Edge plasma conditions and their variation with main plasma density and with neutral-beam input power are presented for expanded boundary divertor discharges produced in the Doublet III tokamak. The density and temperature in the divertor plasma and the heat flux to the divertor plates not only change with the main plasma density and neutral-beam input power but also depend on the level and type of recycling activity present in the divertor. However, the shape of the heat flux profile on the divertor plates is quite insensitive to variations in divertor properties. This insensitivity, together with the weak increase of peak heat flux on the divertor plate with input power, is favourable for the use of an expanded boundary divertor in future fusion reactors. Owing to the similarity of the magnetic configuration, the results from the expanded boundary divertor should be directly applicable to the divertor design for INTOR.
Heat and particle transport of SOL and divertor plasmas in the W shaped divertor on JT-60U