Abstract
High field is very favorable for magnetically confined fusion devices such as a tokamak, but electromagnetic force derived from the field becomes a fatal problem. In particular, the largest in-plane centering force hinders toroidal field coils from operating at higher fields. Variable pitch multihelical coils, which we term force-balanced coils (FBCs), by which this force is drastically reduced, are proposed for the coil system of tokamaks. FBCs can also provide poloidal flux swing for plasma breakdown and current induction during the ramp-up phase of the coil current. In this paper, we indicate how to design FBCs for tokamaks. The fusion reactor-size FBCs are designed and compared with that of the conventional toroidal field coil system. © 1999 Scripta Technica, Electr Eng Jpn, 130(3): 39–48, 2000
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