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Overview of the TCV tokamak program: Scientific progress and facility upgrades

  • S. Coda
  • , J. Ahn
  • , R. Albanese
  • , S. Alberti
  • , E. Alessi
  • , S. Allan
  • , H. Anand
  • , G. Anastassiou
  • , Y. Andrèbe
  • , C. Angioni
  • , M. Ariola
  • , M. Bernert
  • , M. Beurskens
  • , W. Bin
  • , P. Blanchard
  • , T. C. Blanken
  • , J. A. Boedo
  • , T. Bolzonella
  • , F. Bouquey
  • , F. H. Braunmüller
  • H. Bufferand, P. Buratti, G. Calabró, Y. Camenen, D. Carnevale, F. Carpanese, F. Causa, R. Cesario, I. T. Chapman, O. Chellai, D. Choi, C. Cianfarani, G. Ciraolo, J. Citrin, S. Costea, F. Crisanti, N. Cruz, A. Czarnecka, J. Decker, G. De Masi, G. De Tommasi, D. Douai, M. Dunne, B. P. Duval, T. Eich, S. Elmore, B. Esposito, M. Faitsch, A. Fasoli, N. Fedorczak, F. Felici, O. Février, O. Ficker, S. Fietz, M. Fontana, L. Frassinetti, I. Furno, S. Galeani, A. Gallo, C. Galperti, S. Garavaglia, I. Garrido, B. Geiger, E. Giovannozzi, M. Gobbin, T. P. Goodman, G. Gorini, M. Gospodarczyk, G. Granucci, J. P. Graves, R. Guirlet, A. Hakola, C. Ham, J. Harrison, J. Hawke, P. Hennequin, B. Hnat, D. Hogeweij, J. Ph Hogge, C. Honoré, C. Hopf, J. Horáček, Z. Huang, V. Igochine, P. Innocente, C. Ionita Schrittwieser, H. Isliker, R. Jacquier, A. Jardin, J. Kamleitner, A. Karpushov, D. L. Keeling, N. Kirneva, M. Kong, M. Koubiti, J. Kovacic, A. Krämer-Flecken, N. Krawczyk, O. Kudlacek, B. Labit, E. Lazzaro, H. B. Le, B. Lipschultz, X. Llobet, B. Lomanowski, V. P. Loschiavo, T. Lunt, P. Maget, E. Maljaars, A. Malygin, M. Maraschek, C. Marini, P. Martin, Y. Martin, S. Mastrostefano, R. Maurizio, M. Mavridis, D. Mazon, R. McAdams, R. McDermott, A. Merle, H. Meyer, F. Militello, I. G. Miron, P. A. Molina Cabrera, J. M. Moret, A. Moro, D. Moulton, V. Naulin, F. Nespoli, A. H. Nielsen, M. Nocente, R. Nouailletas, S. Nowak, T. Odstrčil, G. Papp, R. Papřok, A. Pau, G. Pautasso, V. Pericoli Ridolfini, P. Piovesan, C. Piron, T. Pisokas, L. Porte, M. Preynas, G. Ramogida, C. Rapson, J. Juul Rasmussen, M. Reich, H. Reimerdes, C. Reux, P. Ricci, D. Rittich, F. Riva, T. Robinson, S. Saarelma, F. Saint-Laurent, O. Sauter, R. Scannell, Ch Schlatter, B. Schneider, P. Schneider, R. Schrittwieser, F. Sciortino, M. Sertoli, U. Sheikh, B. Sieglin, M. Silva, J. Sinha, C. Sozzi, M. Spolaore, T. Stange, T. Stoltzfus-Dueck, P. Tamain, A. Teplukhina, D. Testa, C. Theiler, A. Thornton, L. Tophøj, M. Q. Tran, C. Tsironis, C. Tsui, A. Uccello, S. Vartanian, G. Verdoolaege, K. Verhaegh, L. Vermare, N. Vianello, W. A.J. Vijvers, L. Vlahos, N. M.T. Vu, N. Walkden, T. Wauters, H. Weisen, M. Wischmeier, P. Zestanakis, M. Zuin
  • Ecole Polytechnique Federale de Lausanne
  • Commissariat à l'Énergie Atomique (CEA)
  • University of Napoli 'Federico II'
  • Istituto di Fisica del Plasma Piero Caldirola
  • Culham Centre for Fusion Energy
  • National Technical University of Athens
  • Max-Planck-Institut für Plasmaphysik
  • University of Napoli Parthenope
  • Eindhoven University of Technology
  • University of California, San Diego
  • Consorzio Rfx
  • ENEA Centro Ricerche Frascati
  • Université Aix Marseille
  • University of Rome Tor Vergata
  • FOM Institute DIFFER
  • Universitat Innsbruck
  • Instituto Superior Técnico
  • Institute of Plasma Physics and Laser Microfusion
  • Institute of Plasma Physics, Academy of Sciences of the Czech Republic
  • KTH Royal Institute of Technology
  • University of the Basque Country (UPV/EHU)
  • University of Milano-Bicocca
  • VTT Technical Research Centre of Finland
  • Ecole Polytechnique
  • University of Oxford
  • Aristotle University of Thessaloniki
  • Kurchatov Institute
  • National Research Nuclear University MEPhI
  • Jozef Stefan Institute
  • FORSCHUNGSZENTRUM JULICH GMBH
  • University of York
  • Durham University
  • National Institute for Laser, Plasma and Radiation Physics
  • Technical University of Denmark
  • University of Cagliari
  • MIT Plasma Science and Fusion Center
  • Princeton University
  • University of Ghent
  • Laboratoire de Conception et d'Intégration des Systèmes (LCIS)

Publikation: Beitrag in FachzeitschriftÜbersichtsartikelBegutachtung

69 Zitate (Scopus)

Abstract

The TCV tokamak is augmenting its unique historical capabilities (strong shaping, strong electron heating) with ion heating, additional electron heating compatible with high densities, and variable divertor geometry, in a multifaceted upgrade program designed to broaden its operational range without sacrificing its fundamental flexibility. The TCV program is rooted in a three-pronged approach aimed at ITER support, explorations towards DEMO, and fundamental research. A 1 MW, tangential neutral beam injector (NBI) was recently installed and promptly extended the TCV parameter range, with record ion temperatures and toroidal rotation velocities and measurable neutral-beam current drive. ITER-relevant scenario development has received particular attention, with strategies aimed at maximizing performance through optimized discharge trajectories to avoid MHD instabilities, such as peeling-ballooning and neoclassical tearing modes. Experiments on exhaust physics have focused particularly on detachment, a necessary step to a DEMO reactor, in a comprehensive set of conventional and advanced divertor concepts. The specific theoretical prediction of an enhanced radiation region between the two X-points in the low-field-side snowflake-minus configuration was experimentally confirmed. Fundamental investigations of the power decay length in the scrape-off layer (SOL) are progressing rapidly, again in widely varying configurations and in both D and He plasmas; in particular, the double decay length in L-mode limited plasmas was found to be replaced by a single length at high SOL resistivity. Experiments on disruption mitigation by massive gas injection and electron-cyclotron resonance heating (ECRH) have begun in earnest, in parallel with studies of runaway electron generation and control, in both stable and disruptive conditions; a quiescent runaway beam carrying the entire electrical current appears to develop in some cases. Developments in plasma control have benefited from progress in individual controller design and have evolved steadily towards controller integration, mostly within an environment supervised by a tokamak profile control simulator. TCV has demonstrated effective wall conditioning with ECRH in He in support of the preparations for JT-60SA operation.

OriginalspracheEnglisch
Aufsatznummer102011
FachzeitschriftNuclear Fusion
Jahrgang57
Ausgabenummer10
DOIs
PublikationsstatusVeröffentlicht - 23 Juni 2017

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