ITER is going to be the first experimental pulsed fusion reactor designed to generate more fusion power than input heating power and it will be the largest fusion facility in the world. The tokamak magnet system is based on NbTi and Nb3Sn Cable-In-Conduit superconductors. Due to the high cost of tests, limited length of the conductor samples and, for Nb3Sn Cable-In-Conduit Conductors, the limited possibilities to test with magnetic field and magnetic field change rates as high as the peak values during ITER operating conditions, dedicated and complex simulations are necessary to extend the comprehension of CIC Conductor behavior. Different models are applied for the analysis of the NbTi and Nb3Sn CIC Conductors. The analytical Model with PArtial Shielding zone (MPAS) and the numerical model JackPot ACDC, developed at the University of Twente, are both used in combination with the THEA software to model the thermal and hydraulic behavior of the conductors and their coolant. The aim of this thesis work is to investigate and predict the stability behavior under operational conditions for the ITER plasma-operating scenario, in particular to assess and confirm the ability of the Central Solenoid for continuous operation under the load of the 15 MA Plasma Scenario burn cycles.
|Award date||12 Dec 2018|
|Place of Publication||Enschede|
|Publication status||Published - 12 Dec 2018|
- Fusion magnets
- Stability analysis
- Cable-in-Conduit Conductor