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Current quench and vessel currents characterisation at the COMPASS tokamak

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    SYSNO ASEP0564322
    Document TypeJ - Journal Article
    R&D Document TypeJournal Article
    Subsidiary JČlánek ve WOS
    TitleCurrent quench and vessel currents characterisation at the COMPASS tokamak
    Author(s) Matveeva, Ekaterina (UFP-V)
    Havlíček, Josef (UFP-V) RID, ORCID
    Artola, F. J. (FR)
    Yanovskiy, Vadim (UFP-V) ORCID
    Havránek, Aleš (UFP-V) ORCID
    Adámek, Jiří (UFP-V) RID, ORCID
    Gerardin, Jonathan (UFP-V) ORCID
    Imríšek, Martin (UFP-V) RID
    Loarte, A. (FR)
    Ficker, Ondřej (UFP-V) ORCID
    Hronová-Bilyková, Olena (UFP-V) RID
    Weinzettl, Vladimír (UFP-V) RID, ORCID
    Pánek, Radomír (UFP-V) RID
    Number of authors13
    Article number125010
    Source TitlePlasma Physics and Controlled Fusion. - : Institute of Physics Publishing - ISSN 0741-3335
    Roč. 64, č. 12 (2022)
    Number of pages16 s.
    Languageeng - English
    CountryGB - United Kingdom
    Keywordsdisruption ; halo current ; tokamak ; compass
    Subject RIVBL - Plasma and Gas Discharge Physics
    OECD categoryFluids and plasma physics (including surface physics)
    R&D ProjectsEF16_019/0000768 GA MŠMT - Ministry of Education, Youth and Sports (MEYS)
    LM2018117 GA MŠMT - Ministry of Education, Youth and Sports (MEYS)
    Method of publishingLimited access
    Institutional supportUFP-V - RVO:61389021
    UT WOS000880428600001
    EID SCOPUS85142151621
    DOI10.1088/1361-6587/ac9928
    AnnotationThe characterisation of plasma current quench and understanding of its underlying physical processes play a crucial role when designing large fusion devices such as ITER. For the first time, an extensive analysis of the COMPASS tokamak disruption database is presented. A unique set of magnetic diagnostics allows the investigation of local toroidal and poloidal vessel currents, including currents flowing along the open magnetic field lines from the plasma to the vacuum vessel (VV) (i.e., halo currents). Area-normalised current quench times are in agreement with the ITPA 1.67 ms m(-2) lower limit. Extremely fast I-p quench rates of up to 0.6 MA ms(-1) are observed during runaway electron campaigns at COMPASS, which are under the ITPA lower limit. Vertical movement of the plasma column is accelerated by the I-p quench during major disruptions. Toroidal vessel currents of around 2% 4% of the predisruptive plasma current I-disr(p) I-p quench. Net poloidal eddy currents are obtained by Mirnov coils and diamagnetic loop, reaching 3% of I-disr(p) I-p . Geometric features of the VV structure and in-vessel component positions on the poloidal vessel current measurements are discussed.
    WorkplaceInstitute of Plasma Physics
    ContactVladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975
    Year of Publishing2023
    Electronic addresshttps://iopscience.iop.org/article/10.1088/1361-6587/ac9928
Number of the records: 1  

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