Tokamak Simulation Code modeling of NSTX [electronic resource].
- Washington, D.C. : United States. Dept. of Energy. Office of Energy Research, 2000.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
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- 330 Kilobytes pages : digital, PDF file
- Additional Creators:
- United States. Department of Energy. Office of Energy Research
United States. Department of Energy. Office of Scientific and Technical Information
- 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.
- Published through SciTech Connect.
S. Kaye; J. Menard; C. Kessel; S.C. Jardin; A.H. Glasser.
Princeton Plasma Physics Lab., NJ (US)
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