Taming the plasma-material interface with the 'snowflake' divertor in NSTX

V. A. Soukhanovskii, J. W. Ahn, R. E. Bell, D. A. Gates, S. Gerhardt, R. Kaita, E. Kolemen, B. P. LeBlanc, R. Maingi, M. Makowski, R. Maqueda, A. G. McLean, J. E. Menard, D. Mueller, S. F. Paul, R. Raman, A. L. Roquemore, D. D. Ryutov, S. A. Sabbagh, H. A. Scott

Research output: Contribution to journalArticlepeer-review

70 Scopus citations

Abstract

Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel 'snowflake' divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume available for volumetric power and momentum loss processes, as compared with the standard divertor. Both a significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with core H-mode confinement in discharges with the SFD using only a minimal set of poloidal field coils.

Original languageEnglish (US)
Article number012001
JournalNuclear Fusion
Volume51
Issue number1
DOIs
StatePublished - Jan 2011

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Condensed Matter Physics

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