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Title: NSTX plasma response to lithium coated divertor

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 Z(eff) 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. (C) 2010 Elsevier B.V. All rights reserved.

Authors:
 [1];  [1];  [2];  [1];  [3];  [1];  [1];  [1];  [1];  [1];  [1];  [4];  [1];  [1];  [1];  [1];  [5];  [1];  [6];  [1] more »;  [7];  [1];  [1];  [8];  [2];  [1];  [5];  [1];  [1] « less
  1. Princeton Plasma Physics Laboratory (PPPL)
  2. Purdue University
  3. Academia Sinica, Institute of Plasma Physics, Hefei, China
  4. ORNL
  5. Sandia National Laboratories (SNL)
  6. University of Washington, Seattle
  7. Columbia University
  8. Lawrence Livermore National Laboratory (LLNL)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1036623
DOE Contract Number:  
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 19th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI), San Diego, CA, USA, 20100524, 20100528
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CARBON; CONFINEMENT; DIVERTORS; ELECTRONS; GRAPHITE; IMPURITIES; ION TEMPERATURE; LITHIUM; PERFORMANCE; PLASMA; PLASMA DENSITY

Citation Formats

Kugel, H W, Bell, M G, Allain, J P, Bell, R E, Ding, S, Gerhardt, S P, Jaworski, M A, Kaita, R, Kallman, J, Kaye, S M, LeBlanc, B P, Maingi, Rajesh, Majeski, R, Maqueda, R J, Mansfield, D K, Mueller, D, Nygren, R E, Paul, S F, Raman, R, Roquemore, A L, Sabbagh, S A, Schneider, H, Skinner, C H, Soukhanovskii, V A, Taylor, C N, Timberlake, J, Wampler, W R, Zakharov, L E, and Zweben, S J. NSTX plasma response to lithium coated divertor. United States: N. p., 2011. Web.
Kugel, H W, Bell, M G, Allain, J P, Bell, R E, Ding, S, Gerhardt, S P, Jaworski, M A, Kaita, R, Kallman, J, Kaye, S M, LeBlanc, B P, Maingi, Rajesh, Majeski, R, Maqueda, R J, Mansfield, D K, Mueller, D, Nygren, R E, Paul, S F, Raman, R, Roquemore, A L, Sabbagh, S A, Schneider, H, Skinner, C H, Soukhanovskii, V A, Taylor, C N, Timberlake, J, Wampler, W R, Zakharov, L E, & Zweben, S J. NSTX plasma response to lithium coated divertor. United States.
Kugel, H W, Bell, M G, Allain, J P, Bell, R E, Ding, S, Gerhardt, S P, Jaworski, M A, Kaita, R, Kallman, J, Kaye, S M, LeBlanc, B P, Maingi, Rajesh, Majeski, R, Maqueda, R J, Mansfield, D K, Mueller, D, Nygren, R E, Paul, S F, Raman, R, Roquemore, A L, Sabbagh, S A, Schneider, H, Skinner, C H, Soukhanovskii, V A, Taylor, C N, Timberlake, J, Wampler, W R, Zakharov, L E, and Zweben, S J. Sat . "NSTX plasma response to lithium coated divertor". United States.
@article{osti_1036623,
title = {NSTX plasma response to lithium coated divertor},
author = {Kugel, H W and Bell, M G and Allain, J P and Bell, R E and Ding, S and Gerhardt, S P and Jaworski, M A and Kaita, R and Kallman, J and Kaye, S M and LeBlanc, B P and Maingi, Rajesh and Majeski, R and Maqueda, R J and Mansfield, D K and Mueller, D and Nygren, R E and Paul, S F and Raman, R and Roquemore, A L and Sabbagh, S A and Schneider, H and Skinner, C H and Soukhanovskii, V A and Taylor, C N and Timberlake, J and Wampler, W R and Zakharov, L E and Zweben, S J},
abstractNote = {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 Z(eff) 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. (C) 2010 Elsevier B.V. All rights reserved.},
doi = {},
url = {https://www.osti.gov/biblio/1036623}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2011},
month = {1}
}

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