The impact of error fields on enhanced confinement regimes in tokamaks
Project ID:*19-15229S
Provider:Czech Science Foundation
Period:Jan 01, 2019 - Dec 31, 2021
Recipient - coordinatorInstitute of Plasma Physics, Czech Academy of Sciences, Prague
Principal Investigator:RNDr. Petra Bílková, Ph.D.
Co-recepient(s) / PI(s):Institute of Plasma Physics, Czech Academy of Sciences, Prague -- Petra Bílková
Co-investigators from IPPM. Peterka, O. Grover, J. Seidl, R. Dejarnac, M. Komm, M. Šos, P. Böhm, J. Krbec, M. Tomeš, O. Bogár, V. Weinzettl, J. Havlíček, T. Markovič

Aims of the project: One of the outstanding issues on the road towards controlled thermonuclear fusion with magnetic confinement is the access to the high confinement mode (H-mode) in the ITER tokamak, necessary for achieving its goal of tenfold fusion power gain. The access can be significantly altered by the presence of so called error fields arising from improperly aligned magnetic coils and solenoids. The preliminary results of the very recent experiments at the COMPASS tokamak with a world-unique combination of inboard and outboard error field correction coils have demonstrated that under specific conditions the inboard-generated error fields could be very significant for ITER H-mode operation, possibly preventing access to Hmode altogether. The proposed project aims to analyze these promising first results from the COMPASS tokamak in detail and to design and execute follow-up experiments with an extended range of plasma parameters in order to build a more robust physics picture of the impact of error fields on access to regimes with enhanced confinement in general.