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It is often stated that an increase of the toroidal magnetic field on the plasma axis of tokamaks could be beneficial for future fusion reactors and will help in the economic viability of this new source of energy.
After the development associated with ITER magnets regarding prototype conductors, joints and model coils, it is now possible to have a realistic approach of the design of magnet systems for fusion application and in particular of the toroidal field (TF) conductor design. This approach is meaningful since the ITER size is relevant to that of future fusion reactors. A demonstration reactor, the construction of which is supposed to start in 20 years would likely not be very different of ITER as for the magnet system.

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)
Bibliographic Reference: An article published in: Fusion Engineering and Design (2006), Volume 81, Issues 20-22, Pages 2351-2359
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at:
Record Number: 200718996 / Last updated on: 2007-04-02
Original language: en
Available languages: en