Developments of plasma facing components and plasma surface interaction studies in Japan

Abstract

In order to achieve a long burning time period in a fusion experimental reactor and a steady state operation in a Large Helical Device, LHD, the heat flux and the particle flow have to be adequately controlled, in addition to the suppressions of the plasma surface interactions such as erosions and recyclings. Recently, in Japan, high heat flux components which can remove the fluxes of 30 MW/m2 and 10 MW/m2, have been developed for ITER and LHD, respectively. In addition, the divertor concepts such as a Local Island Divertor and ripple limiters were progressed both for LHD and ITER. The data on erosion and hydrogen recycling were accumulated for low Z materials such as lithium, boron and boron carbide. It is shown that the conditioning for the boron-containing material is significantly easier compared with the case of graphite or CFC. Others activities associated with the plasma facing materials such as tritium and neutron damage are also briefly introduced.