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Abstract

The set of codes described here - ASTRA (Automatic System of Transport Analysis) - is a flexible and effective tool for the study of transport mechanisms in reactor-orientated facilities of the tokamak type. Flexibility is provided within the ASTRA system by a wide choice of standard relationships, functions and subroutines representing various transport coefficients, methods of auxiliary heating and other physical processes in the tokamak plasma, as well as by the possibility of pre-setting transport equations and variables for data output in a simple and conceptually transparent form. The transport code produced by the ASTRA system provides an adequate representation of the discharge for present experimental conditions.

Additional information

Authors: PEREVERZEV G V, Max-Planck-Institut für Plasmaphysik, Garching bei München (DE);YUSHMANOV P N ET AL., I.V. Kurchatov Institute of Atomic Energy, Moscow (SU)
Bibliographic Reference: Report: IPP 5/42 EN (1991) 61 pp.
Availability: Available from Max-Planck-Institut für Plasmaphysik, 8046 Garching bei München (DE)
Record Number: 199111590 / Last updated on: 1994-12-02
Category: PUBLICATION
Original language: en
Available languages: en