REVIEW ON PLASMA-FACING MATERIALS AND SUITABLE DIVERTOR CONFIGURATION OF A FUSION EXPERIMENTAL REACTOR

The characteristics of the graphite as plasma facing material are reviewed and the problems of the graphite for the plasma performance are pointed out. The capabilities of low atomic number materials such as boron and beryllium are shown briefly and the limits in use of B or Be as the plasma facing component are presented. It is then summarized that the achievement of burning plasma condition with a long time period in a fusion experimental reactor such as ITER becomes difficult only by the development of the plasma facing materials. In order to successfully achieve such burning plasma, a scheme with the enlarged divertor configuration is proposed for the reduction of the heat flux to the divertor. The present scheme is also compared with other schemes for the reduction of the heat flux.