Materials of ITER divertor - Behaviour of tungsten and carbon under ionic irradiation and high temperature

In the carrying out of the international ITER project, several different problems are to be solved. Among them, the physico-chemical characterization of the components facing the plasma (structure and divertor materials) is essential because these materials are submitted to high thermal and ionic fluxes. Here is presented a preliminary experimental and theoretical study of the physico-chemical behaviour of graphite and tungsten (materials retained in the design of ITER divertor) in extreme experimental simulated conditions (running in nominal operating or accidental conditions): high temperatures (T≥2500 K), ultra-vacuum and ionic irradiation (H+). The material damage, the mass loss kinetics, the characterization of the species coming from the material after irradiation and after having been submitted to high temperatures as well as the reflectivity properties are studied. (O.M.)