PSI modeling of liquid lithium divertors for the NSTX tokamak

J. N. Brooks, J. P. Allain, T. D. Rognlien, R. Maingi

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23 Scopus citations


We analyzed plasma surface interaction issues for the planned Module-A static liquid lithium divertor for NSTX using coupled codes/models describing the plasma edge, divertor temperature, and erosion/redeposition, with input data from tokamak and laboratory experiments. A 300 nm lithium pre-shot deposited coating will strongly pump impinging D+ ions. This yields a low-recycle SOL plasma with high plasma temperature, Te ∼ 200-400 eV, low density, Ne ∼ 1-3 × 1018 m -3, and peak heat loads of ∼8-20 MW/m2, for 2-4 MW core plasma heating power. This regime has advantages for the NSTX physics mission. Peak surface temperature can be held to an acceptable ≤470 °C with moderate strike point sweeping (10 cm/s) using a carbon (for 2 MW) or Mo/Cu or W/Cu substrate (2-4 MW). Erosion/redeposition analysis shows acceptable coating lifetime for a 2 s pulse and low core plasma contamination by sputtered lithium.

Original languageEnglish (US)
Pages (from-to)1053-1057
Number of pages5
JournalJournal of Nuclear Materials
Issue number1-3 SPEC. ISS.
StatePublished - Mar 1 2005

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering


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