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, experiments on devices with different aspect ratios and magnetic geometries like the National Spherical Torus Experiment (NSTX) continue to show the relationship between lithium PFCs and good confinement and stability. While such results are promising, their empirical nature do not reflect the detailed relationship between 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 (NSTX-U) that is nearing completion. New measurement capabilities include the Materials Analysis and Particle Probe (MAPP) for in situ surface analysis of samples exposed to tokamak plasmas. The OEDGE suite of codes, for example, will provide a new way 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 willmore »
- Authors:
-
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- University of Illinois, Urbana, IL (United States)
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1182198
- Report Number(s):
- PPPL-5059
Journal ID: ISSN 0093-3813; TRN: US1500503
- Grant/Contract Number:
- AC02-09CH11466; SC0010717
- Resource Type:
- Accepted Manuscript
- Journal Name:
- IEEE Transactions on Plasma Science
- Additional Journal Information:
- Journal Volume: 43; Journal Issue: 4; Journal ID: ISSN 0093-3813
- Publisher:
- IEEE
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Materials; Tokamaks, NSTX; Lithium
Citation Formats
Kaita, Robert, Abrams, Tyler, Jaworski, Michael, Lucia, Matthew, Nichols, Jacob H., Skinner, Charles H., Stotler, Daren, Allain, Jean Paul, and Bedoya, Felipe. Addressing the challenges of plasma-surface interactions in NSTX-U*. United States: N. p., 2015.
Web. doi: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*. United States. 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, and Bedoya, Felipe. Wed .
"Addressing the challenges of plasma-surface interactions in NSTX-U*". United States. https://doi.org/10.1109/TPS.2014.2385665. https://www.osti.gov/servlets/purl/1182198.
@article{osti_1182198,
title = {Addressing the challenges of plasma-surface interactions in NSTX-U*},
author = {Kaita, Robert and Abrams, Tyler and Jaworski, Michael and Lucia, Matthew and Nichols, Jacob H. and Skinner, Charles H. and Stotler, Daren and Allain, Jean Paul and Bedoya, Felipe},
abstractNote = {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, experiments on devices with different aspect ratios and magnetic geometries like the National Spherical Torus Experiment (NSTX) continue to show the relationship between lithium PFCs and good confinement and stability. While such results are promising, their empirical nature do not reflect the detailed relationship between 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 (NSTX-U) that is nearing completion. New measurement capabilities include the Materials Analysis and Particle Probe (MAPP) for in situ surface analysis of samples exposed to tokamak plasmas. The OEDGE suite of codes, for example, will provide a new way 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.},
doi = {10.1109/TPS.2014.2385665},
journal = {IEEE Transactions on Plasma Science},
number = 4,
volume = 43,
place = {United States},
year = {Wed Apr 01 00:00:00 EDT 2015},
month = {Wed Apr 01 00:00:00 EDT 2015}
}
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