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Title: Suppressed gross erosion of high-temperature lithium via rapid deuterium implantation

Abstract

Lithium-coated high-Z substrates are planned for use in the NSTX-U divertor and are a candidate plasma facing component (PFC) for reactors, but it remains necessary to characterize the gross Li erosion rate under high plasma fluxes (>1023 m-2 s-1), typical for the divertor region. In this work, a realistic model for the compositional evolution of a Li/D layer is developed that incorporates first principles molecular dynamics (MD) simulations of D diffusion in liquid Li. Predictions of Li erosion from a mixed Li/D material are also developed that include formation of lithium deuteride (LiD). The erosion rate of Li from LiD is predicted to be significantly lower than from pure Li. This prediction is tested in the Magnum-PSI linear plasma device at ion fluxes of 1023–1024 m-2 s-1 and Li surface temperatures ≤800 °C. Li/LiD coatings ranging in thickness from 0.2 to 500 μm are studied. The dynamic D/Li concentrations are inferred via diffusion simulations. The pure Li erosion rate remains greater than Langmuir Law evaporation, as expected. For mixed-material Li/LiD surfaces, the erosion rates are reduced, in good agreement with modelling in almost all cases. These results imply that the temperature limit for a Li-coated PFC may be significantly highermore » than previously imagined.« less

Authors:
 [1];  [1];  [2];  [2]; ORCiD logo [1]; ORCiD logo [1];  [3];  [3];  [3];  [3]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Princeton Univ., Princeton, NJ (United States)
  3. FOM Institute DIFFER - Dutch Institute For Fundamental Energy Research, Nieuwegein (The Netherlands)
Publication Date:
Research Org.:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Princeton Univ., NJ (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1256597
Alternate Identifier(s):
OSTI ID: 1238844; OSTI ID: 1390517
Report Number(s):
PPPL-5114
Journal ID: ISSN 0029-5515
Grant/Contract Number:  
AC02-09CH11466; SC0008598
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 56; Journal Issue: 1; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; lithium; lithium sputtering; ion implantation; Magnum-PSI; liquid; metals; deuterium retention; liquid lithium; dynamics; bombardment; simulation; coatings

Citation Formats

Abrams, T., Jaworski, M. A., Chen, M., Carter, E. A., Kaita, R., Stotler, D. P., De Temmerman, G., Morgan, T. W., van den Berg, M. A., and van der Meiden, H. J. Suppressed gross erosion of high-temperature lithium via rapid deuterium implantation. United States: N. p., 2015. Web. doi:10.1088/0029-5515/56/1/016022.
Abrams, T., Jaworski, M. A., Chen, M., Carter, E. A., Kaita, R., Stotler, D. P., De Temmerman, G., Morgan, T. W., van den Berg, M. A., & van der Meiden, H. J. Suppressed gross erosion of high-temperature lithium via rapid deuterium implantation. United States. https://doi.org/10.1088/0029-5515/56/1/016022
Abrams, T., Jaworski, M. A., Chen, M., Carter, E. A., Kaita, R., Stotler, D. P., De Temmerman, G., Morgan, T. W., van den Berg, M. A., and van der Meiden, H. J. Thu . "Suppressed gross erosion of high-temperature lithium via rapid deuterium implantation". United States. https://doi.org/10.1088/0029-5515/56/1/016022. https://www.osti.gov/servlets/purl/1256597.
@article{osti_1256597,
title = {Suppressed gross erosion of high-temperature lithium via rapid deuterium implantation},
author = {Abrams, T. and Jaworski, M. A. and Chen, M. and Carter, E. A. and Kaita, R. and Stotler, D. P. and De Temmerman, G. and Morgan, T. W. and van den Berg, M. A. and van der Meiden, H. J.},
abstractNote = {Lithium-coated high-Z substrates are planned for use in the NSTX-U divertor and are a candidate plasma facing component (PFC) for reactors, but it remains necessary to characterize the gross Li erosion rate under high plasma fluxes (>1023 m-2 s-1), typical for the divertor region. In this work, a realistic model for the compositional evolution of a Li/D layer is developed that incorporates first principles molecular dynamics (MD) simulations of D diffusion in liquid Li. Predictions of Li erosion from a mixed Li/D material are also developed that include formation of lithium deuteride (LiD). The erosion rate of Li from LiD is predicted to be significantly lower than from pure Li. This prediction is tested in the Magnum-PSI linear plasma device at ion fluxes of 1023–1024 m-2 s-1 and Li surface temperatures ≤800 °C. Li/LiD coatings ranging in thickness from 0.2 to 500 μm are studied. The dynamic D/Li concentrations are inferred via diffusion simulations. The pure Li erosion rate remains greater than Langmuir Law evaporation, as expected. For mixed-material Li/LiD surfaces, the erosion rates are reduced, in good agreement with modelling in almost all cases. These results imply that the temperature limit for a Li-coated PFC may be significantly higher than previously imagined.},
doi = {10.1088/0029-5515/56/1/016022},
journal = {Nuclear Fusion},
number = 1,
volume = 56,
place = {United States},
year = {Thu Dec 17 00:00:00 EST 2015},
month = {Thu Dec 17 00:00:00 EST 2015}
}

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Works referencing / citing this record:

Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility
journal, June 2019


Fusion applications for lithium: wall conditioning in magnetic confinement devices
journal, October 2019


Deuterium addition to liquid Li–Sn alloys: implications for plasma-facing applications
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