A Neutral Beam for the Lithium Tokamak eXperiment Upgrade (LTX-U)

POSTER

Abstract

Neutral beam injection into tokamaks is a proven method of plasma heating and fueling. In LTX, high confinement discharges have been achieved with low-recycling lithium walls. To further improve plasma performance, a neutral beam (NB) will be installed as part of an upgrade to LTX (LTX-U). The NB will provide core plasma fueling with up to 700 kW of injected power. Requirements for accommodating the NB include the addition of injection and beam-dump ports onto the vessel and enhancement of the vacuum vessel pumping capability. Because the NB can also serve as a source of neutrals for charge-exchange recombination spectroscopy, ``active'' spectroscopic diagnostics will also be developed. An overview of these plans and other improvements for upgrading LTX to LTX-U will be presented.

*Supported by US DOE contracts DE-AC02-09CH11466 and DE-AC52-07NA27344

Authors

  • Enrique Merino

    • Princeton Plasma Physics Laboratory (PPPL)
  • R. Majeski

    • Princeton Plasma Physics Laboratory
    • PPPL
    • Princeton Plasma Physics Laboratory (PPPL)
  • Robert Kaita

    • Princeton Plasma Physics Laboratory
    • Princeton Plasma Physics Laboratory (PPPL)
    • PPPL
  • Thomas Kozub

    • Princeton Plasma Physics Laboratory (PPPL)
  • D.P. Boyle

    • Princeton Plasma Physics Laboratory (PPPL)
    • PPPL
  • J.C. Schmitt

    • PPPL
    • Princeton Plasma Physics Laboratory (PPPL)
  • Artem Smirnov

    • Tri-Alpha Energy, Inc.
    • Tri Alpha Energy
    • Tri Alpha Energy, Inc.