NSTX plasma response to lithium coated divertor

H. W. Kugel, M. G. Bell, Jean Paul Allain, R. E. Bell, S. Ding, S. P. Gerhardt, M. A. Jaworski, R. Kaita, J. Kallman, S. M. Kaye, B. P. Leblanc, R. Maingi, R. Majeski, R. Maqueda, D. K. Mansfield, D. Mueller, R. Nygren, S. F. Paul, R. Raman, A. L. RoquemoreS. A. Sabbagh, H. Schneider, C. H. Skinner, V. A. Soukhanovskii, C. N. Taylor, J. R. Timberlake, W. R. Wampler, L. E. Zakharov, S. J. Zweben

Research output: Contribution to journalArticle

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Abstract

NSTX experiments have explored lithium evaporated on a graphite divertor and other plasma-facing components in both L- and H- mode confinement regimes heated by high-power neutral beams. Improvements in plasma performance have followed these lithium depositions, including a reduction and eventual elimination of the HeGDC time between discharges, reduced edge neutral density, reduced plasma density, particularly in the edge and the SOL, increased pedestal electron and ion temperature, improved energy confinement and the suppression of ELMs in the H-mode. However, with improvements in confinement and suppression of ELMs, there was a significant secular increase in the effective ion charge Zeff and the radiated power in H-mode plasmas as a result of increases in the carbon and medium-Z metallic impurities. Lithium itself remained at a very low level in the plasma core, <0.1%. Initial results are reported from operation with a Liquid Lithium Divertor (LLD) recently installed.

Original languageEnglish (US)
JournalJournal of Nuclear Materials
Volume415
Issue number1 SUPPL
DOIs
StatePublished - Aug 1 2011

Fingerprint

Lithium
lithium
Plasmas
retarding
liquid lithium
Ions
Facings
ion charge
Graphite
Plasma density
neutral beams
ion temperature
Density (specific gravity)
plasma density
elimination
Carbon
graphite
Impurities
electron energy
impurities

All Science Journal Classification (ASJC) codes

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

Cite this

Kugel, H. W., Bell, M. G., Allain, J. P., Bell, R. E., Ding, S., Gerhardt, S. P., ... Zweben, S. J. (2011). NSTX plasma response to lithium coated divertor. Journal of Nuclear Materials, 415(1 SUPPL). https://doi.org/10.1016/j.jnucmat.2010.12.016
Kugel, H. W. ; Bell, M. G. ; Allain, Jean Paul ; Bell, R. E. ; Ding, S. ; Gerhardt, S. P. ; Jaworski, M. A. ; Kaita, R. ; Kallman, J. ; Kaye, S. M. ; Leblanc, B. P. ; Maingi, R. ; Majeski, R. ; Maqueda, R. ; Mansfield, D. K. ; Mueller, D. ; Nygren, R. ; Paul, S. F. ; Raman, R. ; Roquemore, A. L. ; Sabbagh, S. A. ; Schneider, H. ; Skinner, C. H. ; Soukhanovskii, V. A. ; Taylor, C. N. ; Timberlake, J. R. ; Wampler, W. R. ; Zakharov, L. E. ; Zweben, S. J. / NSTX plasma response to lithium coated divertor. In: Journal of Nuclear Materials. 2011 ; Vol. 415, No. 1 SUPPL.
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abstract = "NSTX experiments have explored lithium evaporated on a graphite divertor and other plasma-facing components in both L- and H- mode confinement regimes heated by high-power neutral beams. Improvements in plasma performance have followed these lithium depositions, including a reduction and eventual elimination of the HeGDC time between discharges, reduced edge neutral density, reduced plasma density, particularly in the edge and the SOL, increased pedestal electron and ion temperature, improved energy confinement and the suppression of ELMs in the H-mode. However, with improvements in confinement and suppression of ELMs, there was a significant secular increase in the effective ion charge Zeff and the radiated power in H-mode plasmas as a result of increases in the carbon and medium-Z metallic impurities. Lithium itself remained at a very low level in the plasma core, <0.1{\%}. Initial results are reported from operation with a Liquid Lithium Divertor (LLD) recently installed.",
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Kugel, HW, Bell, MG, Allain, JP, Bell, RE, Ding, S, Gerhardt, SP, Jaworski, MA, Kaita, R, Kallman, J, Kaye, SM, Leblanc, BP, Maingi, R, Majeski, R, Maqueda, R, Mansfield, DK, Mueller, D, Nygren, R, Paul, SF, Raman, R, Roquemore, AL, Sabbagh, SA, Schneider, H, Skinner, CH, Soukhanovskii, VA, Taylor, CN, Timberlake, JR, Wampler, WR, Zakharov, LE & Zweben, SJ 2011, 'NSTX plasma response to lithium coated divertor', Journal of Nuclear Materials, vol. 415, no. 1 SUPPL. https://doi.org/10.1016/j.jnucmat.2010.12.016

NSTX plasma response to lithium coated divertor. / Kugel, H. W.; Bell, M. G.; Allain, Jean Paul; Bell, R. E.; Ding, S.; Gerhardt, S. P.; Jaworski, M. A.; Kaita, R.; Kallman, J.; Kaye, S. M.; Leblanc, B. P.; Maingi, R.; Majeski, R.; Maqueda, R.; Mansfield, D. K.; Mueller, D.; Nygren, R.; Paul, S. F.; Raman, R.; Roquemore, A. L.; Sabbagh, S. A.; Schneider, H.; Skinner, C. H.; Soukhanovskii, V. A.; Taylor, C. N.; Timberlake, J. R.; Wampler, W. R.; Zakharov, L. E.; Zweben, S. J.

In: Journal of Nuclear Materials, Vol. 415, No. 1 SUPPL, 01.08.2011.

Research output: Contribution to journalArticle

TY - JOUR

T1 - NSTX plasma response to lithium coated divertor

AU - Kugel, H. W.

AU - Bell, M. G.

AU - Allain, Jean Paul

AU - Bell, R. E.

AU - Ding, S.

AU - Gerhardt, S. P.

AU - Jaworski, M. A.

AU - Kaita, R.

AU - Kallman, J.

AU - Kaye, S. M.

AU - Leblanc, B. P.

AU - Maingi, R.

AU - Majeski, R.

AU - Maqueda, R.

AU - Mansfield, D. K.

AU - Mueller, D.

AU - Nygren, R.

AU - Paul, S. F.

AU - Raman, R.

AU - Roquemore, A. L.

AU - Sabbagh, S. A.

AU - Schneider, H.

AU - Skinner, C. H.

AU - Soukhanovskii, V. A.

AU - Taylor, C. N.

AU - Timberlake, J. R.

AU - Wampler, W. R.

AU - Zakharov, L. E.

AU - Zweben, S. J.

PY - 2011/8/1

Y1 - 2011/8/1

N2 - NSTX experiments have explored lithium evaporated on a graphite divertor and other plasma-facing components in both L- and H- mode confinement regimes heated by high-power neutral beams. Improvements in plasma performance have followed these lithium depositions, including a reduction and eventual elimination of the HeGDC time between discharges, reduced edge neutral density, reduced plasma density, particularly in the edge and the SOL, increased pedestal electron and ion temperature, improved energy confinement and the suppression of ELMs in the H-mode. However, with improvements in confinement and suppression of ELMs, there was a significant secular increase in the effective ion charge Zeff and the radiated power in H-mode plasmas as a result of increases in the carbon and medium-Z metallic impurities. Lithium itself remained at a very low level in the plasma core, <0.1%. Initial results are reported from operation with a Liquid Lithium Divertor (LLD) recently installed.

AB - NSTX experiments have explored lithium evaporated on a graphite divertor and other plasma-facing components in both L- and H- mode confinement regimes heated by high-power neutral beams. Improvements in plasma performance have followed these lithium depositions, including a reduction and eventual elimination of the HeGDC time between discharges, reduced edge neutral density, reduced plasma density, particularly in the edge and the SOL, increased pedestal electron and ion temperature, improved energy confinement and the suppression of ELMs in the H-mode. However, with improvements in confinement and suppression of ELMs, there was a significant secular increase in the effective ion charge Zeff and the radiated power in H-mode plasmas as a result of increases in the carbon and medium-Z metallic impurities. Lithium itself remained at a very low level in the plasma core, <0.1%. Initial results are reported from operation with a Liquid Lithium Divertor (LLD) recently installed.

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