Super{\_}X divertor geometries and plasma simulations

POSTER

Abstract

Potential implementations on NSTX, a component test facility (CTF) and a fission-fusion hybrid are considered. Magnetic equilibria are devised using CORSICA for desirable core plasma configurations, to allow considerable flexibility, and without unacceptable coil currents or positions. Using the state of the art edge simulation code SOLPS, plasma simulations of these configurations are considered, to examine their advantages.

Authors

  • Brent Covele

    • University of Texas

  • P. Valanju

    • University of Texas

  • Swadesh Mahajan

    • IFS, University of Texas at Austin
    • University of Texas
    • Institute for Fusion Studies, The University of Texas at Austin, TX 78712
    • Inst. Fusion Sudies, U. Texas at Austin

  • M. Kotschenreuther

    • University of Texas