[en] The Correction Coils (CC) in ITER consist of 18 individual coils arranged in 3 groups around the toroidal field coils(TF), those are 6 on top(TCC), 6 on side(SCC) and 6 on bottom(BCC) by out of the TF. The correction coils are placed and sized can correct the most significant error on poloidal (PF), TF and feeders that come from manufacturing and assembly tolerances. These opposite pairs of coils are connected in 9 independent circuits. The coils have been designed using a cable-in-conduit NbTi conductor (CICC) with a 10 kA operating current. They are pancake wound with a vacuum pressure impregnated (VPI) with glass-kapton-epoxy insulating system. The winding pack is contained in a case which is mounted onto the TF coil cases as support. The ITER Organization (IO) and the Institute of Plasma Physics at the Chinese Academy of Sciences (ASIPP) are jointly preparing the definition of the technical specifications and the upcoming qualification program for the Correction Coils. The development of major items such as terminal joints, casing manufacture, and vacuum impregnation system, is an essential phase before the series production which will take place at the premises of the supplier. This paper was shown the status on key technologies for fabricating of CC coils. (author)

[en] The Correction Coils System (CCs or CC) in ITER consists of eighteen individual multi-turn coils arranged in three groups (Top, Side and Bottom) around the TF coils. It was used to compensate field errors arising from misalignment of the coils and winding deviations from the nominal shape as a result of fabrication tolerances, joints, leads and assembly tolerances. The six side coils are also used for feedback control of plasma resistive wall mode (RWM) disturbances. The top and bottom coils is located between TF cases and PF6 coil and consists of six saddle type coils covers a 60deg sector and spans three TF coils in the toroidal direction at upper and lower of the TF coil. The side coils is located between TF cases and both of PF3 coil, PF4 coil and consists of six quadrilateral shape type coils arranged around the toroidal circumference with a 40deg sector and each coil spans only two TF coils at aside of the TF coil. All Corrections Coils (lower, side and upper) are then attached to the TF coil cases. The electromagnetic field and forces acting on the CC winding are calculated with the CC current and ITER presented design scenario (burn time), which includes TF in operating, PF system discharge, plasma initiation, current ramp-up and heating to a driven burn. The CCs experience electromagnetic forces due to their self-field and the field of the TF coils, PF coils and CS coils. During calculating, the geometrical dimensions of all coils are originally defined in the reference of ITER Design Description Document DDD 11 Magnet Section 1. It was an engineering description (ITER D_--22HV5L v2.2) in 2006 version. (author)