Simulations of a high-density, highly-radiating lithium divertor

Rognlien, T. D.; Rensink, M. E.; Emdee, E.; Goldston, R. J.; Schwartz, J.; Stotler, D. P.

doi:10.1016/j.nme.2018.12.030

Title: Simulations of a high-density, highly-radiating lithium divertor

Journal Article · Tue Jan 08 00:00:00 EST 2019 · Nuclear Materials and Energy

DOI:https://doi.org/10.1016/j.nme.2018.12.030· OSTI ID:1511432

Rognlien, T. D. ^[1]; Rensink, M. E. ^[1];

^[2]; Goldston, R. J. ^[2];

^[2];

^[2]

Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

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.

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Research Organization:: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC02-09CH11466; AC52-07NA27344; AC02-76CHO3073

OSTI ID:: 1511432

Journal Information:: Nuclear Materials and Energy, Vol. 18, Issue C; ISSN 2352-1791

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 8 works

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References (8)

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Cited By (1)

Vapor shielding of liquid lithium divertor target during steady state and transient events Marenkov, E.; Pshenov, A. Nuclear Fusion, Vol. 60, Issue 2 https://doi.org/10.1088/1741-4326/ab5eb5	journal	January 2020