Control of Edge Transport Barrier relaxations using Resonant Magnetic Perturbations
Journal Article
·
· AIP Conference Proceedings
- Equipe Dynamique des Systemes Complexes, LPIIM, UMR 6633 CNRS-Universite de Provence, Centre St. Jerome, Case 321, 13397 Marseille Cedex 20 (France)
- Association Euratom-CEA sur la Fusion, LPIIM, CEA-Cadarache, 130108 St. Paul-Lez-Durance (France)
In divertor tokamak plasmas, an Edge Transport Barrier forms during the L-H transition. A poloidal shear flow has been shown to play a crucial role in the barrier sustainement. The H regime, obtained for a critical value of the heating power, is promising for the next generation of tokamak experiments such as ITER. However, an instability known as Edge Localized Mode (ELM) develops as the power is increased further. ELMs are characterized by intermittent bursts in the radial heat flux, therefore causing the transport barrier to relax quasi-periodically. Over the last decade, the possibility of controlling ELMs has become more and more plausible, as recent experiments were carried out on DIII-D using I-coils, on JET using error field correction coils, and on TEXTOR using an ergodic divertor. These experimental studies demonstrate a qualitative control over the ELMs by imposing a magnetostatic perturbation at the plasma edge. However, in order to get any quantitative result, much work has to be done in the understanding of ELM dynamics. In this work, we present results from numerical simulations of Resistive Ballooning Mode (RBM) turbulence reproducing the stabilization of barrier relaxations by a static magnetic perturbation. We focus our study on the edge region around the resonant surface q = 3. We use the TEXTOR tokamak geometry, and plasma parameters close to those used in typical experiments on this machine.
- OSTI ID:
- 21136944
- Journal Information:
- AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 993; ISSN APCPCS; ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BALLOONING INSTABILITY
COMPUTERIZED SIMULATION
CORRECTIONS
DISTURBANCES
DIVERTORS
DOUBLET-3 DEVICE
EDGE LOCALIZED MODES
HEAT FLUX
ITER TOKAMAK
JET TOKAMAK
PLASMA
PLASMA DIAGNOSTICS
PLASMA SIMULATION
RADIATION TRANSPORT
RELAXATION
SHEAR
TEXTOR TOKAMAK
TURBULENCE
BALLOONING INSTABILITY
COMPUTERIZED SIMULATION
CORRECTIONS
DISTURBANCES
DIVERTORS
DOUBLET-3 DEVICE
EDGE LOCALIZED MODES
HEAT FLUX
ITER TOKAMAK
JET TOKAMAK
PLASMA
PLASMA DIAGNOSTICS
PLASMA SIMULATION
RADIATION TRANSPORT
RELAXATION
SHEAR
TEXTOR TOKAMAK
TURBULENCE