Hannover 2010 – scientific programme
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P: Fachverband Plasmaphysik
P 13: Magnetic Confinement
P 13.8: Talk
Wednesday, March 10, 2010, 16:45–17:00, B 305
Magnetic field lines tracing for ITER ELM control coils — •R. Laengner1, O. Schmitz1, M. Becoulet2, T. Evans3, H. Frerichs4, U. Samm1, and M. Schaffer3 — 1Institut für Energieforschung - Plasmaphysik, Forschungszentrum Jülich GmbH, Assoziation EURATOM-FZ-Jülich, Trilaterales Euregio Cluster, Jülich — 2Association EURATOM-CEA, Centre de Cadarache — 3General Atomics, San Diego, CA, USA — 4German Research School for Simulation Sciences, Jülich, Germany
For the mitigation of high, transient heat and particle fluxes caused by Edge Localized Modes (ELMs), magnetic perturbation coils are planed at the next step fusion experiment ITER. These coils generate an external magnetic perturbation field with a resonant alignment to the field line pitch angle in the plasma edge, breaking the axissymmetry of the tokamak. In this contribution, a detailed study of the new three-dimensional magnetic boundary, computed from vacuum field line tracing, is shown. Analysis of the perturbed system with Poincaré plots and modeling of the field line connection length shows that a system evolves which is very similar to the stochastic boundary applied at the DIII-D tokamak for complete ELM suppression [T.E.Evans et al., Nature Phys. 2, 419 (2006)]. The open field line region intersects the divertor target in ITER in a helical pattern which will determine a non-axissymmetric heat and particle fluxes. The magnetic footprint geometry will be presented for a standard, inductive plasma setup as well as for a high magnetic shear, steady state scenario and discussed with particular reference to recent ITER divertor design reviews.