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Multi-machine scaling of main SOL parallel heat flux width in tokamak limiter plasmas

  1. 1.
    SYSNO ASEP0454403
    Document TypeC - Proceedings Paper (int. conf.)
    R&D Document TypeConference Paper
    TitleMulti-machine scaling of main SOL parallel heat flux width in tokamak limiter plasmas
    Author(s) Horáček, Jan (UFP-V) RID, ORCID
    Pitts, R.A. (FR)
    Gunn, J. (FR)
    Silva, C. (PT)
    Rudakov, D. (US)
    Arnoux, G. (GB)
    Marsen, S. (DE)
    Vondráček, Petr (UFP-V) RID, ORCID
    Maddaluno, G. (IT)
    Pericoli, V. (IT)
    Viola, B. (IT)
    Xu, G.S. (CN)
    Wang, H. (CN)
    Nie, L. (CN)
    LaBombard, B. (US)
    Brezinsek, S. (DE)
    Xu, Y. (DE)
    Shimada, M. (FR)
    Adámek, Jiří (UFP-V) RID, ORCID
    Popov, Tsv. (BG)
    Dimitrova, Miglena (UFP-V) ORCID
    Seidl, Jakub (UFP-V) RID
    Janky, Filip (UFP-V) RID
    Pánek, Radomír (UFP-V) RID
    Goldston, R.J. (US)
    Stangeby, P.C. (CA)
    Article numberO2.105
    Source TitleEPS 2015:42nd European Physical Society Conference on Plasma Physics, 39E. - Mulhouse : European Physical Society, 2015 - ISBN 2-914771-98-3
    Pageso2.105-o2.105
    Number of pages4 s.
    Publication formOnline - E
    ActionEPS 2015 Conference on Plasma Physics/42./
    Event date22.06.2015-26.06.2015
    VEvent locationLisbon
    CountryPT - Portugal
    Event typeEUR
    Languageeng - English
    CountryPT - Portugal
    Keywordstokamak ; plasma ; SOL ; ITER
    Subject RIVBL - Plasma and Gas Discharge Physics
    R&D ProjectsGAP205/12/2327 GA ČR - Czech Science Foundation (CSF)
    LM2011021 GA MŠMT - Ministry of Education, Youth and Sports (MEYS)
    Institutional supportUFP-V - RVO:61389021
    EID SCOPUS84979658169
    AnnotationDischarge on the ITER tokamak will preferably start and end up with plasma touching the inboard (HFS) limiter before shaping into the divertor configuration. In order to avoid exceeding the designed limit of the Beryllium enhanced heat flux limiters (4.7MW=m2), its shape has to be optimized in order to receive the power everywhere equally. The optimum shape has been derived based on observation that the SOL radial profile of the power flux decays mostly exponentially, qjj = q0jjexp(r=lomp q ).
    WorkplaceInstitute of Plasma Physics
    ContactVladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975
    Year of Publishing2016
Number of the records: 1  

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