Abstract Details

Coil Designs with 3-D Plasma Equilibria to Test New Divertors

Author: Prashant M Valanju
Submitted: 2006-01-02 13:59:13

Co-authors: M. Kotschenreuther, J.C. Wiley, M. Pekker, W.L. Rowan, Huang He

Contact Info:
Institute for Fusion Studies
1 University Station
Austin, TX   78712

Abstract Text:
We have proposed novel magnetic divertor geometries to overcome the divertor heat flux bottleneck in tokamak reactors. These include: either 1) inducing a second axi-symmetric flux expansion region along the separatrix, or 2) the extraction of the separatrix flux to outside the TF coils with low plasma TF ripple. Both coils significantly reduce the heat flux on the divertor plates while introducing only small plasma ripple. The reduced heat flux enables operation with lower core radiation, thus improving confinement. In order to test these ideas, we have designed realistic coils for PEGASUS and NSTX. We propose to use 3-D MHD free-boundary VMEC equilibrium code generated by filamentary coils, which will form the basis for finite cross-section coils. Coil currents, stresses, and heating will be calculated. Spectroscopic, probes, and bolometric diagnostics are proposed to check the predictions of the effects of these coils on divertor performance.

Characterization: A5

Place with posters by Wiley, Kotschenreuther, Pekker

The University of Texas at Austin

Innovative Confinement Concepts Workshop
February 13-16, 2006
Austin, Texas

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