyclic heating conditions. The heat removal efficiency and the ther mal fatigue behavior of these samples were compared to those of correspondi ng non-irradiated samples. A significant increase of surface temperature wa s observed for all CFC samples, due to a reduced thermal conductivity of th e materials after neutron irradiation. This effect is less distinctive for samples irradiated at the higher temperature. Long term fatigue tests with 1000 heating cycles at 15 MW/m(2) did not create any failure of the plasma- facing material or the bond layer of the tested mock-ups.