Simulations of NSTX with a Liquid Lithium Divertor Module

Technical Report · Thu Feb 18 00:00:00 EST 2010

DOI:https://doi.org/10.2172/973090· OSTI ID:973090

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

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.

• Research Organization: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-ACO2-09CH11466
• OSTI ID: 973090
• Report Number(s): PPPL-4495; TRN: US1002742
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DIVERTORS
HEAT FLUX
HEAT TRANSFER
LITHIUM
PLASMA
RECYCLING
SIMULATION
TRANSPORT
Computer simulationTokamaks
NSTX