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Report No.
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Simulation modeling of ITER 15MA/70s ramp scenario using inductive/non-inductive current drive

Nakamura, Yukiharu*; Miyamoto, Seiji; Fujieda, Hirobumi; Oikawa, Toshihiro; Sugie, Tatsuo; Kusama, Yoshinori; Yoshino, Ryuji

In tokamak fusion reactors with superconducting PF coil system, ramping-up of the plasma current for startup of discharges is essentially restrained at a rate much slower than the current tokamak with normal PF conductors. Therefore, the induced plasma current can penetrate deeply into the core region with higher electron temperature, i.e. low Ohmic resistivity, leading to a centrally peaked current profile. Consequently, such the high li, highly elongated configuration imperative to divertor formation has the dangerous property of causing vertical instability. Additional heating at early phase of the ramp-up has been addressed as one of startup procedures that retard the penetration of plasma current. A potential drawback, however, is the substantial increase of direct heat load to limiter. Hence, it follows that discharge optimization, e.g. timing of the heating, has been critical to plasma formation during the startup phase. The feasible ramp-up scenario to obtain a stable current profile while increasing bootstrap current fraction is discussed, as well as the interests: how quickly the plasma current needs to be ramped up and how slowly it can be.

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