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Overview of the JET results

  • JET Contributors
  • JET-EFDA
  • JET
  • Institute for Plasma Research
  • Instituto Superior Técnico
  • Institute of Plasma Physics AS CR
  • CCFE
  • Culham Centre for Fusion Energy
  • Department of Pure and Applied Physics
  • Queen's University of Belfast
  • VTT Technical Research Centre of Finland Ltd
  • Aalto University
  • University Tartu
  • University of Naples Federico II
  • Laboratorio Nacional de Fusión
  • IFP-CNR
  • ITER
  • Consorzio Rfx
  • Kurchatov Institute
  • University of Rome
  • Università di Napoli Parthenope
  • Troitsk Insitute of Innovating and Thermonuclear Research (TRINITI)
  • Dept. Earth and Space Sciences
  • Chalmers University of Technology
  • Department of Physics and Astronomy
  • Uppsala University
  • ENEA Centro Ricerche Frascati
  • Plasma and Radiation Physics
  • Plasma and Radiation Physics (INFLPR)
  • National Institute for Cryogenics and Isotopic Technology
  • Max-Planck-Institut für Plasmaphysik
  • Dipartimento di Ingegneria Elettrica Elettronica e dei Sistemi
  • Università degli Studi di Catania
  • CEA Cadarache
  • Fusion for Energy
  • University of Latvia (LU)
  • EUROfusion Programme Management Unit

Research output: Contribution to journalArticlepeer-review

104 Citations (Scopus)

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
Publication statusPublished - 27 Mar 2015
Externally publishedYes

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