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Redd, A.J.; Ignat, D.W.
Princeton Plasma Physics Laboratory, Princeton, NJ (United States). Funding organisation: USDOE Office of Energy Research (ER)(United States)1998
Princeton Plasma Physics Laboratory, Princeton, NJ (United States). Funding organisation: USDOE Office of Energy Research (ER)(United States)1998
AbstractAbstract
[en] The Lower Hybrid Simulation Code (LSC) is a computational model of lower hybrid current drive in the presence of an electric field. Details of geometry, plasma profiles, and circuit equations are treated. Two-dimensional velocity space effects are approximated in a one-dimensional Fokker-Planck treatment. The LSC was originally written to be a module for lower hybrid current drive called by the Tokamak Simulation Code (TSC), which is a numerical model of an axisymmetric tokamak plasma and the associated control systems. The TSC simulates the time evolution of a free boundary plasma by solving the MHD equations on a rectangular computational grid. The MHD equations are coupled to the external circuits (representing poloidal field coils) through the boundary conditions. The code includes provisions for modeling the control system, external heating, and fusion heating. The LSC module can also be called by the TRANSP code. TRANSP represents the plasma with an axisymmetric, fixed-boundary model and focuses on calculation of plasma transport to determine transport coefficients from data on power inputs and parameters reached. This manual covers the basic material needed to use the LSC. If run in conjunction with TSC, the ''TSC Users Manual'' should be consulted. If run in conjunction with TRANSP, on-line documentation will be helpful. A theoretical background of the governing equations and numerical methods is given. Information on obtaining, compiling, and running the code is also provided
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1 Feb 1998; 48 p; ALSO AVAILABLE FROM OSTI AS DE00003751; NTIS; US GOVT. PRINTING OFFICE DEP
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