Tokamak Simulation Code modeling of NSTX

Jardin, S.C. ; Kaye, S. ; Menard, J. ; Kessel, C. ; Glasser, A.H.

Princeton University. Plasma Physics Laboratory.

关键词: 99 General And Miscellaneous//Mathematics, Computing, And Information Science;    Nstx Device;    70 Plasma Physics And Fusion Technology;    Plasma Simulation;    Stability;   

DOI  :  10.2172/758640
RP-ID  :  PPPL-3472
RP-ID  :  AC02-76CH03073
RP-ID  :  758640

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Tokamak Simulation Code [TSC] is widely used for the design of new axisymmetric toroidal experiments. In particular, TSC was used extensively in the design of the National Spherical Torus eXperiment [NSTX]. The authors have now benchmarked TSC with initial NSTX results and find excellent agreement for plasma and vessel currents and magnetic flux loops when the experimental coil currents are used in the simulations. TSC has also been coupled with a ballooning stability code and with DCON to provide stability predictions for NSTX operation. TSC has also been used to model initial CHI experiments where a large poloidal voltage is applied to the NSTX vacuum vessel, causing a force-free current to appear in the plasma. This is a phenomenon that is similar to the plasma halo current that sometimes develops during a plasma disruption.