Updated Stability Analysis of the PF/CC Models With the ITER DINA 2016 Plasma Scenario

In the ITER project, the Poloidal Field (PF) and Correction Coils (CC) - all made of Nb-Ti conductors - share the same supercritical Helium cooling loop at about 4.5 K. Recently, the associated thermo-hydraulic model developed with SuperMagnet has been updated to obtain a more accurate description of this cryomagnetic system. These changes include integration of feeders, more detailed cryodistribution circuits and refined coil geometries, with the general aim at approaching as much as possible the as-built configuration. In parallel, currents, magnetic field maps and magnet heat loads (mainly AC losses) associated with the ITER DINA 2016 plasma scenario have been included in this model together with refined nuclear heating to evaluate the corresponding PF and CC conductor minimum temperature margins; the objective being to ensure that they remain above the specification value of 1.5 K.