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; 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

doi:10.1016/j.jnucmat.2013.01.100

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

Nuclear Science & Technology

Research output: Contribution to journal › Article › peer-review

7 Scopus citations

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 language	English
Pages (from-to)	S488-S492
Journal	Journal of Nuclear Materials
Volume	438
Issue number	SUPPL
DOIs	https://doi.org/10.1016/j.jnucmat.2013.01.100
State	Published - 2013

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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., ... Zakharov, L. (2013). Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor. Journal of Nuclear Materials, 438(SUPPL), S488-S492. https://doi.org/10.1016/j.jnucmat.2013.01.100

@article{7282ae60505744cfbad8b37526ccc23a,

title = "Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor",

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.",

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

note = "Funding Information: This work is supported by United States Department of Energy (US DOE) Contracts DE-AC02-09CH11466 (PPPL), DE-AC05-00OR22725 (ORNL), DE-AC52-07NA27344 (LLNL), DE-FG02-08ER54990 (Purdue University), and that of Sandia, a multi-program laboratory operated by Lockheed Martin Company, for the United States Department of Energy{\textquoteright}s National Nuclear Security Administration, under Contract DE-AC04-94AL85000.",

year = "2013",

doi = "10.1016/j.jnucmat.2013.01.100",

language = "English",

volume = "438",

pages = "S488--S492",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

number = "SUPPL",

}

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, pp. S488-S492. https://doi.org/10.1016/j.jnucmat.2013.01.100

TY - JOUR

T1 - Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor

AU - Kaita, R.

AU - Kugel, H. W.

AU - Abrams, T.

AU - Allain, J. P.

AU - Bell, M. G.

AU - Bell, R. E.

AU - Diallo, A.

AU - Gerhardt, S. P.

AU - Heim, B.

AU - Jaworski, M. A.

AU - Kallman, J.

AU - Kaye, S.

AU - LeBlanc, B. P.

AU - Maingi, R.

AU - Mansfield, D.

AU - McLean, A.

AU - Menard, J.

AU - Mueller, D.

AU - Nygren, R.

AU - Ono, M.

AU - Paul, S. F.

AU - Podesta, M.

AU - Raman, R.

AU - Roquemore, A. L.

AU - Sabbagh, S. A.

AU - Scotti, F.

AU - Skinner, C. H.

AU - Soukhanovskii, V. A.

AU - Taylor, C. N.

AU - Zakharov, L.

N1 - Funding Information: This work is supported by United States Department of Energy (US DOE) Contracts DE-AC02-09CH11466 (PPPL), DE-AC05-00OR22725 (ORNL), DE-AC52-07NA27344 (LLNL), DE-FG02-08ER54990 (Purdue University), and that of Sandia, a multi-program laboratory operated by Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration, under Contract DE-AC04-94AL85000.

PY - 2013

Y1 - 2013

N2 - 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.

AB - 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.

UR - http://www.scopus.com/inward/record.url?scp=84885480941&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2013.01.100

DO - 10.1016/j.jnucmat.2013.01.100

M3 - Article

AN - SCOPUS:84885480941

SN - 0022-3115

VL - 438

SP - S488-S492

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SUPPL

ER -

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

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