Simulations of NSTX with a Liquid Lithium Divertor Module

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

Princeton University. Plasma Physics Laboratory.

关键词: Heat Transfer;    Heat Flux;    70 Plasma Physics And Fusion Technology;    Transport Computer Simulationtokamaks, Nstx;    Computer Simulationtokamaks, Nstx;   

RP-ID  :  PPPL-4495
RP-ID  :  DE-ACO2-09CH11466
RP-ID  :  973090

美国|英语

来源: UNT Digital Library

【 摘 要 】

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.