Implications of the tore-supra west-project on radio-frequency additionnal heating systems

Dominique Guilhem, Arnaud Argouarch, Jean Michel Bernard, Francis Bouquey, Laurent Colas, Lena Delpech, Frederic Durodie, Annika Ekedahl, Jan van Helvoirt, Julien Hillairet, Emmanuel Joffrin, Xavier Litaudon, Roland Magne, Daniele Milanesio, Jean Moerel, Patrick Mollard, Erik Wittebol, Joelle Achard, Arthur Armitano, Gilles Berger-ByNicolas Charabot, Marc Goniche, Jonathan Jacquot, Gilles Lombard, Marc Prou, Elodie Traisnel-Corbel, Robert Volpe, Karl Vulliez

Research output: Contribution to journalArticleAcademicpeer-review


This year Tore-Supra celebrated its 25 years of operation. During this long time, a number of technologies have been developed. First of all, it was mandatory to develop reliable superconducting magnets at ∼1.8 K, with superfluid helium as an efficient coolant. For the production of steady state discharge, three types of radio frequency (RF) additional heating systems have been developed: 1) lower hybrid current drive; 2) ion cyclotron resonance heating; and 3) electron cyclotron resonance heating. To cope with long lasting discharges (up to 380 s × 2.8 MW) and large RF additional heating power (12.3 MW × 3 s), actively cooled (AC) plasma facing components were deployed in Tore-Supra for the first time in a tokamak environment. Tore-Supra is now being modified into a D-shape axisymmetric tokamak with AC tungsten main chamber walls and a divertor, the WEST project (W-for tungsten-environment in steady-state tokamak). This new facility has the objective to offer ITER a test bed for validating the relevant AC metallic technologies in D-shape H-mode plasmas. In contrast to other metallic devices, such as JET and ASDEX Upgrade, WEST will rely only on the RF additional power systems. A set of plasma scenarios have been identified, ranging from a high total RF power scenario up to 15 MW in 30 s, to a high fluence scenario of 1000 s with up to 10 MW of injected RF power. These scenarios are able to reproduce ITER relevant conditions of steady state heat loads of 10-20 MW/m2, to test tungsten AC divertor technologies with relevant power heat fluxes and particle fluence.

Original languageEnglish
Article number6716017
Pages (from-to)600-605
Number of pages6
JournalIEEE Transactions on Plasma Science
Issue number3
Publication statusPublished - 17 Jan 2014


  • Plasma additional heating systems
  • radio-frequency (RF)
  • Tore-Supra
  • WEST-project


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