Equilibrium Reconstruction of LHD Discharges using V3FIT
POSTER
Abstract
The presence of significant pressure driven currents as well as the ability to drive tens of kiloamperes of toroidal plasma current in LHD leads to deviations in the equilibrium magnetic geometry from the vacuum flux surfaces. The V3FIT code is being used to reconstruct non-axisymmetric stellarator equilibria for LHD discharges with the assumption of good flux surfaces. The present work is a study of the ability of the V3FIT code to reliably reconstruct the plasma equilibrium state for a variety of LHD discharge types using the existing diagnostics. The initial diagnostic set studied consists of the measured coil currents, the total plasma current, magnetic diagnostics and soft x-ray diode arrays. The accuracy of the reconstructed current and pressure profiles using this initial diagnostic set is assessed and the relative effectiveness of each diagnostic is determined for each fit parameter.
Authors
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A.C. Sontag
Oak Ridge National Laboratory, ORNL, UT-Battelle
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J.D. Hanson
Auburn University
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J.H. Harris
ORNL, Oak Ridge National Laboratory
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Satoshi Ohdachi
National Institute for Fusion Science
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S. Sakakibara
National Institute for Fusion Science
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Y. Suzuki
National Institute for Fusion Science