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Abstract

The TORE SUPRA (TS) tokamak is the first important application of superconductivity in Plasma Physics on a large scale. Overall, despite the differences in design and size, the accumulated reliable experience over 16 years of operation is a useful tool to prepare the manufacture and the operation of the ITER magnets.
An overview is given about the main design choices of the superconducting toroidal field (TF) system. The acceptance tests of the systems are described with details concerning the problems encountered and solved during this phase.
The actual status of the system is described through a presentation of the present operation and of the solutions to mitigate the effects of fast safety discharges.
The behaviour of the TF system during long plasma discharges in TS is a good introduction to the situation in a steady state tokamak reactor. It can be observed that the long plasma discharges do not bring a significant cryogenic load.

Additional information

Authors: DUCHATEAU J L, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);TENA M, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR)
Bibliographic Reference: An article published in: Fusion Engineering and Design (2006), Volume 81, Issues 20-22, Pages 2297-2304
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://www.sciencedirect.com/science/journal/09203796
Record Number: 200718997 / Last updated on: 2007-04-02
Category: PUBLICATION
Original language: en
Available languages: en
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