NSTX plasma response to lithium coated divertor

Title: NSTX plasma response to lithium coated divertor

Full Record
Other Related Research

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:

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] more »

Princeton Plasma Physics Laboratory (PPPL)
Purdue University
Academia Sinica, Institute of Plasma Physics, Hefei, China
ORNL
Sandia National Laboratories (SNL)
University of Washington, Seattle
Columbia University
Lawrence Livermore National Laboratory (LLNL)

Publication Date:: 2011-01-01

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.

Copy to clipboard


                    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.

Copy to clipboard


                    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.

Copy to clipboard


                    
@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}

}

Copy to clipboard

Conference:

Other availability

Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

NSTX Plasma Response to Lithium Coated Divertor

Technical Report H.W. Kugel, M.G. Bell, J.P. 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. Roquemore, S.A. Sabbagh, H. Schneider, C.H. Skinner, V.A. Soukhanovskii, C.N. Taylor, J.R. Timberlak, W.R. Wampler, L.E. Zakharov, S.J. Zweben, and the NSTX Research Team

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 chargemore »« less
https://doi.org/10.2172/1003011

Full Text Available
Evaporated Lithium Surface Coatings in NSTX

Conference Kugel, H W ; Mansfield, D ; Maingi, Rajesh ; ...

Two lithium evaporators were used to evaporate more than 100 g of lithium on to the NSTX lower divertor region. Prior to each discharge, the evaporators were withdrawn behind shutters, where they also remained during the subsequent HeGDC applied for periods up to 9.5 min. After the HeGDC, the shutters were opened and the LITERs were reinserted to deposit lithium on the lower divertor target for 10 min, at rates of 10-70 mg/min, prior to the next discharge. The major improvements in plasma performance from these lithium depositions include: (1) plasma density reduction as a result of lithium deposition; (2)more »« less
The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX)

Conference Majeski, R ; Kugel, H ; Kaita, R ; ...

Recent experiments on the National Spherical Torus eXperiment (NSTX) have shown the benefits of solid lithium coatings on carbon PFC's to diverted plasma performance, in both L- and H-mode confinement regimes. Better particle control, with decreased inductive flux consumption, and increased electron temperature, ion temperature, energy confinement time, and DD neutron rate were observed. Successive increases in lithium coverage resulted in the complete suppression of ELM activity in H-mode discharges. A liquid lithium divertor (LLD), which will employ the porous molybdenum surface developed for the LTX shell, is being installed on NSTX for the 2010 run period, and will providemore »« less
Evaporated lithium surface coatings in NSTX.

Conference Zakharov, L ; Gates, D ; Menard, J ; ...

Two lithium evaporators were used to evaporate more than 100 g of lithium on to the NSTX lower divertor region. Prior to each discharge, the evaporators were withdrawn behind shutters, where they also remained during the subsequent HeGDC applied for periods up to 9.5 min. After the HeGDC, the shutters were opened and the LITERs were reinserted to deposit lithium on the lower divertor target for 10 min, at rates of 10-70 mg/min, prior to the next discharge. The major improvements in plasma performance from these lithium depositions include: (1) plasma density reduction as a result of lithium deposition; (2)more »« less
Evaporated Lithium Surface Coatings in NSTX

Conference Kugel, H. W. ; Mansfield, D. ; Maingi, R. ; ... - Journal of Nuclear Materials (May 2008)

Two lithium evaporators were used to evaporate more than 100 g of lithium on to the NSTX lower divertor region. Prior to each discharge, the evaporators were withdrawn behind shutters, where they also remained during the subsequent HeGDC applied for periods up to 9.5 min. After the HeGDC, the shutters were opened and the LITERs were reinserted to deposit lithium on the lower divertor target for 10 min, at rates of 10-70 mg/min, prior to the next discharge. The major improvements in plasma performance from these lithium depositions include: 1) plasma density reduction as a result of lithium deposition; 2)more »« less
Full Text Available

Similar Records