作者: V. M. Amoskov , V. A. Belyakov , Yu. A. Gribov , E. A. Lamzin , N. A. Maximenkova
DOI: 10.1134/S1547477115030048
关键词:
摘要: In tokamaks non-axisymmetric magnetic field perturbations (error fields) can induce in plasma locked modes and cause disruption. ITER the main contributor to error fields is assembly manufacturing errors of magnet system machine. To suppress intrinsic guarantee expected performance provided with proper correction coils (CC). The paper related optimization CC currents. takes into account as constraints both current capacities an allowable level fields.