SOLPS Modeling of Transport of the Super-X Divertor for the CFNS/Fusion-Fission Hybrid

POSTER

Abstract

Recent transport results from the B2-Eirene fluid/Monte-Carlo code will be presented for the Super-X Divertor in the Compact Fusion Neutron Source, a high-power-density, low-aspect-ratio double-null tokamak design. The Super-X Divertor, a novel magnetic geometry, greatly reduces heat fluxes and plasma temperatures at the outer target plates (with an outer:inner total power ratio of 10:1) while maintaining excellent core plasma shape characteristics.

Authors

  • Brent Covele

    University of Texas, University of Texas at Austin

  • Mike Kotschenreuther

    University of Texas, University of Texas at Austin

  • Swadesh Mahajan

    University of Texas, University of Texas at Austin

  • Prashant Valanju

    University of Texas, University of Texas at Austin