Community Research and Development Information Service - CORDIS

Abstract

The study of long-duration high-power discharges need an efficient real time control of the plasma parameters, especially the plasma position when RF heating systems are used. On Tore Supra, recent improvements have been carried out: (a) for the poloidal interpolation and the radial extrapolation of the magnetic measurements, (b) for a better feedback matrix converting the radial errors of the plasma position to voltage values for the poloidal generators, and (c) for a very fast solution to find the plasma parameters from the knowledge of its surface. The plasma edge localisation is now controlled with a precision better than 1 cm and controlled within a few millimetres uncertainty for several tenths of seconds. Moreover, for advanced tokamak scenarios, a precise real time determination of safety factor, poloidal beta, internal inductance, Shafranov shift as well as online computation of the electron density and current density profiles are now available on Tore Supra. These quantities compare well with results from batch calculations using an equilibrium code. To fulfil the new requirements of plasma control for the CIEL project, a local control of the plasma edge position and curvature is planned for the near future.

Additional information

Authors: SAINT-LAURENT F, Association EURATOM-CEA, CEA Cadarache, Saint Paul lez Durance (FR);MARTIN G, Association EURATOM-CEA, CEA Cadarache, Saint Paul lez Durance (FR)
Bibliographic Reference: An article published in: Fusion Engineering and Design, 56-57 (2001), pp. 761 - 765.
Record Number: 200214399 / Last updated on: 2002-02-14
Category: PUBLICATION
Original language: en
Available languages: en