NSTX plasma response to lithium coated divertor

Conference · Sat Jan 01 00:00:00 EST 2011

OSTI ID:1036623

Kugel, H W ^[1]; Bell, M G ^[1]; Allain, J P ^[2]; Bell, R E ^[1]; Ding, S ^[3]; Gerhardt, S P ^[1]; Jaworski, M A ^[1]; Kaita, R ^[1]; Kallman, J ^[1]; Kaye, S M ^[1]; LeBlanc, B P ^[1]; Maingi, Rajesh ^[4]; Majeski, R ^[1]; Maqueda, R J ^[1]; Mansfield, D K ^[1]; Mueller, D ^[1]; Nygren, R E ^[5]; Paul, S F ^[1]; Raman, R ^[6]; Roquemore, A L ^[1] ; Sabbagh, S A ^[7]; Schneider, H ^[1]; Skinner, C H ^[1]; Soukhanovskii, V A ^[8]; Taylor, C N ^[2]; Timberlake, J ^[1]; Wampler, W R ^[5]; Zakharov, L E ^[1]; Zweben, S J ^[1]

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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)

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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1036623
• 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

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CARBON
CONFINEMENT
DIVERTORS
ELECTRONS
GRAPHITE
IMPURITIES
ION TEMPERATURE
LITHIUM
PERFORMANCE
PLASMA
PLASMA DENSITY