Abstract
Abstract Carbon-based materials are widely used for fusion reactor plasma facing components. They are characterized by a low atomic number, fair thermophysical characteristics thermal shock resistance and low neutron activation. Ignition machines such as ITER will produce high neutron fluxes and influence of neutron damage on different properties of graphites and carbon-carbon composites must be evaluated. Irradiation was performed in the Kurchatov Institute IR-8 reactor, where a 0.18 Mev neutron flux intensity reacted 1–3•1013 1/cm2•s. A peak neutron fluence of 2.6•1020 1/cm2, at temperature up to 650°C. The recrystallized graphites and four- and five- directional carbon-carbon composites were irradiated. Thermal conductivity, dimensional changes, strength and coefficient of thermal expansion are reported for the materials examined.
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