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Comparing scrape-off layer and divertor physics in JET pure He and D discharges

  • R. A. Pitts
  • , P. Andrew
  • , Y. Andrew
  • , M. Becoulet
  • , I. Coffey
  • , D. Coster
  • , D. C. McDonald
  • , T. Eich
  • , S. K. Erents
  • , M. E. Fenstermacher
  • , W. Fundamenski
  • , G. Haas
  • , A. Hermann
  • , C. Hidalgo
  • , D. Hillis
  • , A. Huber
  • , L. C. Ingesson
  • , S. Jachmich
  • , A. Kallenbach
  • , A. Korotkov
  • K. Lawson, P. Lomas, T. Loarer, A. Loarte, G. F. Matthews, G. McCracken, A. Meigs, Ph Mertens, M. O'Mullane, V. Philipps, G. Porter, A. Pospieszczyk, J. Rapp, D. Reiter, V. Riccardo, G. Saibene, R. Sartori, M. F. Stamp, E. Tsitrone, M. Wischmeier, J. Gafert
  • Ecole Polytechnique Federale de Lausanne
  • Culham Centre for Fusion Energy
  • Commissariat à l'Énergie Atomique (CEA)
  • Max-Planck-Institut für Plasmaphysik
  • Lawrence Livermore National Laboratory
  • CIEMAT
  • Oak Ridge National Laboratory
  • Forschungszentrum Jülich GmbH
  • FOM-Instituut voor Plasmafysica 'Rijnhuizen'

Research output: Contribution to journalConference articlepeer-review

22 Citations (Scopus)

Abstract

Though helium plasmas are one option for the low activation phase of ITER, little effort has thus far been devoted to studying them in a large, diverted tokamak. A recent campaign on JET has therefore sought to address some of the important questions related to helium operation (He concentrations near 90%) in single null configuruations, particularly with regard to edge and divertor physics. This contribution compiles a selection of results from these experiments, in which, in each case, discharges have been chosen to match as closely as possible previous, well characterised D plasmas in both L and ELMing H-modes. These matched pulses are used to draw conclusions regarding the principle source and location of carbon production in D plasmas, to compare and contrast the mechanisms of the density limit and the detachment process in D and He, to investigate the nature of cross-field power transport in the SOL and to gain insight into the process by which ELM energy is transported to the divertor targets.

Original languageEnglish
Pages (from-to)777-786
Number of pages10
JournalJournal of Nuclear Materials
Volume313-316
Issue numberSUPPL.
DOIs
Publication statusPublished - Mar 2003
EventPlasma - Surface Interactions in Controlled Fusion Devices - Gifu, Japan
Duration: 26 May 200231 May 2002

Keywords

  • Carbon source
  • Density limit
  • Detachment
  • Divertor
  • Helium
  • Tokamak

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