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 »
- Authors:
-
more »
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- 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.
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
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.
@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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