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Fundamental ICRF heating of deuterium ions in JET-DTE2

  • E. Lerche
  • , M. Maslov
  • , Ph Jacquet
  • , I. Monakhov
  • , D. King
  • , D. Keeling
  • , C. D. Challis
  • , D. Van Eester
  • , P. Mantica
  • , C. Maggi
  • , J. Garcia
  • , F. Auriemma
  • , R. Coelho
  • , I. Coffey
  • , A. Chomiczewska
  • , E. Delabie
  • , R. Dumont
  • , P. Dumortier
  • , J. Eriksson
  • , J. Ferreira
  • M. Fitzgerald, M. Fontana, Z. Ghani, N. Hawkes, J. Hobirk, Ph Huynh, T. Johnson, A. Kappatou, Y. Kazakov, V. Kiptily, K. Kirov, M. Lennholm, E. De La Luna, J. Mailloux, M. Marin, G. Matthews, S. Menmuir, J. Mitchell, M. Nocente, J. Ongena, A. Patel, G. Pucella, E. Rachlew, D. Rigamonti, F. Rimini, S. Silburn, P. Siren, M. Salewski, E. Solano, Z. Stancar, M. Tardocchi, M. Valisa
  • EURATOM-UKAEA Association Culham Science Centre
  • CNR
  • Commissariat à l'Énergie Atomique (CEA)
  • Consorzio Rfx
  • Instituto Superior Técnico
  • Queens University
  • Institute of Plasma Physics and Laser Microfusion
  • Oak Ridge National Laboratory
  • Uppsala University
  • Ecole Polytechnique Federale de Lausanne
  • Max-Planck-Institut für Plasmaphysik
  • KTH Royal Institute of Technology
  • Laboratorio Nacional de Fusión
  • ENEA Centro Ricerche Frascati
  • Technical University of Denmark
  • Jozef Stefan Institute

Publikation: Beitrag in FachzeitschriftKonferenzartikelBegutachtung

18 Zitate (Scopus)

Abstract

Beam-target reactions are responsible for a substantial fraction of the fusion power generated in D-T plasmas in JET-ILW (Be/W-wall), with ion temperatures of 10-12keV and large neutral-beam injection (NBI) power. It is known that injecting D beam ions with energies of ∼100-150keV in T-rich plasmas has a larger potential for beam-target fusion than in 50:50 D:T plasmas, but such a scenario was never developed in the past D-T experiments performed in JET-C (Carbon-wall) and in TFTR in the 90's. On top of the intrinsic advantages of using D beams in T-rich plasmas for D-T neutron production, simulations have shown that fundamental ion-cyclotron resonance heating (ICRH) of the D ions can significantly boost the net fusion reactivity, since both the thermalized D ions and the fast D-NBI ions are accelerated to energy ranges that are optimal for the D-T reaction cross-section. The beneficial effect of fundamental D ICRH on thermal D minorities in tritium plasmas (without NBI) was identified in the JET-C D-T experiments, but was not tested in high performance H-mode discharges with D-NBI heating. In 2021, dedicated JET-ILW DTE2 [1] experiments confirmed - for the first time - the improved fusion performance of T-rich plasmas with high D-NBI power and highlighted the key impact of fundamental D ICRH on the fusion reactivity. This new scenario lead to the world-wide 5s averaged fusion power (and energy) record in D-T tokamak plasmas with dominant beam-target reactions. A brief experimental overview followed by detailed RF wave / Fokker-Planck simulations including NBI-ICRH synergy will be presented, to disentangle the different components contributing to the high neutron yield achieved in these experiments.

OriginalspracheEnglisch
Aufsatznummer030005
FachzeitschriftAIP Conference Proceedings
Jahrgang2984
Ausgabenummer1
DOIs
PublikationsstatusVeröffentlicht - 18 Aug. 2023
Veranstaltung24th Topical Conference on Radio-frequency Power in Plasmas - Annapolis, USA/Vereinigte Staaten
Dauer: 26 Sept. 202228 Sept. 2022

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