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Title: Tokamak Simulation Code modeling of NSTX

Abstract

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.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Princeton Plasma Physics Lab., NJ (US)
Sponsoring Org.:
USDOE Office of Energy Research (ER) (US)
OSTI Identifier:
758640
Report Number(s):
PPPL-3472
TRN: US0003974
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 20 Jul 2000
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; NSTX DEVICE; T CODES; COMPUTER-AIDED DESIGN; OPERATION; STABILITY; PLASMA SIMULATION

Citation Formats

S.C. Jardin, S. Kaye, J. Menard, C. Kessel, and A.H. Glasser. Tokamak Simulation Code modeling of NSTX. United States: N. p., 2000. Web. doi:10.2172/758640.
S.C. Jardin, S. Kaye, J. Menard, C. Kessel, & A.H. Glasser. Tokamak Simulation Code modeling of NSTX. United States. doi:10.2172/758640.
S.C. Jardin, S. Kaye, J. Menard, C. Kessel, and A.H. Glasser. Thu . "Tokamak Simulation Code modeling of NSTX". United States. doi:10.2172/758640. https://www.osti.gov/servlets/purl/758640.
@article{osti_758640,
title = {Tokamak Simulation Code modeling of NSTX},
author = {S.C. Jardin and S. Kaye and J. Menard and C. Kessel and A.H. Glasser},
abstractNote = {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.},
doi = {10.2172/758640},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jul 20 00:00:00 EDT 2000},
month = {Thu Jul 20 00:00:00 EDT 2000}
}

Technical Report:

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