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Impurity transport studies in NSTX neutral beam heated H-mode plasmas

  • L. Delgado-Aparicio*
  • , D. Stutman
  • , K. Tritz
  • , M. Finkenthal
  • , S. Kaye
  • , R. Bell
  • , R. Kaita
  • , B. Leblanc
  • , F. Levinton
  • , J. Menard
  • , S. Paul
  • , D. Smith
  • , H. Yuh
  • *Corresponding author for this work

Research output: Contribution to journal › Article › peer-review

30 Scopus citations

Abstract

The first experimental assessment of low-Z impurity transport in a neutral beam heated, high-confinement H-mode plasma sustained in a low-field, low-aspect ratio spherical tokamak, was performed at the National Spherical Torus Experiment (NSTX). The injected impurities penetrate to the core on a hundred millisecond time scale, indicating a low core particle diffusivity (≲1 m2 s-1) in good agreement with the values predicted by neoclassical transport theory. In addition, a fixed q-profile magnetic field scan that showed reduced impurity penetration at high fields is also reported. This result suggests that anomalous ion particle transport associated with turbulent long-wavelength electrostatic instabilities must be largely suppressed in the NSTX core.

Original languageEnglish
Article number085028
JournalNuclear Fusion
Volume49
Issue number8
DOIs
StatePublished - 2009
Externally publishedYes

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

  1. SDG 7 - Affordable and Clean Energy
    SDG 7 Affordable and Clean Energy

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