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

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28 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

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