Journal article
Overview of the TCV tokamak experimental programme
Swiss Federal Institute of Technology Lausanne1
University of York2
Laboratory for Plasma Physics3
University of Rome Tor Vergata4
Aix-Marseille Université5
KU Leuven6
Dutch Institute for Fundamental Energy Research7
Institute of Plasma Physics and Laser Microfusion8
Chalmers University of Technology9
University of Milan - Bicocca10
National Technical University Kharkiv Polytechnic Institute11
Oak Ridge Associated Universities12
United Kingdom Atomic Energy Authority13
KTH Royal Institute of Technology14
University of Strathclyde15
University of Seville16
University of Wisconsin-Madison17
Massachusetts Institute of Technology18
Josef Stefan Institute19
VTT Technical Research Centre of Finland Ltd.20
Austrian Academy of Sciences21
University of Innsbruck22
National Research Council of Italy23
Aristotle University of Thessaloniki24
Polish Academy of Sciences Kraków Branch25
National Centre for Nuclear Research26
National and Kapodistrian University of Athens27
University of Texas at Austin28
Culham Centre for Fusion Energy29
Plasma Physics and Fusion Energy, Department of Physics, Technical University of Denmark30
Department of Physics, Technical University of Denmark31
Technical University of Denmark32
University of Naples Federico II33
Institute for Magnetic Fusion Research34
Institute of Nuclear Physics PAN35
Laboratorio Nacional de Fusíon36
National Institutes of Natural Sciences - National Institute for Fusion Science37
Forschungszentrum Jülich GmbH38
EUROfusion MST1 Team39
Max Planck Institute for Plasma Physics40
Eindhoven University of Technology41
University of California at San Diego42
Czech Academy of Sciences43
Consorzio RFX44
...and 34 moreThe tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system to address critical issues in preparation for ITER and a fusion power plant. For the 2019–20 campaign its configurational flexibility has been enhanced with the installation of removable divertor gas baffles, its diagnostic capabilities with an extensive set of upgrades and its heating systems with new dual frequency gyrotrons.
The gas baffles reduce coupling between the divertor and the main chamber and allow for detailed investigations on the role of fuelling in general and, together with upgraded boundary diagnostics, test divertor and edge models in particular. The increased heating capabilities broaden the operational regime to include Te/Ti ∼ 1 and have stimulated refocussing studies from L-mode to H-mode across a range of research topics.
ITER baseline parameters were reached in type-I ELMy H-modes and alternative regimes with ‘small’ (or no) ELMs explored. Most prominently, negative triangularity was investigated in detail and confirmed as an attractive scenario with H-mode level core confinement but an L-mode edge. Emphasis was also placed on control, where an increased number of observers, actuators and control solutions became available and are now integrated into a generic control framework as will be needed in future devices.
The quantity and quality of results of the 2019–20 TCV campaign are a testament to its successful integration within the European research effort alongside a vibrant domestic programme and international collaborations.
| Language: | English |
|---|---|
| Publisher: | IOP Publishing |
| Year: | 2022 |
| Pages: | 042018 |
| ISSN: | 17414326 , 00295515 and 10185577 |
| Types: | Journal article |
| DOI: | 10.1088/1741-4326/ac369b |
| ORCIDs: | 0000-0002-9726-1519 , Nielsen, Anders Henry , Rasmussen, Jens Juul , Salewski, M. , Schmidt, B. S. and Thrysøe, Alexander Simon |
