プラズマ－壁相互作用研究用小型プラズマ源

Abstract

Material selection for the first wall and divertor plate is essential to ensure a stable sustainment of tokamak plasma confinement and burning in ITER and DEMO. Tungsten is one of the most promising candidates. However, the surface damage due to helium irradiation is a serious concern to be overcome. Compact plasma device for such PWI (Plasma-Wall Interactions) studies is helpful to investigate how to avoid the helium damage of tungsten surface. In this paper the qualification of new plasma device for PWI is introduced, and the preliminary data of the effect of He irradiation on tungsten surface are shown.