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Abstract

The international thermonuclear experimental reactor (ITER) toroidal field (TF) magnet system consists of 18 superconducting coils using a 68 kA Nb3Sn conductor. In order to guarantee the performances of these coils prior to their installation, the test of at least one prototype coil at liquid helium temperature and full current is required. The test of all coils in the two-coil test configuration, with successive charging of each coil to nominal current is recommended. This requires a large test facility.

Additional information

Authors: LIBEYRE P, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);CIAZYNSKI D, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);DUCHATEAU J L, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);SCHILD T, CEA/DSM/DAPNIA, Centre de Saclay, Gif-sur-Yvette (FR);FIETZ W H, Forschungszentrum Karlsruhe, Association EURATOM-FZK, Institut für Hochleistungsimpuls- und Mikrowellentechnik, Karlsruhe (DE);ZAHN G, Forschungszentrum Karlsruhe, Association EURATOM-FZK, Institut für Hochleistungsimpuls- und Mikrowellentechnik, Karlsruhe (DE)
Bibliographic Reference: An article published in: Fusion Engineering and Design (2005), Volumes 75-79, Pages 81-85
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: 200718995 / Last updated on: 2007-04-02
Category: PUBLICATION
Original language: en
Available languages: en
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