Operational Characteristics of Liquid Lithium Divertor in NSTX

ORAL

Abstract

Lithium coatings on plasma-facing components (PFC's) have resulted in improved plasma performance on NSTX in deuterium H-mode plasmas with neutral beam heating.$^{ }$Salient results included improved electron confinement and ELM suppression. In CDX-U, the use of lithium-coated PFC's and a large-area liquid lithium limiter resulted in a six-fold increase in global energy confinement time. A Liquid Lithium Divertor (LLD) has been installed in NSTX for the 2010 run campaign. The LLD PFC consists of a thin film of lithium on a temperature-controlled substrate to keep the lithium liquefied between shots, and handle heat loads during plasmas. This capability was demonstrated when the LLD withstood a strike point on its surface during discharges with up to 4 MW of neutral beam heating.

*Supported by U.S. Department of Energy Contracts DE-AC02-09CH11466, DE-AC04-94AL85000, DE-AC52-07NA27344, and DE-AC05-00OR22725

Authors

  • R. Kaita

    • PPPL
    • Princeton Plasma Physics Laboratory
    • Princeton Plasma Physics Lab
  • H. Kugel

  • T. Abrams

  • M.G. Bell

  • R.E. Bell

  • S. Gerhardt

  • M.A. Jaworski

  • J. Kallman

  • B. LeBlanc

  • D. Mansfield

  • D. Mueller

  • S. Paul

  • A.L. Roquemore

  • F. Scotti

  • C.H. Skinner

  • J. Timberlake

  • L. Zakharov

    • PPPL
  • R. Maingi

    • ORNL
  • R. Nygren

    • SNL
  • R. Raman

    • U. of Washington
  • S. Sabbagh

    • Columbia U.
  • V. Soukhanovskii

    • LLNL