Search

The cable-in-conduit-conductors (CICC) for the ITER Toroidal Field (TF) Coils are tested in the Sultan test facility in order to estimate their AC and DC performances under operating conditions. The tests are carried out on different stages of conductor procurement implementation starting from \Nb3\Sn superconducting strand layout and process development to regular checks of production unit lengths. Four TF samples provided by Russia have been successfully tested in the Sultan facility by now in the framework of the ITER collaboration, including Strand Performances Qualification Sample, Qualification Conductor Sample, Pre-production and Production Conductors sample. The test results of all four samples shows pretty good reproducibility of the conductor performances from sample to sample and at the same time good stability of conductor performance under mechanical loading caused by Lorenz force during electromagnetic (EM) cycling can be observed. In the present work a comparison of the conductors and their performance was carried out to show the development of conductor performances from R&D stage to mass production. [ABSTRACT FROM PUBLISHER]

The ITER Poloidal Field (PF) magnet system consists of six coils. Niobium-Titanium (NbTi) is used as superconducting material and cable-in-conduit conductor(CICC) type are used as a conductor. All coils are fabricated by stacking 6 to 9 double-pancakes wound by two-in-hand winding scheme. The six PF coils (PF1 to PF6) are attached to the Toroidal Field (TF) coil cases through flexible plates or sliding supports to allow small radial and vertical displacements. The outer diameters of the coils vary between 8 m and 24 m. Since the PF coil system provides magnetic field for plasma shaping and position control together with the Central Solenoid (CS) coil, it needs to operate in fast pulse mode, leading to induced voltages of up to 14 kV on the coil terminals during operation. [ABSTRACT FROM PUBLISHER]