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22-27 October 2018
Mahatma Mandir Conference Centre
Asia/Kolkata timezone
CONFERENCE MATERIAL NOW AVAILABLE!

Development of a Lithium Vapor Box Divertor for Controlled Plasma Detachment

25 Oct 2018, 18:20
20m
Mahatma Mandir Conference Centre

Mahatma Mandir Conference Centre

Gandhinagar (nearest Airport: Ahmedabad), India
Oral FIP - Fusion Engineering, Integration and Power Plant Design FIP/3 DEMO & Advanced Technology

Speaker

Robert Goldston (Princeton Plasma Physics Laboratory)

Description

A lithium vapor-box configuration [1] has been proposed to provide volumetric radiative dissipation in the divertor region of tokamak plasmas. While recent experiments have achieved continuous vapor shielding in close proximity to a lithium coated target in Magnum-PSI [2], this approach seeks to provide controlled detachment far from the divertor target, in a lithium vapor cloud maintained through controlled evaporation and kept away from the main plasma through baffling and recondensation.

We performed edge-plasma simulations with the geometry and parameters of the recent FNSF study [3]. A set of calculations are performed with the 2D UEDGE plasma model and a simple diffusive neutral model [4]. To mimic a crude vapor-box, Li vapor is injected near the divertor plate from the private-flux and outer divertor leg regions and is removed assuming a wall albedo of 0.5 on both PF and outer walls, which allows steady state solutions. For a range of Li vapor input, steady-state, detached-plasma solutions are shown where well over 90% of the exhaust power is radiated by Li, resulting in peak surface heat fluxes ≤ 2 MW/m^2 on the divertor plate, outer wall, and?private-flux wall. While Li ions?dominate in the divertor leg, their density is much less?than the DT density at the midplane. Here the key?issue is possible dilution of the core DT fuel.

We also developed a simulation of the neutral lithium vapor flow in the divertor using the Stochastic PArallel Rarefied-gas Time- accurate Analyzer (SPARTA) Direct Simulation Monte Carlo (DSMC) code [5]. We have simulated the open geometry of the present FNSF design, as well as begun studies using (so far) a single baffle. While the original open geometry allows 75% of the lithium absorption in the plasma to occur in the far SOL, distant from the divertor leg, this is reduced to 5% through the use of a single baffle.

[1] R.J. Goldston, G.W. Hammett, M.A. Jaworski, J. Schwartz, Nucl. Mat. Eng. 12 (2017) 1118
[2] P. Rindt, ISLA Conference, Moscow 2017
[3] C.E. Kessel, J.P. Blanchard, A. Davis et al., Fusion Eng. Design (2017),
http://dx.doi.org/10.1016/j.fusengdes.2017.05.081.?
[4] T.D. Rognlien, M.E. Rensink, and D.P. Stotler, Fusion Eng. Design (2017),
http://dx.doi.org/10.1016/j.fusengdes.2017.07.024
[5] M.A Gallis et al., AIP Conference Proceedings 1628, 27 (2014); doi: 10.1063/1.4902571

Country or International Organization United States of America
Paper Number FIP/3-6

Primary author

Robert Goldston (Princeton Plasma Physics Laboratory)

Co-authors

Daren Stotler (Princeton Plasma Physics Laboratory) Mr Eric Emdee (Princeton Plasma Physics Laboratory) Mr Jacob Schwartz (Princeton Plasma Physics Laboratory) Dr Michael Jaworski (Princeton Plasma Physics Laboratory) Dr Rensink Marvin (Lawrence Livermore National Laboratory) Dr Thomas Rognlien (Lawrence Livermore National Laboratory)

Presentation Materials

Paper