Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U
Abstract
The application of lithium to plasma-facing components (PFCs) has long been used as a technique for wall conditioning in magnetic confinement devices to improve plasma performance. Determining the characteristics of PFCs at the time of exposure to the plasma, however, is difficult because they can only be analyzed after venting the vacuum vessel and removing them at the end of an operational period. The Materials Analysis and Particle Probe (MAPP) addresses this problem here by enabling PFC samples to be exposed to plasmas, and then withdrawn into an analysis chamber without breaking vacuum. The MAPP system was used to introduce samples that matched the metallic PFCs of the Lithium Tokamak Experiment (LTX). Lithium that was subsequently evaporated onto the walls also covered the MAPP samples, which were then subject to LTX discharges. In vacuo extraction and analysis of the samples indicated that lithium oxide formed on the PFCs, but improved plasma performance persisted in LTX. The reduced recycling this suggests is consistent with separate surface science experiments that demonstrated deuterium retention in the presence of lithium oxide films. Since oxygen decreases the thermal stability of the deuterium in the film, the release of deuterium was observed below the lithium deuteridemore »
- Authors:
-
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Univ. of Illinois, Urbana, IL (United States). Dept. of Nuclear, Plasma, & Radiological Engineering
- The College of New Jersey, Ewing, NJ (United States). Dept. of Physics
- Princeton Univ., NJ (United States). Dept. of Chemical & Biological Engineering
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Publication Date:
- Research Org.:
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Univ. of Illinois at Urbana-Champaign, IL (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- OSTI Identifier:
- 1512618
- Alternate Identifier(s):
- OSTI ID: 1416200
- Report Number(s):
- LLNL-JRNL-771458
Journal ID: ISSN 0920-3796; 960989
- Grant/Contract Number:
- AC52-07NA27344; AC02-09CH11466; SC0010717
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Fusion Engineering and Design
- Additional Journal Information:
- Journal Volume: 117; Journal ID: ISSN 0920-3796
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 42 ENGINEERING; lithium; plasma-surface interactions; materials science and technology
Citation Formats
Kaita, R., Lucia, M., Allain, J. P., Bedoya, F., Bell, R., Boyle, D., Capece, A., Jaworski, M., Koel, B. E., Majeski, R., Roszell, J., Schmitt, J., Scotti, F., Skinner, C. H., and Soukhanovskii, V. Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U. United States: N. p., 2016.
Web. doi:10.1016/j.fusengdes.2016.06.056.
Kaita, R., Lucia, M., Allain, J. P., Bedoya, F., Bell, R., Boyle, D., Capece, A., Jaworski, M., Koel, B. E., Majeski, R., Roszell, J., Schmitt, J., Scotti, F., Skinner, C. H., & Soukhanovskii, V. Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U. United States. https://doi.org/10.1016/j.fusengdes.2016.06.056
Kaita, R., Lucia, M., Allain, J. P., Bedoya, F., Bell, R., Boyle, D., Capece, A., Jaworski, M., Koel, B. E., Majeski, R., Roszell, J., Schmitt, J., Scotti, F., Skinner, C. H., and Soukhanovskii, V. Mon .
"Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U". United States. https://doi.org/10.1016/j.fusengdes.2016.06.056. https://www.osti.gov/servlets/purl/1512618.
@article{osti_1512618,
title = {Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U},
author = {Kaita, R. and Lucia, M. and Allain, J. P. and Bedoya, F. and Bell, R. and Boyle, D. and Capece, A. and Jaworski, M. and Koel, B. E. and Majeski, R. and Roszell, J. and Schmitt, J. and Scotti, F. and Skinner, C. H. and Soukhanovskii, V.},
abstractNote = {The application of lithium to plasma-facing components (PFCs) has long been used as a technique for wall conditioning in magnetic confinement devices to improve plasma performance. Determining the characteristics of PFCs at the time of exposure to the plasma, however, is difficult because they can only be analyzed after venting the vacuum vessel and removing them at the end of an operational period. The Materials Analysis and Particle Probe (MAPP) addresses this problem here by enabling PFC samples to be exposed to plasmas, and then withdrawn into an analysis chamber without breaking vacuum. The MAPP system was used to introduce samples that matched the metallic PFCs of the Lithium Tokamak Experiment (LTX). Lithium that was subsequently evaporated onto the walls also covered the MAPP samples, which were then subject to LTX discharges. In vacuo extraction and analysis of the samples indicated that lithium oxide formed on the PFCs, but improved plasma performance persisted in LTX. The reduced recycling this suggests is consistent with separate surface science experiments that demonstrated deuterium retention in the presence of lithium oxide films. Since oxygen decreases the thermal stability of the deuterium in the film, the release of deuterium was observed below the lithium deuteride dissociation temperature. This may explain what occurred when lithium was applied to the surface of the NSTX Liquid Lithium Divertor (LLD). The LLD had segments with individual heaters, and the deuterium-alpha emission was clearly lower in the cooler regions. The plan for NSTX-U is to replace the graphite tiles with high-Z PFCs, and apply lithium to their surfaces with lithium evaporation. Experiments with lithium coatings on such PFCs suggest that deuterium could still be retained if lithium compounds form, but limiting their surface temperatures may be necessary.},
doi = {10.1016/j.fusengdes.2016.06.056},
journal = {Fusion Engineering and Design},
number = ,
volume = 117,
place = {United States},
year = {Mon Jul 18 00:00:00 EDT 2016},
month = {Mon Jul 18 00:00:00 EDT 2016}
}
Web of Science
Figures / Tables:
Works referenced in this record:
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dataset, January 2016
- Kaita, R.; Lucia, M.; Allain, J.
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
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dataset, January 2016
- Kaita, R.; Lucia, M.; Allain, J. P.
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Hydrogen Retention in Lithium on Metallic Walls from "In Vacuo" Analysis in LTX and Implications for High-Z Plasma-Facing Components in NSTX-U
dataset, January 2016
- Kaita, R.; Lucia, M.; Allain, J.
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Works referencing / citing this record:
Fusion applications for lithium: wall conditioning in magnetic confinement devices
journal, October 2019
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Self-consistent modelling of a liquid metal box-type divertor with application to the divertor tokamak test facility: Li versus Sn
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Hydrogen Retention in Lithium on Metallic Walls from "In Vacuo" Analysis in LTX and Implications for High-Z Plasma-Facing Components in NSTX-U
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dataset, January 2016
- Kaita, R.; Lucia, M.; Allain, J. P.
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Figures / Tables found in this record: