Published November 2005 | Version v1
Journal article

How should we test the ITER TF coils?

  • 1. Association Euratom-CEA, CEA/DSM/DRFC, Centre de Cadarache, F-13108 Saint Paul Lez Durance (France)
  • 2. CEA/DSM/DAPNIA, Centre de Saclay, F-91191 Gif-sur-Yvette (France)
  • 3. Association Euratom-Forschungszentrum Karlsruhe, P.O. Box 3640, D-76021 Karlsruhe (Germany)

Description

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 details

Identifiers

DOI
10.1016/j.fusengdes.2005.06.344;
PII
S0920-3796(05)00364-9;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
75-79
Journal Page Range
p. 81-85
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
23. symposium of fusion technology
Acronym
SOFT 23
Dates
20-24 Sep 2004
Place
Venice (Italy)

Optional Information

Copyright
Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.