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MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade

Authors :
Igochine V.
P. Piovesan
P. Bettini
T. Bolzonella
I.G.J. Classen
M. Dunne
A. Gude
P. Lauber
Y. Liu
M. Maraschek
N. Marconato
L. Marrelli
S. Mastrostefano
P. McCarthy
R. McDermott
M. Reich
D. Ryan
M. Schneller
E. Strumberger
W. Suttrop
G. Tardini
F. Villone
D. Yadykin
the ASDEX Upgrade Team
the EUROfusion MST Team
Source :
26th IAEA Fusion Energy Conference, Kyoto, Japan, 17-22 October 2016, info:cnr-pdr/source/autori:Igochine V.; P. Piovesan; P. Bettini; T. Bolzonella; I.G.J. Classen; M. Dunne; A. Gude; P. Lauber; Y. Liu; M. Maraschek; N. Marconato; L. Marrelli; S. Mastrostefano; P. McCarthy; R. McDermott; M. Reich; D. Ryan; M. Schneller; E. Strumberger; W. Suttrop; G. Tardini ; F. Villone; D. Yadykin; the ASDEX Upgrade Team; the EUROfusion MST Team/congresso_nome:26th IAEA Fusion Energy Conference/congresso_luogo:Kyoto, Japan/congresso_data:17-22 October 2016/anno:2016/pagina_da:/pagina_a:/intervallo_pagine
Publication Year :
2016

Abstract

The improved H-mode scenario (or high ? hybrid operations) is one of the main candidates for high-fusion performance tokamak operation, which offers potential steady-state scenario. In this case, the normalized pressure ?N must be maximized and pressure driven instabilities limit the plasma performance. These instabilities could have either resistive ((m=2,n=1) and (3,2) Neoclassical Tearing Modes (NTMs)), or ideal character (n=1 ideal kink modes). In ASDEX Upgrade (AUG), the first limit for maximum achievable ?N is set by NTMs. Application of pre-emptive electron cyclotron current drive at the q=2 and q=1.5 resonant surfaces reduces this problem, such that higher values of ?N can be reached. AUG experiments have shown that, in spite of the fact that hybrids are mainly limited by NTMs, proximity to the no-wall limit leads to amplification of external fields that strongly influences the plasma profiles: for example, rotation braking is observed throughout the plasma and peaks in the core. In this situation, even small external fields are amplified and their effect becomes visible. To quantify these effects, the plasma response to magnetic fields produced by B-coils is measured as ?N approaches the no-wall limit. These experiments and corresponding modelling allow to identify the main limiting factors which depend on the stabilizing influence of conducting components facing the plasma surface, existence of external actuators and kinetic interaction between the plasma and the marginally stable ideal modes. Analysis of the plasma reaction to external perturbations allowed us to identify optimal correction currents for compensating the intrinsic error field in the device. Such correction, together with analysis of kinetic effects, will help to increase ?N further in future experiments.

Details

Language :
English
Database :
OpenAIRE
Journal :
26th IAEA Fusion Energy Conference, Kyoto, Japan, 17-22 October 2016, info:cnr-pdr/source/autori:Igochine V.; P. Piovesan; P. Bettini; T. Bolzonella; I.G.J. Classen; M. Dunne; A. Gude; P. Lauber; Y. Liu; M. Maraschek; N. Marconato; L. Marrelli; S. Mastrostefano; P. McCarthy; R. McDermott; M. Reich; D. Ryan; M. Schneller; E. Strumberger; W. Suttrop; G. Tardini ; F. Villone; D. Yadykin; the ASDEX Upgrade Team; the EUROfusion MST Team/congresso_nome:26th IAEA Fusion Energy Conference/congresso_luogo:Kyoto, Japan/congresso_data:17-22 October 2016/anno:2016/pagina_da:/pagina_a:/intervallo_pagine
Accession number :
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