The ITER poloidal field (PF) system uses superconducting coils to provide the plasma equilibrium fields, slow equilibrium control and plasma flux linkage (V-s) needed for the ITER Operations and Research Program. Double-null (DN) divertor plasmas and operation scenarios for 22 MA Physics (high-Q/ignition) and 15 MA Technology (high-fluence testing) phases are provided. For 22 MA plasmas, total PF flux swing is 333 V-s. This provides inductive current drive (CD) for start-up with 66 V-s of resistive loss and 440-s (330-s minimum) sustained burn. The PF system also allows plasma start-up and shutdown scenarios, and can maintain the plasma configuration during burn over a range of current and pressure profiles. Other capabilities include increased plasma current (25 MA with inductive CD; 28 MA with non-inductive CD assist), divertor separatrix sweeping, and semi-DN and single-null plasmas.
Wesley, J;  Beljakov, V; Kavin, A; Korshakov, V; Kostenko, A; Roshal, A; Zakharov, L;  Bulmer, R; Kaiser, T; Miller, J R; Pearlstein, L D;  Hogan, J;  Kurihara, K; Shimomura, Y; Sugihara, M; Yoshino, R 
- General Atomics, San Diego, CA (USA)
- Kurchatov Inst. of Atomic Energy, Moscow (USSR)
- Lawrence Livermore National Lab., CA (USA)
- Oak Ridge National Lab., TN (USA)
- Japan Atomic Energy Resea