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Stationary and transient divertor heat flux profiles and extrapolation to ITER

  • A. Herrmann
  • , T. Eich
  • , S. Jachmich
  • , M. Laux
  • , P. Andrew
  • , A. Bergmann
  • , A. Loarte
  • , G. Matthews
  • , J. Neuhauser
  • Max-Planck-Institut für Plasmaphysik
  • Culham Centre for Fusion Energy

Résultats de recherche: Contribution à un journalArticle de conférenceRevue par des pairs

82 Citations (Scopus)

Résumé

Experimental results on divertor heat load measurements from ASDEX Upgrade and JET are discussed. Thereby three topics are considered: (i) parameter dependence of steady state heat flux profiles, (ii) spatial distribution of the heat flux profile during type I edge localised modes (ELMs), and (iii) temporal evolution of the energy deposition during type I ELMs. No clear scaling of steady state heat flux profiles with plasma parameters is found. For different data sets a broadening of the heat flux profiles, a constant profile width, as well as a steepening with heating power is found. Extrapolation to ITER requires a review of the data. The heat flux profile is not significantly broadened during type I ELMs. Advantageous is the change of the in/out symmetry. The temporal behaviour of the energy deposition shows a strong increase of the heat flux on time scales of the ion sound speed and an exponential decay with about twice the rise time.

langue originaleAnglais
Pages (de - à)759-767
Nombre de pages9
journalJournal of Nuclear Materials
Volume313-316
Numéro de publicationSUPPL.
Les DOIs
étatPublié - mars 2003
EvénementPlasma - Surface Interactions in Controlled Fusion Devices - Gifu, Japon
Durée: 26 mai 200231 mai 2002

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