Počet záznamů: 1  

Impact of the ITER-like wall on divertor detachment and on the density limit in the JET tokamak

  1. 1.
    0394930 - ÚFP 2014 RIV NL eng J - Článek v odborném periodiku
    Huber, A. - Brezinsek, S. - Groth, M. - de Vries, P.C. - Riccardo, V. - van Rooij, G. - Sergienko, G. - Arnoux, G. - Boboc, A. - Bílková, Petra - Calabrò, G. - Clever, M. - Coenen, J.W. - Beurskens, M.N.A. - Eich, E. - Jachmich, S. - Lehnen, M. - Lerche, E. - Marsen, S. - Matthews, G. F. - McCormick, K. - Meigs, A.G. - Mertens, Ph. - Philipps, V. - Rapp, J. - Samm, U. - Stamp, M. - Wischmeier, M. - Wiesen, S. … celkem 30 autorů
    Impact of the ITER-like wall on divertor detachment and on the density limit in the JET tokamak.
    Journal of Nuclear Materials. Roč. 438, suppl (2013), S139-S147. ISSN 0022-3115. E-ISSN 1873-4820.
    [International Conference on Plasma-Surface Interactions in Controlled Fusion Devices/20./. Aachen, 21.05.2012-25.05.2012]
    Grant CEP: GA ČR GAP205/10/2055; GA MŠMT(CZ) LG11018
    Institucionální podpora: RVO:61389021
    Klíčová slova: plasma * tokamak
    Kód oboru RIV: BL - Fyzika plazmatu a výboje v plynech
    Impakt faktor: 2.016, rok: 2013
    http://www.sciencedirect.com/science/article/pii/S0022311513000305#

    L-mode and H-mode density limits with the ITER-like wall (ILW) have been investigated and compared with experiments in the JET carbon material configuration.The density limit is up to 40% higher in the JET-ILW.This is linked to the formerly higher radiation fraction and, correspondingly, to earlier divertor detachment in the JET-CFC.In the ILW configuration, the discharge demonstrates a stable operation with a completely detached outer divertor in L- and H-mode. In contrary to the well-known ‘heating power independent’ Greenwald limit, the L-mode densities limit increases moderately with rising heating power independently of the wall material.The H–L transition constitutes an effective undisruptive density limit for an H-mode plasma. Detachment itself does not trigger the H–L back transition and does not present a limit on plasma density. In the range of neutral beam heating 8–10.5 MW, no dependence of the H-mode density limit on the heating power was observed.
    Trvalý link: http://hdl.handle.net/11104/0223081

     
     
Počet záznamů: 1  

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