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Current quench and vessel currents characterisation at the COMPASS tokamak
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SYSNO ASEP 0564322 Document Type J - Journal Article R&D Document Type Journal Article Subsidiary J Článek ve WOS Title Current 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) RIDNumber of authors 13 Article number 125010 Source Title Plasma Physics and Controlled Fusion. - : Institute of Physics Publishing - ISSN 0741-3335
Roč. 64, č. 12 (2022)Number of pages 16 s. Language eng - English Country GB - United Kingdom Keywords disruption ; halo current ; tokamak ; compass Subject RIV BL - Plasma and Gas Discharge Physics OECD category Fluids and plasma physics (including surface physics) R&D Projects EF16_019/0000768 GA MŠMT - Ministry of Education, Youth and Sports (MEYS) Research Infrastructure COMPASS II - 90117 - Ústav fyziky plazmatu AV ČR, v. v. i. Method of publishing Limited access Institutional support UFP-V - RVO:61389021 UT WOS 000880428600001 EID SCOPUS 85142151621 DOI https://doi.org/10.1088/1361-6587/ac9928 Annotation The 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. Workplace Institute of Plasma Physics Contact Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Year of Publishing 2023 Electronic address https://iopscience.iop.org/article/10.1088/1361-6587/ac9928
Number of the records: 1