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Overview of ASDEX upgrade results

  • the ASDEX Upgrade Team
  • , EUROfusion MST1 Team
  • Instituto Superior Técnico
  • VTT Technical Research Centre of Finland Ltd
  • Max-Planck-Institut für Plasmaphysik
  • Aalto University
  • Dutch Institute for Fundamental Energy Research
  • CCFE Fusion Association
  • Technical University of Munich
  • Consorzio Rfx
  • CEA/UVSQ/CNRS
  • Research Centre Julich
  • Univ.́ Henri Poincaré
  • ENEA Centro Ricerche Frascati
  • IFP-CNR
  • ENAC-IIC-GEL
  • University of Innsbruck
  • Wigner Research Centre for Physics
  • Soltan Institute for Nuclear Studies
  • Universität Karlsruhe/Forschungszentrum Karlsruhe
  • Technical University of Eindhoven
  • VR
  • General Atomics
  • University of Seville
  • The University of Texas at Austin
  • Max-Planck Computing and Data Facility
  • University of Suttgart
  • Technical University of Denmark
  • Budapest University of Technology and Economics
  • University of California, Los Angeles
  • Koninklijke Militaire School - Ecole Royale Militaire
  • IMBA Institute of Molecular Biotechnology of the Austrian Academy of Sciences
  • Hellenic Republic
  • University of York
  • University of California, Davis
  • Pompeu Fabra University (UPF)
  • University College Cork
  • Princeton Plasma Physics Laboratory
  • Ghent University
  • Chinese Academy of Sciences
  • Plasma Science and Fusion Center
  • Aix Marseille Université

Research output: Contribution to journalReview articlepeer-review

Abstract

The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design. Since 2015, AUG is equipped with a new pair of 3-strap ICRF antennas, which were designed for a reduction of tungsten release during ICRF operation. As predicted, a factor two reduction on the ICRF-induced W plasma content could be achieved by the reduction of the sheath voltage at the antenna limiters via the compensation of the image currents of the central and side straps in the antenna frame. There are two main operational scenario lines in AUG. Experiments with low collisionality, which comprise current drive, ELM mitigation/suppression and fast ion physics, are mainly done with freshly boronized walls to reduce the tungsten influx at these high edge temperature conditions. Full ELM suppression and non-inductive operation up to a plasma current of Ip = 0.8 MA could be obtained at low plasma density. Plasma exhaust is studied under conditions of high neutral divertor pressure and separatrix electron density, where a fresh boronization is not required. Substantial progress could be achieved for the understanding of the confinement degradation by strong D puffing and the improvement with nitrogen or carbon seeding. Inward/outward shifts of the electron density profile relative to the temperature profile effect the edge stability via the pressure profile changes and lead to improved/decreased pedestal performance. Seeding and D gas puffing are found to effect the core fueling via changes in a region of high density on the high field side (HFSHD). The integration of all above mentioned operational scenarios will be feasible and naturally obtained in a large device where the edge is more opaque for neutrals and higher plasma temperatures provide a lower collisionality. The combination of exhaust control with pellet fueling has been successfully demonstrated. High divertor enrichment values of nitrogen EN ≥ 10 have been obtained during pellet injection, which is a prerequisite for the simultaneous achievement of good core plasma purity and high divertor radiation levels. Impurity accumulation observed in the all-metal AUG device caused by the strong neoclassical inward transport of tungsten in the pedestal is expected to be relieved by the higher neoclassical temperature screening in larger devices.

Original languageEnglish
Article number102015
JournalNuclear Fusion
Volume57
Issue number10
DOIs
Publication statusPublished - 28 Jun 2017

Keywords

  • DEMO
  • ITER
  • nuclear fusion
  • tokamak physics

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