Simulations of a high-density, highly-radiating lithium divertor
Abstract
Results are presented for one- and two-dimensional (2D) edge plasma transport simulations for strong injection of lithium (Li) in the divertor region of a tokamak. The model includes the scrape-off layer and divertor regions, and, for 2D, a small region inside the magnetic separtrix. Equations are solved for the density and momentum of a deuterium/tritium (DT) species and all three charge states of Li, in addition to separate ion and electron energy equations via the UEDGE code. Equations are also included for the DT and Li gas species. Lithium gas is injected from the side walls or divertor plate, implying that these surfaces are evaporating liquid Li. For a range of Li gas input, steady-state, detached-plasma solutions are shown where greater than 90% of the exhaust power is radiated by Li, resulting in peak surface heat fluxes ~2 MW/m2 on the divertor plate, outer wall, and private-flux wall. While Li ions dominate in the divertor leg, their density is in the range of 10% of the DT density at the midplane. The collisional parallel thermal force plays a key role in determining the midplane ion Li density, and sensitivity of results to different model assumptions are discussed. Here the keymore »
- Authors:
-
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Publication Date:
- Research Org.:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1511432
- Grant/Contract Number:
- AC02-09CH11466; AC52-07NA27344; AC02-76CHO3073
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Materials and Energy
- Additional Journal Information:
- Journal Volume: 18; Journal Issue: C; Journal ID: ISSN 2352-1791
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Citation Formats
Rognlien, T. D., Rensink, M. E., Emdee, E., Goldston, R. J., Schwartz, J., and Stotler, D. P. Simulations of a high-density, highly-radiating lithium divertor. United States: N. p., 2019.
Web. doi:10.1016/j.nme.2018.12.030.
Rognlien, T. D., Rensink, M. E., Emdee, E., Goldston, R. J., Schwartz, J., & Stotler, D. P. Simulations of a high-density, highly-radiating lithium divertor. United States. https://doi.org/10.1016/j.nme.2018.12.030
Rognlien, T. D., Rensink, M. E., Emdee, E., Goldston, R. J., Schwartz, J., and Stotler, D. P. Tue .
"Simulations of a high-density, highly-radiating lithium divertor". United States. https://doi.org/10.1016/j.nme.2018.12.030. https://www.osti.gov/servlets/purl/1511432.
@article{osti_1511432,
title = {Simulations of a high-density, highly-radiating lithium divertor},
author = {Rognlien, T. D. and Rensink, M. E. and Emdee, E. and Goldston, R. J. and Schwartz, J. and Stotler, D. P.},
abstractNote = {Results are presented for one- and two-dimensional (2D) edge plasma transport simulations for strong injection of lithium (Li) in the divertor region of a tokamak. The model includes the scrape-off layer and divertor regions, and, for 2D, a small region inside the magnetic separtrix. Equations are solved for the density and momentum of a deuterium/tritium (DT) species and all three charge states of Li, in addition to separate ion and electron energy equations via the UEDGE code. Equations are also included for the DT and Li gas species. Lithium gas is injected from the side walls or divertor plate, implying that these surfaces are evaporating liquid Li. For a range of Li gas input, steady-state, detached-plasma solutions are shown where greater than 90% of the exhaust power is radiated by Li, resulting in peak surface heat fluxes ~2 MW/m2 on the divertor plate, outer wall, and private-flux wall. While Li ions dominate in the divertor leg, their density is in the range of 10% of the DT density at the midplane. The collisional parallel thermal force plays a key role in determining the midplane ion Li density, and sensitivity of results to different model assumptions are discussed. Here the key issue is possible dilution of the core DT fuel. A brief comparison of the Li neutral solution is made with that from the Direct Simulation Monte-Carlo (DSMC) SPARTA code.},
doi = {10.1016/j.nme.2018.12.030},
journal = {Nuclear Materials and Energy},
number = C,
volume = 18,
place = {United States},
year = {Tue Jan 08 00:00:00 EST 2019},
month = {Tue Jan 08 00:00:00 EST 2019}
}
Web of Science
Figures / Tables:
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Works referencing / citing this record:
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Figures / Tables found in this record: