Simulations of NSTX with a Liquid Lithium Divertor Module

Conference · Tue Jul 08 00:00:00 EDT 2008

OSTI ID:958413

D. P. Stotler, R. Maingi, H.W. Kugel, A. Yu. Pigarov, T.D. Rognlien, V.A. Soukhanovskii

The UEDGE edge plasma transport code is used to model the effect of the reduced recycling provided by the Liquid Lithium Divertor (LLD) module that will be installed in NSTX. UEDGE's transport coefficients are calibrated against an existing NSTX shot using midplane and divertor diagnostic data. The LLD is then 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 indicate that lithium evaporation will be negligible for pulse lengths < 2 s at low (~ 2 MW) input power. At high input power (~ 7 MW), the pulse length may have to be restricted.

• Research Organization: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-AC02-76CHO3073
• OSTI ID: 958413
• Report Number(s): PPPL-4331; TRN: US1000377
• Resource Relation: Conference: 18th International Conference of Plasma Surface Interactions, Toledo, Spain May 26-30, 2008
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DIVERTORS
EVAPORATION
HEAT FLUX
HEAT TRANSFER
LITHIUM
PLASMA
RECYCLING
TRANSPORT
Computer Simulation Tokamaks
NSTX
Lithium