Abstract
Operation points of a tokamak fusion DEMO in the conventional (C-) and “inter-linked” (IL-) CS configurations are analyzed. A specific feature of the systems analysis presented here is that it is consistent with superconducting toroidal field coil (TFC) system analysis. It is shown that in order to achieve the fusion power of the order of gigawatt with the inductive plasma current ramp-up, the large reactor size is needed for the C-CS configuration. Use of the IL-CS configuration enables to reduce the plasma major radius and, in turn, the reactor size compatible with both the large fusion power and inductive plasma current ramp-up.
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