Disruption control on FTU and ASDEX upgrade with ECRH (Articolo in rivista)

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  • Disruption control on FTU and ASDEX upgrade with ECRH (Articolo in rivista) (literal)
Anno
  • 2009-01-01T00:00:00+01:00 (literal)
Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#doi
  • 10.1088/0029-5515/49/6/065014 (literal)
Alternative label
  • B. Esposito1, G. Granucci2, S. Nowak2, J.R. Martin-Solis3, L. Gabellieri1, E. Lazzaro2, P. Smeulders1, M. Maraschek4, G. Pautasso4, J. Stober4, W. Treutterer4, L. Urso4, F. Volpe4, H. Zohm4, FTU1, ECRH2,4 and ASDEX Upgrade4 Teams (2009)
    Disruption control on FTU and ASDEX upgrade with ECRH
    in Nuclear fusion
    (literal)
Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#autori
  • B. Esposito1, G. Granucci2, S. Nowak2, J.R. Martin-Solis3, L. Gabellieri1, E. Lazzaro2, P. Smeulders1, M. Maraschek4, G. Pautasso4, J. Stober4, W. Treutterer4, L. Urso4, F. Volpe4, H. Zohm4, FTU1, ECRH2,4 and ASDEX Upgrade4 Teams (literal)
Pagina inizio
  • 065014 (literal)
Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#url
  • http://iopscience.iop.org/0029-5515/49/6/065014 (literal)
Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#numeroVolume
  • 49 (literal)
Rivista
Note
  • ISI Web of Science (WOS) (literal)
Http://www.cnr.it/ontology/cnr/pubblicazioni.owl#affiliazioni
  • 1 Associazione EURATOM-ENEA sulla Fusione, C.R. Frascati, Via E. Fermi 45, 00044 Frascati (Roma), Italy 2 Associazione EURATOM-ENEA sulla Fusione, IFP-CNR, Via R. Cozzi 53, 20125 Milano, Italy 3 Departamento de Fisica, Universidad Carlos III de Madrid, 28911 Leganes, Madrid, Spain 4 Max-Planck-Institut f¨ur Plasmaphysik, EURATOM Association, Boltzmannstrasse 2, 85748 Garching bei M¨unchen, Germany (literal)
Titolo
  • Disruption control on FTU and ASDEX upgrade with ECRH (literal)
Abstract
  • The use of ECRH has been investigated as a promising technique to avoid or postpone disruptions in dedicated experiments in FTU and ASDEX Upgrade. Disruptions have been produced by injecting Mo through laser blow-off (FTU) or by puffing deuterium gas above the Greenwald limit (FTU and ASDEX Upgrade). The toroidal magnetic field is kept fixed and the ECRH launching mirrors have been steered before every discharge in order to change the deposition radius. The loop voltage signal is used as disruption precursor to trigger the ECRH power before the plasma current quench. In the FTU experiments (Ip = 0.35-0.5 MA, Bt = 5.3T, PECRH = 0.4-1.2MW) it is found that the application of ECRH modifies the current quench starting time depending on the power deposition location. A scan in deposition location has shown that the direct heating of one of the magnetic islands produced by magnetohydrodynamic (MHD) resistive instabilities (either m/n = 3/2, 2/1 or 3/1) prevents its further growth and also produces the stabilization of the other coupled modes and the delay of the current quench or its full avoidance. Disruption avoidance and complete discharge recovery are obtained when the ECRH power is applied on rational surfaces. The modes involved in the disruption are found to be tearing modes stabilized by a strong local ECRH heating. The Rutherford equation has been used to reproduce the evolution of the MHD modes. In the ASDEX Upgrade experiments L-mode plasmas (Ip = 0.6 MA, Bt = 2.5T, PECRH = 0.6MW ~ POHM) the injection of ECRH close to q = 2 significantly delays the 2/1 onset and prolongs the duration of the discharge: during this phase the density continues to increase. No delay in the onset of the 2/1 mode is observed when the injected power is reduced to 0.35MW. (literal)
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