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Integration of a radiative divertor for heat load control into JET high triangularity ELMy H-mode plasmas

  • C. Giroud
  • , G. Maddison
  • , K. McCormick
  • , M. N.A. Beurskens
  • , S. Brezinsek
  • , S. Devaux
  • , T. Eich
  • , L. Frassinetti
  • , W. Fundamenski
  • , M. Groth
  • , A. Huber
  • , S. Jachmich
  • , A. Järvinen
  • , A. Kallenbach
  • , K. Krieger
  • , D. Moulton
  • , S. Saarelma
  • , H. Thomsen
  • , S. Wiesen
  • , A. Alonso
  • B. Alper, G. Arnoux, P. Belo, A. Boboc, A. Brett, M. Brix, I. Coffey, E. De La Luna, D. Dodt, P. De Vries, R. Felton, E. Giovanozzi, J. Harling, D. Harting, N. Hawkes, J. Hobirk, I. Jenkins, E. Joffrin, M. Kempenaars, M. Lehnen, T. Loarer, P. Lomas, J. Mailloux, D. McDonald, A. Meigs, P. Morgan, I. Nunes, C. Perez Van Thun, V. Riccardo, F. Rimini, A. Sirinnelli, M. Stamp, I. Voitsekhovitch
  • EFDA-JET
  • Culham Centre for Fusion Energy
  • Max-Planck-Institut für Plasmaphysik
  • FORSCHUNGSZENTRUM JULICH GMBH
  • KTH Royal Institute of Technology
  • Aalto University
  • Imperial College London
  • Laboratorio Nacional de Fusión
  • Instituto Superior Técnico
  • Queens University
  • FOM-Instituut voor Plasmafysica 'Rijnhuizen'
  • Associazione EURATOM-ENEA sulla Fusione
  • Commissariat à l'Énergie Atomique (CEA)

Résultats de recherche: Contribution à un journalArticleRevue par des pairs

65 Citations (Scopus)

Résumé

Experiments on JET with a carbon-fibre composite wall have explored the reduction of steady-state power load in an ELMy H-mode scenario at high Greenwald fraction 0.8, constant power and close to the L to H transition. This paper reports a systematic study of power load reduction due to the effect of fuelling in combination with seeding over a wide range of pedestal density ((48)×10 19m 3) with detailed documentation of divertor, pedestal and main plasma conditions, as well as a comparative study of two extrinsic impurity nitrogen and neon. It also reports the impact of steady-state power load reduction on the overall plasma behaviour, as well as possible control parameters to increase fuel purity. Conditions from attached to fully detached divertor were obtained during this study. These experiments provide reference plasmas for comparison with a future JET Be first wall and an all W divertor where the power load reduction is mandatory for operation.

langue originaleAnglais
Numéro d'article063022
journalNuclear Fusion
Volume52
Numéro de publication6
Les DOIs
étatPublié - juin 2012

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