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

R. Majeski; H. Kugel; R. Kaita; S. Avasarala; M. G. Bell; R. E. Bell; L. Berzak; P. Beiersdorfer; S. P. Gerhardt; E. Granstedt; T. Gray; C. Jacobson; J. Kallman; S. Kaye; T. Kozub; B. P. LeBlanc; J. Lepson; D. P. Lundberg; R. Maingi; D. Mansfield; S. F. Paul; G. V. Pereverzev; H. Schneider; V. Soukhanovskii; T. Strickler; D. Stotler; J. Timberlake; L. E. Zakharov

doi:10.1016/j.fusengdes.2010.03.020

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

R. Majeski, H. Kugel, R. Kaita, S. Avasarala, M. G. Bell, R. E. Bell, L. Berzak, P. Beiersdorfer, S. P. Gerhardt, E. Granstedt, T. Gray, C. Jacobson, J. Kallman, S. Kaye, T. Kozub, B. P. LeBlanc, J. Lepson, D. P. Lundberg, R. Maingi, D. MansfieldS. F. Paul, G. V. Pereverzev, H. Schneider, V. Soukhanovskii, T. Strickler, D. Stotler, J. Timberlake, L. E. Zakharov

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20 Scopus citations

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 wall in a tokamak to operate at reactor-relevant temperatures. The engineering of LTX will be discussed.

Original language	English (US)
Pages (from-to)	1283-1289
Number of pages	7
Journal	Fusion Engineering and Design
Volume	85
Issue number	7-9
DOIs	https://doi.org/10.1016/j.fusengdes.2010.03.020
State	Published - Dec 2010

All Science Journal Classification (ASJC) codes

Civil and Structural Engineering
Nuclear Energy and Engineering
General Materials Science
Mechanical Engineering

Keywords

Lithium
Plasma-facing components
Spherical tokamak

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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., ... Zakharov, L. E. (2010). The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX). Fusion Engineering and Design, 85(7-9), 1283-1289. https://doi.org/10.1016/j.fusengdes.2010.03.020

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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 wall in a tokamak to operate at reactor-relevant temperatures. The engineering of LTX will be discussed.",

keywords = "Lithium, Plasma-facing components, Spherical tokamak",

author = "R. Majeski and H. Kugel and R. Kaita and S. Avasarala and Bell, \{M. G.\} and Bell, \{R. E.\} and L. Berzak and P. Beiersdorfer and Gerhardt, \{S. P.\} and E. Granstedt and T. Gray and C. Jacobson and J. Kallman and S. Kaye and T. Kozub and LeBlanc, \{B. P.\} and J. Lepson and Lundberg, \{D. P.\} and R. Maingi and D. Mansfield and Paul, \{S. F.\} and Pereverzev, \{G. V.\} and H. Schneider and V. Soukhanovskii and T. Strickler and D. Stotler and J. Timberlake and Zakharov, \{L. E.\}",

year = "2010",

month = dec,

doi = "10.1016/j.fusengdes.2010.03.020",

language = "English (US)",

volume = "85",

pages = "1283--1289",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier B.V.",

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Majeski, R, Kugel, H, Kaita, R, Avasarala, S, Bell, MG, Bell, RE, Berzak, L, Beiersdorfer, P, Gerhardt, SP, Granstedt, E, Gray, T, Jacobson, C, Kallman, J, Kaye, S, Kozub, T, LeBlanc, BP, Lepson, J, Lundberg, DP, Maingi, R, Mansfield, D, Paul, SF, Pereverzev, GV, Schneider, H, Soukhanovskii, V, Strickler, T, Stotler, D, Timberlake, J & Zakharov, LE 2010, 'The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX)', Fusion Engineering and Design, vol. 85, no. 7-9, pp. 1283-1289. https://doi.org/10.1016/j.fusengdes.2010.03.020

TY - JOUR

T1 - The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX)

AU - Majeski, R.

AU - Kugel, H.

AU - Kaita, R.

AU - Avasarala, S.

AU - Bell, M. G.

AU - Bell, R. E.

AU - Berzak, L.

AU - Beiersdorfer, P.

AU - Gerhardt, S. P.

AU - Granstedt, E.

AU - Gray, T.

AU - Jacobson, C.

AU - Kallman, J.

AU - Kaye, S.

AU - Kozub, T.

AU - LeBlanc, B. P.

AU - Lepson, J.

AU - Lundberg, D. P.

AU - Maingi, R.

AU - Mansfield, D.

AU - Paul, S. F.

AU - Pereverzev, G. V.

AU - Schneider, H.

AU - Soukhanovskii, V.

AU - Strickler, T.

AU - Stotler, D.

AU - Timberlake, J.

AU - Zakharov, L. E.

PY - 2010/12

Y1 - 2010/12

N2 - 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.

AB - 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.

KW - Lithium

KW - Plasma-facing components

KW - Spherical tokamak

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SN - 0920-3796

VL - 85

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JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

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ER -

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

Abstract

All Science Journal Classification (ASJC) codes

Keywords

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