Design of Divertor Scraper Elements for the W7-X Stellarator

POSTER

Abstract

A PPPL/ORNL/LANL team is partnering with the Max-Planck Institut f\"{u}r Plasmaphysik in the Wendelstein 7-X (W7-X) stellarator project. W7-X is a large superconducting, steady-state stellarator (R = 5.5, a = 0.5, B = 3T) with P =15-30 MW that will begin operation in 2015. The US team is focusing on control of the magnetic configuration and divertor heat flux. The W7-X divertor consists of cooled CFC plates arranged as a magnetic island divertor outside the last closed flux surface. While the W7-X configuration is optimized to minimize both Pfirsch-Schl\"{u}ter and bootstrap currents, the $\sim $30 sec evolution of the plasma to its final equilibrium drives bootstrap currents which transiently alter the distribution of divertor heat flux. This necessitates the addition of 10 actively cooled scraper elements (dimensions $\sim $0.2 m x 1 m) capable of absorbing localized heat fluxes $<$ 12 MW/m$^{2}$. ORNL/IPP are developing an engineering design for the scraper elements using ITER CFC monoblock technology.

Authors

  • J.H. Harris

    ORNL, Oak Ridge National Laboratory

  • A. Lumsdaine

    Oak Ridge National Laboratory, ORNL, ORNL, UT-Battelle

  • J.M. Canik

    Oak Ridge National Laboratory, ORNL, UT-Battelle, ORNL

  • Jeremy Lore

    ORISE, ORNL, ORNL, Oak Ridge National Lab, HSX Plasma Lab, Univeristy of Wisconsin, Oak Ridge National Laboratory

  • Dean McGinnis

    Oak Ridge National Laboratory

  • Alan Peacock

    Max-Planck Institut f\&#034;ur Plasmaphysik

  • Fred Hurd

    Max-Planck Institut f\&#034;ur Plasmaphysik

  • Jean Boscary

    Max-Planck Institut f\&#034;ur Plasmaphysik

  • Joachim Geiger

    Max-Planck Institut f\&#034;ur Plasmaphysik

  • Joseph Tipton

    Oak Ridge National Laboratory