Triple-X Divertor Coil Designs for EAST, PEGASUS, MAST, and Reactors

POSTER

Abstract

Novel magnetic divertor with additional X-points downstream from main plasma X-point have been proposed to overcome reactor heat flux limitations. PEGASUS, MAST, and EAST(China's new long-pulse, superconducting tokamak) are considering experimental implementation of these divertors. MHD equilibria, optimized coil designs, sensitivity to plasma motion, stresses, and heating will be presented for these machines as well as for some reactor designs.

Authors

  • William Rowan

  • Prashant Valanju

  • M. Kotschenreuther

  • James Wiley

  • Mikhail Pekker

    • Institute for Fusion Studies, Univ. of Texas at Austin

  • Huang He

    • Fusion Research Center, Univ. of Texas at Austin