Addressing the challenges of plasma-surface interactions in NSTX-U

Robert Kaita, Tyler Abrams, Michael Jaworski, Matthew Lucia, Jacob H. Nichols, Charles H. Skinner, Daren Stotler, Jean Paul Allain, Felipe Bedoya

Research output: Contribution to journalArticle

Abstract

The importance of conditioning plasma-facing components (PFCs) has long been recognized as a critical element in obtaining high-performance plasmas in magnetic confinement devices. Lithium coatings, for example, have been used for decades for conditioning PFCs. Since the initial studies on the Tokamak Fusion Test Reactor (TFTR), experiments on devices with different aspect ratios and magnetic geometries like the National Spherical Torus Experiment (NSTX) continue to show the relationship between the lithium PFCs and good confinement and stability. While such results are promising, their empirical nature do not reflect the detailed relationship between the PFCs and the dynamic conditions that occur in the tokamak environment. A first step developing an understanding such complexity will be taken in the upgrade to NSTX, or the National Spherical Torus Experiment-Upgrade (NSTX-U) that is nearing completion. New measurement capabilities include the materials analysis and particle probe for in situ surface analysis of samples exposed to tokamak plasmas. The onion-skin modeling for edge analysis (OEDGE) suite of codes, for example, will be used to model the underlying mechanisms for such material migration in NSTX-U. This will lead to a better understanding of how plasma-facing surfaces evolve during a shot, and how the composition of the plasma-facing surface influences the discharge performance we observe. This paper will provide an overview of these capabilities, and highlight their importance for NSTX-U plans to transition from carbon to high- {Z} PFCs.

Original languageEnglish (US)
Article number7021917
Pages (from-to)965-971
Number of pages7
JournalIEEE Transactions on Plasma Science
Volume43
Issue number4
DOIs
StatePublished - Apr 1 2015

Fingerprint

surface reactions
conditioning
lithium
shot
aspect ratio
fusion
reactors
coatings
probes
carbon
geometry

Keywords

  • Lithium
  • magnetic confinement
  • materials science and technology
  • plasma confinement.

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Condensed Matter Physics

Cite this

Kaita, R., Abrams, T., Jaworski, M., Lucia, M., Nichols, J. H., Skinner, C. H., ... Bedoya, F. (2015). Addressing the challenges of plasma-surface interactions in NSTX-U. IEEE Transactions on Plasma Science, 43(4), 965-971. [7021917]. https://doi.org/10.1109/TPS.2014.2385665

Addressing the challenges of plasma-surface interactions in NSTX-U. / Kaita, Robert; Abrams, Tyler; Jaworski, Michael; Lucia, Matthew; Nichols, Jacob H.; Skinner, Charles H.; Stotler, Daren; Allain, Jean Paul; Bedoya, Felipe.

In: IEEE Transactions on Plasma Science, Vol. 43, No. 4, 7021917, 01.04.2015, p. 965-971.

Research output: Contribution to journalArticle

Kaita, R, Abrams, T, Jaworski, M, Lucia, M, Nichols, JH, Skinner, CH, Stotler, D, Allain, JP & Bedoya, F 2015, 'Addressing the challenges of plasma-surface interactions in NSTX-U', IEEE Transactions on Plasma Science, vol. 43, no. 4, 7021917, pp. 965-971. https://doi.org/10.1109/TPS.2014.2385665
Kaita R, Abrams T, Jaworski M, Lucia M, Nichols JH, Skinner CH et al. Addressing the challenges of plasma-surface interactions in NSTX-U. IEEE Transactions on Plasma Science. 2015 Apr 1;43(4):965-971. 7021917. https://doi.org/10.1109/TPS.2014.2385665
Kaita, Robert ; Abrams, Tyler ; Jaworski, Michael ; Lucia, Matthew ; Nichols, Jacob H. ; Skinner, Charles H. ; Stotler, Daren ; Allain, Jean Paul ; Bedoya, Felipe. / Addressing the challenges of plasma-surface interactions in NSTX-U. In: IEEE Transactions on Plasma Science. 2015 ; Vol. 43, No. 4. pp. 965-971.
@article{eb8f24eff29447629b78d504208c5d49,
title = "Addressing the challenges of plasma-surface interactions in NSTX-U",
abstract = "The importance of conditioning plasma-facing components (PFCs) has long been recognized as a critical element in obtaining high-performance plasmas in magnetic confinement devices. Lithium coatings, for example, have been used for decades for conditioning PFCs. Since the initial studies on the Tokamak Fusion Test Reactor (TFTR), experiments on devices with different aspect ratios and magnetic geometries like the National Spherical Torus Experiment (NSTX) continue to show the relationship between the lithium PFCs and good confinement and stability. While such results are promising, their empirical nature do not reflect the detailed relationship between the PFCs and the dynamic conditions that occur in the tokamak environment. A first step developing an understanding such complexity will be taken in the upgrade to NSTX, or the National Spherical Torus Experiment-Upgrade (NSTX-U) that is nearing completion. New measurement capabilities include the materials analysis and particle probe for in situ surface analysis of samples exposed to tokamak plasmas. The onion-skin modeling for edge analysis (OEDGE) suite of codes, for example, will be used to model the underlying mechanisms for such material migration in NSTX-U. This will lead to a better understanding of how plasma-facing surfaces evolve during a shot, and how the composition of the plasma-facing surface influences the discharge performance we observe. This paper will provide an overview of these capabilities, and highlight their importance for NSTX-U plans to transition from carbon to high- {Z} PFCs.",
keywords = "Lithium, magnetic confinement, materials science and technology, plasma confinement.",
author = "Robert Kaita and Tyler Abrams and Michael Jaworski and Matthew Lucia and Nichols, {Jacob H.} and Skinner, {Charles H.} and Daren Stotler and Allain, {Jean Paul} and Felipe Bedoya",
year = "2015",
month = "4",
day = "1",
doi = "10.1109/TPS.2014.2385665",
language = "English (US)",
volume = "43",
pages = "965--971",
journal = "IEEE Transactions on Plasma Science",
issn = "0093-3813",
publisher = "Institute of Electrical and Electronics Engineers Inc.",
number = "4",

}

TY - JOUR

T1 - Addressing the challenges of plasma-surface interactions in NSTX-U

AU - Kaita, Robert

AU - Abrams, Tyler

AU - Jaworski, Michael

AU - Lucia, Matthew

AU - Nichols, Jacob H.

AU - Skinner, Charles H.

AU - Stotler, Daren

AU - Allain, Jean Paul

AU - Bedoya, Felipe

PY - 2015/4/1

Y1 - 2015/4/1

N2 - The importance of conditioning plasma-facing components (PFCs) has long been recognized as a critical element in obtaining high-performance plasmas in magnetic confinement devices. Lithium coatings, for example, have been used for decades for conditioning PFCs. Since the initial studies on the Tokamak Fusion Test Reactor (TFTR), experiments on devices with different aspect ratios and magnetic geometries like the National Spherical Torus Experiment (NSTX) continue to show the relationship between the lithium PFCs and good confinement and stability. While such results are promising, their empirical nature do not reflect the detailed relationship between the PFCs and the dynamic conditions that occur in the tokamak environment. A first step developing an understanding such complexity will be taken in the upgrade to NSTX, or the National Spherical Torus Experiment-Upgrade (NSTX-U) that is nearing completion. New measurement capabilities include the materials analysis and particle probe for in situ surface analysis of samples exposed to tokamak plasmas. The onion-skin modeling for edge analysis (OEDGE) suite of codes, for example, will be used to model the underlying mechanisms for such material migration in NSTX-U. This will lead to a better understanding of how plasma-facing surfaces evolve during a shot, and how the composition of the plasma-facing surface influences the discharge performance we observe. This paper will provide an overview of these capabilities, and highlight their importance for NSTX-U plans to transition from carbon to high- {Z} PFCs.

AB - The importance of conditioning plasma-facing components (PFCs) has long been recognized as a critical element in obtaining high-performance plasmas in magnetic confinement devices. Lithium coatings, for example, have been used for decades for conditioning PFCs. Since the initial studies on the Tokamak Fusion Test Reactor (TFTR), experiments on devices with different aspect ratios and magnetic geometries like the National Spherical Torus Experiment (NSTX) continue to show the relationship between the lithium PFCs and good confinement and stability. While such results are promising, their empirical nature do not reflect the detailed relationship between the PFCs and the dynamic conditions that occur in the tokamak environment. A first step developing an understanding such complexity will be taken in the upgrade to NSTX, or the National Spherical Torus Experiment-Upgrade (NSTX-U) that is nearing completion. New measurement capabilities include the materials analysis and particle probe for in situ surface analysis of samples exposed to tokamak plasmas. The onion-skin modeling for edge analysis (OEDGE) suite of codes, for example, will be used to model the underlying mechanisms for such material migration in NSTX-U. This will lead to a better understanding of how plasma-facing surfaces evolve during a shot, and how the composition of the plasma-facing surface influences the discharge performance we observe. This paper will provide an overview of these capabilities, and highlight their importance for NSTX-U plans to transition from carbon to high- {Z} PFCs.

KW - Lithium

KW - magnetic confinement

KW - materials science and technology

KW - plasma confinement.

UR - http://www.scopus.com/inward/record.url?scp=85027940831&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85027940831&partnerID=8YFLogxK

U2 - 10.1109/TPS.2014.2385665

DO - 10.1109/TPS.2014.2385665

M3 - Article

AN - SCOPUS:85027940831

VL - 43

SP - 965

EP - 971

JO - IEEE Transactions on Plasma Science

JF - IEEE Transactions on Plasma Science

SN - 0093-3813

IS - 4

M1 - 7021917

ER -