摘要
According to the present design of ITER,the divertor armor is consisted predominantly of carbon fiber composites and tungsten(W)with carbon coatings in the areas subject to the highest heat load[1].Due to sputtering and subsequent re-deposition,mixing of these materials will occur.Studying radiation damage in tungsten carbide(WC)is of importance both due to its applications of plasma facing materials and due to the presence of WC in the divertor of fusion reactors[2].
