One of the main FAST (Fusion Advanced Studies Torus) goals is to have a flexible experiment capable to test tools and scenarios for safe and reliable tokamak operation, in order to support ITER and help the final DEMO design. In particular, in this paper, we focus on operation close to a possible border of stability related to low-q operation. To this purpose, a new FAST scenario has then been designed at Ip=10 MA, BT=8.5T, q 95≈2.3. Transport simulations, carried out by using the code JETTO and the first principle transport model GLF23, indicate that, under these conditions, FAST could achieve an equivalent Q≈3.5. FAST will be equipped with a set of internal active coils for feedback control, which will produce magnetic perturbation with toroidal number n=1 or n=2. Magnetohydrodynamic (MHD) mode analysis and feedback control simulations performed with the codes MARS, MARS-F, CarMa (both assuming the presence of a perfect conductive wall and using the exact 3D resistive wall structure) show the possibility of the FAST conductive structures to stabilize n=1 ideal modes. This leaves therefore room for active mitigation of the resistive mode (down to a characteristic time of 1ms) for safety purposes, i.e., to avoid dangerous MHD-driven plasma disruption, when working close to the machine limits and magnetic and kinetic energy density not far from reactor values. © 2014 AIP Publishing LLC.
All Science Journal Classification (ASJC) codes
- Condensed Matter Physics
Villone, F., Calabrò, G., Marchiori, G., Mastrostefano, S., Vlad, G., Bolzonella, T., ... Martin, P. (2014). Magnetohydrodynamic modes analysis and control of Fusion Advanced Studies Torus high-current scenarios. Physics of Plasmas, 21(8), -. . https://doi.org/10.1063/1.4893418