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Performance of Wendelstein 7-X stellarator plasmas during the first divertor operation phase

  • Wendelstein 7-X Team
  • Max Planck Institute for Plasma Physics
  • Laboratorio Nacional de Fusión
  • FORSCHUNGSZENTRUM JULICH GMBH
  • University of WisconsinMadison
  • National Institute for Fusion Science
  • Princeton Plasma Physics Laboratory
  • Massachusetts Institute of Technology
  • Greifswald University
  • Technical University of Denmark
  • CIEMAT
  • Wigner Research Centre for Physics
  • The Australian National University
  • Eindhoven University of Technology
  • University of Cagliari
  • Consorzio Rfx
  • Instituto Superior Técnico
  • Ioffe Physical-Technical Institute of the Russian Academy of Sciences
  • Commissariat à l'Énergie Atomique et aux Énergies Alternatives
  • Oak Ridge National Laboratory
  • University of Salerno
  • ENEA Centro Ricerche Frascati
  • Institute of Plasma Physics and Laser Microfusion
  • University of Szczecin
  • University of Milano-Bicocca
  • Auburn University
  • Karlsruher Institut für Technologie
  • Universidad Carlos III de Madrid
  • University of Stuttgart
  • Austrian Academy of Science
  • Institute for Nuclear Research
  • University of Opole
  • Aalto University
  • University of Maryland, College Park
  • Istituto di Fisica del Plasma Piero Caldirola
  • Kyoto University
  • Culham Centre for Fusion Energy
  • Physikalisch Technische Bundesanstalt (PTB)
  • Technical University of Berlin
  • Los Alamos National Laboratory

Onderzoeksoutput: Bijdrage aan een tijdschriftArtikelpeer review

110 Citaten (Scopus)

Samenvatting

Wendelstein 7-X is the first comprehensively optimized stellarator aiming at good confinement with plasma parameters relevant to a future stellarator power plant. Plasma operation started in 2015 using a limiter configuration. After installing an uncooled magnetic island divertor, extending the energy limit from 4 to 80 MJ, operation continued in 2017. For this phase, the electron cyclotron resonance heating (ECRH) capability was extended to 7 MW, and hydrogen pellet injection was implemented. The enhancements resulted in the highest triple product (6.5 × 1019 keV m-3 s) achieved in a stellarator until now. Plasma conditions [Te(0) ≈ Ti(0) ≈ 3.8 keV, τE > 200 ms] already were in the stellarator reactor-relevant ion-root plasma transport regime. Stable operation above the 2nd harmonic ECRH X-mode cutoff was demonstrated, which is instrumental for achieving high plasma densities in Wendelstein 7-X. Further important developments include the confirmation of low intrinsic error fields, the observation of current-drive induced instabilities, and first fast ion heating and confinement experiments. The efficacy of the magnetic island divertor was instrumental in achieving high performance in Wendelstein 7-X. Symmetrization of the heat loads between the ten divertor modules could be achieved by external resonant magnetic fields. Full divertor power detachment facilitated the extension of high power plasmas significantly beyond the energy limit of 80 MJ.

Originele taal-2Engels
Artikelnummer082504
TijdschriftPhysics of Plasmas
Volume26
Nummer van het tijdschrift8
DOI's
StatusGepubliceerd - 1 aug. 2019

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