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. Ono & 10 others S. 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 journalArticle

Abstract

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)
JournalJournal of Nuclear Materials
Volume438
Issue numberSUPPL
DOIs
StatePublished - 2013
Externally publishedYes

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Liquids
liquid lithium
Birth Certificates
Lithium
Plasmas
refueling
Callosities
Fueling
Experiments
Edema Disease of Swine
Common Bile Duct Diseases
Laboratory Animals
coatings
liquids
Coatings
Acetabularia
Butylene Glycols
disrupting
erosion
deuterium

ASJC Scopus subject areas

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

Cite this

Kaita, R., Kugel, H. W., Abrams, T., Allain, J. P., Bell, M. G., Bell, R. E., ... Zakharov, L. (2013). Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor. Journal of Nuclear Materials, 438(SUPPL). DOI: 10.1016/j.jnucmat.2013.01.100

Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor. / Kaita, R.; Kugel, H. W.; Abrams, T.; Allain, J. P.; Bell, M. G.; Bell, R. E.; Diallo, A.; Gerhardt, S. P.; Heim, B.; Jaworski, M. A.; Kallman, J.; Kaye, S.; LeBlanc, B. P.; Maingi, R.; Mansfield, D.; McLean, A.; Menard, J.; Mueller, D.; Nygren, R.; Ono, M.; Paul, S. F.; Podesta, M.; Raman, R.; Roquemore, A. L.; Sabbagh, S. A.; Scotti, F.; Skinner, C. H.; Soukhanovskii, V. A.; Taylor, C. N.; Zakharov, L.

In: Journal of Nuclear Materials, Vol. 438, No. SUPPL, 2013.

Research output: Contribution to journalArticle

Kaita, R, Kugel, HW, Abrams, T, Allain, JP, Bell, MG, Bell, RE, Diallo, A, Gerhardt, SP, Heim, B, Jaworski, MA, Kallman, J, Kaye, S, LeBlanc, BP, Maingi, R, Mansfield, D, McLean, A, Menard, J, Mueller, D, Nygren, R, Ono, M, Paul, SF, Podesta, M, Raman, R, Roquemore, AL, Sabbagh, SA, Scotti, F, Skinner, CH, Soukhanovskii, VA, Taylor, CN & Zakharov, L 2013, 'Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor' Journal of Nuclear Materials, vol 438, no. SUPPL. DOI: 10.1016/j.jnucmat.2013.01.100

Kaita, R.; Kugel, H. W.; Abrams, T.; Allain, J. P.; Bell, M. G.; Bell, R. E.; Diallo, A.; Gerhardt, S. P.; Heim, B.; Jaworski, M. A.; Kallman, J.; Kaye, S.; LeBlanc, B. P.; Maingi, R.; Mansfield, D.; McLean, A.; Menard, J.; Mueller, D.; Nygren, R.; Ono, M.; Paul, S. F.; Podesta, M.; Raman, R.; Roquemore, A. L.; Sabbagh, S. A.; Scotti, F.; Skinner, C. H.; Soukhanovskii, V. A.; Taylor, C. N.; Zakharov, L. / Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor.

In: Journal of Nuclear Materials, Vol. 438, No. SUPPL, 2013.

Research output: Contribution to journalArticle

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