Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor

R. Kaita, H. W. Kugel, T. Abrams, J. P. Allain, M. G. Bell, R. E. Bell, A. Diallo, S. P. Gerhardt, B. Heim, M. A. Jaworski, J. Kallman, S. Kaye, B. P. LeBlanc, R. Maingi, D. Mansfield, A. McLean, J. Menard, D. Mueller, R. Nygren, M. OnoS. F. Paul, M. Podesta, R. Raman, A. L. Roquemore, S. A. Sabbagh, F. Scotti, C. H. Skinner, V. A. Soukhanovskii, C. N. Taylor, L. Zakharov

Research output: Contribution to journalArticlepeer-review


Deuterium fueling experiments were conducted with the NSTX Liquid Lithium Divertor (LLD). Lithium evaporation recoated the LLD surface to approximate flowing liquid Li to sustain D retention. In the first experiment with the diverted outer strike point on the LLD, the difference between the applied D gas input and the plasma D content reached very high values without disrupting the plasma, as would normally occur in the absence of Li pumping, and there was also little change in plasma D content. In the second experiment, constant fueling was applied, as the LLD temperature was varied to change the surface from solid to liquid. The D retention was relatively constant, and about the same as that for solid Li coatings on graphite, or twice that achieved without Li PFC coatings. Contamination of the LLD surface was also possible due to compound formation and erosion and redeposition from carbon PFCs.

Original languageEnglish (US)
Pages (from-to)S488-S492
JournalJournal of Nuclear Materials
Issue numberSUPPL
StatePublished - 2013
Externally publishedYes

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • General Materials Science
  • Nuclear Energy and Engineering


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