The high heat load on divertor target is one of the essential issues that must be addressed for next-step high-power steady-state fusion devices. One possible solution is using the island divertor configuration, which has been proposed in 1977 for tokamak. The island divertor configuration not only has a long L|| in the SOL, but also forms a three-dimensional stochastic layer around the boundary magnetic island. It is beneficial to increase the equivalent radial transport, and consequently reduce the peak heat load on the divertor target. This poster focuses on the design of the island divertor coils.
 

divertor;tokamak