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Title: The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX)

Abstract

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 provide comparisons between liquid walls in the Lithium Tokamak eXperiment (LTX) and liquid divertor targets in NSTX. LTX, which recently began operations at the Princeton Plasma Physics Laboratory, is the world's first confinement experiment with full liquid metal plasma-facing components (PFCs). All materials and construction techniques in LTX are compatible with liquid lithium. LTX employs an inner, heated, stainless steel-faced liner or shell, which will be lithium-coated. In order to ensure that lithium adheres to the shell, it is designed to operate at up to 500–600 °C to promote wetting of the stainless by the lithium, providing the first hot wallmore » in a tokamak to operate at reactor-relevant temperatures. The engineering of LTX will be discussed.« less

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [2];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [2];  [1];  [3];  [1] more »;  [1];  [4];  [1];  [2];  [1];  [1];  [1];  [1] « less
+ Show Author Affiliations
  1. Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
  2. Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
  3. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  4. Max-Planck-Institut Für Plasmaphysik, EURATOM Association, Garching (Germany)
Publication Date:
Research Org.:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
Contributing Org.:
NSTX Research Team; LTX Research Team
OSTI Identifier:
1898290
Report Number(s):
LLNL-JRNL-418592
Journal ID: ISSN 0920-3796; 380382; TRN: US2310869
Grant/Contract Number:  
AC52-07NA27344; AC02-09CH11466
Resource Type:
Accepted Manuscript
Journal Name:
Fusion Engineering and Design
Additional Journal Information:
Journal Volume: 85; Journal Issue: 7-9; Journal ID: ISSN 0920-3796
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; lithium; spherical tokamak; plasma facing components

Citation Formats

Majeski, R., Kugel, H., Kaita, R., Avasarala, S., Bell, M. G., Bell, R. E., Berzak, L., Beiersdorfer, P., Gerhardt, S. P., Granstedt, E., Gray, T., Jacobson, C., Kallman, J., Kaye, S., Kozub, T., LeBlanc, B. P., Lepson, J., Lundberg, D. P., Maingi, R., Mansfield, D., Paul, S. F., Pereverzev, G. V., Schneider, H., Soukhanovskii, V., Strickler, T., Stotler, D., Timberlake, J., and Zakharov, L. E. The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX). United States: N. p., 2010. Web. doi:10.1016/j.fusengdes.2010.03.020.
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Majeski, R., Kugel, H., Kaita, R., Avasarala, S., Bell, M. G., Bell, R. E., Berzak, L., Beiersdorfer, P., Gerhardt, S. P., Granstedt, E., Gray, T., Jacobson, C., Kallman, J., Kaye, S., Kozub, T., LeBlanc, B. P., Lepson, J., Lundberg, D. P., Maingi, R., Mansfield, D., Paul, S. F., Pereverzev, G. V., Schneider, H., Soukhanovskii, V., Strickler, T., Stotler, D., Timberlake, J., & Zakharov, L. E. The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX). United States. https://doi.org/10.1016/j.fusengdes.2010.03.020
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Majeski, R., Kugel, H., Kaita, R., Avasarala, S., Bell, M. G., Bell, R. E., Berzak, L., Beiersdorfer, P., Gerhardt, S. P., Granstedt, E., Gray, T., Jacobson, C., Kallman, J., Kaye, S., Kozub, T., LeBlanc, B. P., Lepson, J., Lundberg, D. P., Maingi, R., Mansfield, D., Paul, S. F., Pereverzev, G. V., Schneider, H., Soukhanovskii, V., Strickler, T., Stotler, D., Timberlake, J., and Zakharov, L. E. Wed . "The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX)". United States. https://doi.org/10.1016/j.fusengdes.2010.03.020. https://www.osti.gov/servlets/purl/1898290.
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@article{osti_1898290,
title = {The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX)},
author = {Majeski, R. and Kugel, H. and Kaita, R. and Avasarala, S. and Bell, M. G. and Bell, R. E. and Berzak, L. and Beiersdorfer, P. and Gerhardt, S. P. and Granstedt, E. and Gray, T. and Jacobson, C. and Kallman, J. and Kaye, S. and Kozub, T. and LeBlanc, B. P. and Lepson, J. and Lundberg, D. P. and Maingi, R. and Mansfield, D. and Paul, S. F. and Pereverzev, G. V. and Schneider, H. and Soukhanovskii, V. and Strickler, T. and Stotler, D. and Timberlake, J. and Zakharov, L. E.},
abstractNote = {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 provide comparisons between liquid walls in the Lithium Tokamak eXperiment (LTX) and liquid divertor targets in NSTX. LTX, which recently began operations at the Princeton Plasma Physics Laboratory, is the world's first confinement experiment with full liquid metal plasma-facing components (PFCs). All materials and construction techniques in LTX are compatible with liquid lithium. LTX employs an inner, heated, stainless steel-faced liner or shell, which will be lithium-coated. In order to ensure that lithium adheres to the shell, it is designed to operate at up to 500–600 °C to promote wetting of the stainless by the lithium, providing the first hot wall in a tokamak to operate at reactor-relevant temperatures. The engineering of LTX will be discussed.},
doi = {10.1016/j.fusengdes.2010.03.020},
journal = {Fusion Engineering and Design},
number = 7-9,
volume = 85,
place = {United States},
year = {Wed Apr 14 00:00:00 EDT 2010},
month = {Wed Apr 14 00:00:00 EDT 2010}
}
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Publisher's Version of Record
https://doi.org/10.1016/j.fusengdes.2010.03.020
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Works referenced in this record:

Performance projections for the lithium tokamak experiment (LTX)
journal, April 2009

New capabilities and results for the National Spherical Torus Experiment
journal, July 2006

Li-CPS limiter in tokamak T-11M
journal, April 2003

The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment
journal, May 2008

  • Kugel, H. W.; Bell, M. G.; Ahn, J. -W.
  • Physics of Plasmas, Vol. 15, Issue 5
  • DOI: 10.1063/1.2906260

Transition to ELM-free improved H-mode by lithium deposition on NSTX graphite divertor surfaces
journal, June 2009

Impact of lithium-coated walls on plasma performance in the TJ-II stellarator
journal, June 2009

Equilibrium properties of spherical torus plasmas in NSTX
journal, November 2001

Exploration of spherical torus physics in the NSTX device
journal, March 2000

Edge-Localized-Mode Suppression through Density-Profile Modification with Lithium-Wall Coatings in the National Spherical Torus Experiment
journal, August 2009

First experiments with lithium limiter on FTU
journal, June 2007

Development of NSTX particle control techniques
journal, March 2005

Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment
journal, November 2009

Observations concerning the injection of a lithium aerosol into the edge of TFTR discharges
journal, December 2001

Enhanced Energy Confinement and Performance in a Low-Recycling Tokamak
journal, August 2006

Effect of lithium PFC coatings on NSTX density control
journal, June 2007

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