Lithium surface-response modelling for the NSTX liquid lithium divertor

J. P. Allain, J. N. Brooks

Research output: Contribution to journalArticle

Abstract

We analyse lithium sputtering, evaporation and transport for the National Spherical Torus Experiment (NSTX) liquid lithium divertor (LLD) for planned high heating power plasma conditions. A temperature-dependent, datacalibrated, surface-response model is used to specify sputter yield, velocity distributions, sputtered Li ion fraction and related phenomena, for the static liquid lithium surface with D, Li and trace C impingement. Using the surfaceresponse model, and supplied UEDGE code edge plasma parameters and LLD surface temperature profile for a typical 2MW heating, low D-recycle shot, the REDEP/WBC code package computes Li erosion/redeposition. The results are encouraging showing negligible Li evaporation, moderate sputter erosion, and acceptable Li transport to the edge (̃7% Li/D density) and core plasma (̃1% Li/D contamination potential) and LLD adjacent surfaces. A 2% carbon plasma content does not significantly affect the LLD surface response. For fixed plasma conditions, but with hypothetically higher surface temperatures than the reference 281 °C peak, an increase to ̃350 °C appears acceptable, thus implying a significant operating temperature margin.

Original languageEnglish (US)
Article number023002
JournalNuclear Fusion
Volume51
Issue number2
DOIs
StatePublished - Feb 1 2011

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Condensed Matter Physics

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