• Title of article

    Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation

  • Author/Authors

    Kugel، نويسنده , , H.W. and Bell، نويسنده , , M.G. and Schneider، نويسنده , , H. and Allain، نويسنده , , J.P. and Bell، نويسنده , , R.E. and Kaita، نويسنده , , R. and Kallman، نويسنده , , J. and Kaye، نويسنده , , S. and LeBlanc، نويسنده , , B.P. and Mansfield، نويسنده , , D. and Nygren، نويسنده , , R.E. and Maingi، نويسنده , , R. and Menard، نويسنده , , J. and Mueller، نويسنده , , M. D. Ichiro Ono، نويسنده , , M. and Paul، نويسنده , , S. and Gerhard-Multhaupt، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2010
  • Pages
    9
  • From page
    865
  • To page
    873
  • Abstract
    NSTX high power divertor plasma experiments have used in succession lithium pellet injection (LPI), evaporated lithium, and injected lithium powder to apply lithium coatings to graphite plasma facing components. In 2005, following the wall conditioning and LPI, discharges exhibited edge density reduction and performance improvements. Since 2006, first one, and now two lithium evaporators have been used routinely to evaporate lithium onto the lower divertor region at total rates of 10–70 mg/min for periods 5–10 min between discharges. Prior to each discharge, the evaporators are withdrawn behind shutters. Significant improvements in the performance of NBI heated divertor discharges resulting from these lithium depositions were observed. These evaporators are now used for more than 80% of NSTX discharges. Initial work with injecting fine lithium powder into the edge of NBI heated deuterium discharges yielded comparable changes in performance. Several operational issues encountered with lithium wall conditions, and the special procedures needed for vessel entry are discussed. The next step in this work is installation of a liquid lithium divertor surface on the outer part of the lower divertor.
  • Keywords
    Divertors , Spherical torus , lithium , Lithium wall fusion regime , recycling , Plasma wall interactions
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2010
  • Journal title
    Fusion Engineering and Design
  • Record number

    2370108