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Overview of the JET results

  • JET Contributors
  • JET-EFDA
  • JET
  • Institute for Plasma Research
  • University of Lisbon
  • Czech Academy of Sciences
  • CCFE
  • United Kingdom Atomic Energy Authority
  • Department of Pure and Applied Physics
  • Queen's University Belfast
  • VTT Technical Research Centre of Finland Ltd.
  • Aalto University
  • University of Tartu
  • University of Naples Federico II
  • CIEMAT
  • National Research Council of Italy
  • ITER
  • Russian Research Centre Kurchatov Institute
  • University of Rome La Sapienza
  • University of Naples Parthenope
  • Troitsk Institute for Innovation and Fusion Research
  • Department of Earth and Space Sciences
  • Chalmers University of Technology
  • Dept. of Physics and Astronomy
  • Uppsala University
  • Agenzia nazionale per le nuove tecnologie, l'energia e lo sviluppo economico sostenibile
  • Plasma and Radiation Physics
  • National Institute for Laser, Plasma and Radiation Physics
  • National Institute for Cryogenics and Isotopic Technology
  • Max Planck Institute for Plasma Physics
  • Dipartimento di Ingegneria Elettrica Elettronica e dei Sistemi
  • University of Catania
  • Commissariat à l’énergie atomique et aux énergies alternatives
  • Fusion for Energy
  • University of Latvia
  • EUROfusion Programme Management Unit
  • Jülich Research Centre

Research output: Contribution to journal › Article › peer-review

104 Scopus citations

Abstract

Since the installation of an ITER-like wall, the JET programme has focused on the consolidation of ITER design choices and the preparation for ITER operation, with a specific emphasis given to the bulk tungsten melt experiment, which has been crucial for the final decision on the material choice for the day-one tungsten divertor in ITER. Integrated scenarios have been progressed with the re-establishment of long-pulse, high-confinement H-modes by optimizing the magnetic configuration and the use of ICRH to avoid tungsten impurity accumulation. Stationary discharges with detached divertor conditions and small edge localized modes have been demonstrated by nitrogen seeding. The differences in confinement and pedestal behaviour before and after the ITER-like wall installation have been better characterized towards the development of high fusion yield scenarios in DT. Post-mortem analyses of the plasma-facing components have confirmed the previously reported low fuel retention obtained by gas balance and shown that the pattern of deposition within the divertor has changed significantly with respect to the JET carbon wall campaigns due to the absence of thermally activated chemical erosion of beryllium in contrast to carbon. Transport to remote areas is almost absent and two orders of magnitude less material is found in the divertor.

Original languageEnglish
Article number104001
JournalNuclear Fusion
Volume55
Issue number10
DOIs
StatePublished - 27 Mar 2015
Externally publishedYes

Bibliographical note

Publisher Copyright:
© 2015 EURATOM.

Funding

FundersFunder number
Horizon 2020 Framework Programme633053

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