Tokamak plasmas are subject to various resistive and ideal MHD instabilities when operating close to the MHD limits. In this paper we investigate these instabilities in high beta plasmas in ASDEX Upgrade tokamak. Experimental limits for maximal achievable ?N in these plasmas are typically set by the neoclassical tearing modes (NTMs). It is possible to remove these modes (or reduce their amplitudes) with application of electron cyclotron current drive (ECCD) either in pre-emptive or in feedback control variants. As far as this done, the normalized pressure can be increased further into the region, where ideal kink modes become main limiting factor [1,2]. In this paper, we investigate structure and dynamics of these resistive and ideal modes with the main focus on recent experiments during the last campaigns. The other problem which appears in these discharges is resonant field amplification which is the result of the proximity to the "no wall" limit. In this situation, even small external fields are amplified and influence the plasma performance. Based on the results of the previous experiments, the optimal error field correction is applied with the use of the B-coils to extend the achievable pressure values. Stability boundaries for experimental discharges are calculated with CAS3D/STARWALL codes [3], taking into account main conducting structures located close to the plasma boundary.

MHD activity in high beta discharges in ASDEX Upgrade

Piovesan P;Marrelli L;
2017

Abstract

Tokamak plasmas are subject to various resistive and ideal MHD instabilities when operating close to the MHD limits. In this paper we investigate these instabilities in high beta plasmas in ASDEX Upgrade tokamak. Experimental limits for maximal achievable ?N in these plasmas are typically set by the neoclassical tearing modes (NTMs). It is possible to remove these modes (or reduce their amplitudes) with application of electron cyclotron current drive (ECCD) either in pre-emptive or in feedback control variants. As far as this done, the normalized pressure can be increased further into the region, where ideal kink modes become main limiting factor [1,2]. In this paper, we investigate structure and dynamics of these resistive and ideal modes with the main focus on recent experiments during the last campaigns. The other problem which appears in these discharges is resonant field amplification which is the result of the proximity to the "no wall" limit. In this situation, even small external fields are amplified and influence the plasma performance. Based on the results of the previous experiments, the optimal error field correction is applied with the use of the B-coils to extend the achievable pressure values. Stability boundaries for experimental discharges are calculated with CAS3D/STARWALL codes [3], taking into account main conducting structures located close to the plasma boundary.
2017
Istituto gas ionizzati - IGI - Sede Padova
Inglese
44th European Physical Society Conference on Plasma Physics
4
9781510849303
http://ocs.ciemat.es/EPS2017PAP/pdf/P4.132.pdf
26-30 June 2017
Belfast, Northern Ireland
MHD
ASDEX
P4.132
14
none
Igochine, V; Piovesan, P; Bock, A; Giannone, L; Gude, A; Kudlacek, O; Maraschek, M; Marrelli, L; Mcdermott, R; Reich, M; Suttrop, W; Zohm, H; ASDEX Up...espandi
273
info:eu-repo/semantics/conferenceObject
04 Contributo in convegno::04.01 Contributo in Atti di convegno
   Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium
   EUROfusion
   H2020
   633053
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/335746
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