抄録
A poloidal divertor system is available for the thermonuclear fusion experimental tokamak reactor from the viewpoint of power and particle control. Divertor plasma models are reviewed briefly, which are used for analyzing divertor functions and for computer simulations. Simple results of one-dimensional analysis parallel to magnetic field lines are given, which show the qualitative characteristics of divertor plasma and rough values of divertor-plasma parameters. In relation to the boundary condition at the divertor plate, sheath conditions are especially noted in the appendix. Experimental results of density and temperature profiles in divertor plasmas as well as the width of heat flux are reviewed. Results of impurity shielding experiments and He ash exhaust experiments are also described shortly. Comment on the completion of divertor-plasma database is attached finally.
