Simulations of NSTX with a Liquid Lithium Divertor Module

Conference · Fri Jan 01 04:00:00 EST 2010

OSTI ID:1019015

Stotler, D P ^[1]; Maingi, Rajesh ^[2]; Zakharov, L E ^[1]; Kugel, H w ^[1]; Pigarov, A Y ^[3]; Rognlien, T D ^[4]; Soukhanovskii, V A ^[4]

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1. Princeton Plasma Physics Laboratory (PPPL)
2. ORNL
3. University of California, San Diego
4. Lawrence Livermore National Laboratory (LLNL)

A strategy to develop self-consistent simulations of the behavior of lithium in the Liquid Lithium Divertor (LLD) module to be installed in NSTX is described. In this initial stage of the plan, the UEDGE edge plasma transport code is used to simulate an existing NSTX shot, with UEDGE's transport coefficients set using midplane and divertor diagnostic data. The LLD is incorporated into the simulations as a reduction in the recycling coefficient over the outer divertor. Heat transfer calculations performed using the resulting heat flux profiles provide preliminary estimates on operating limits for the LLD as well as input data for subsequent steps in the LLD modeling effort. (C) 2010 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim

• Research Organization: Oak Ridge National Laboratory (ORNL)
• Sponsoring Organization: SC USDOE - Office of Science (SC)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1019015
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DIVERTORS
HEAT FLUX
HEAT TRANSFER
LITHIUM
PARALLEL PLASMA FLOWS
PLASMA
RECYCLING
SCRAPE-OFF LAYER
SIMULATION
SPHERICAL TORUS EXPERIMENT
TOKAMAK
TRANSPORT