Abstract
JT-60 is a large hydrogen tokamak with a compact poloidal divertor. The maximum input energy into the torus is about 500 MJ, and divertor studies are among the most essential experiments. The divertor in JT-60 has been studied numerically from three different view points, i.e. MHD equilibrium control, divertor plasma control and surface temperature control of the device. These results suggest that a serious heat flux can be avoided and a plasma contacting the divertor plates can be cooled down to 10 eV or less by controlling the magnetic configuration and divertor plasma density. The magnetic configuration with the divertor can be controlled by changing various coil currents, and the divertor plasma density can be controlled by changing the particle recycling condition in the divertor. The particle number in the main plasma can be also controlled by combining the compact divertor and gas influx both in the main chamber and in the divertor chamber.
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