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Experimental evidence of very short power decay lengths in H-mode discharges in the COMPASS tokamak
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SYSNO ASEP 0581974 Document Type J - Journal Article R&D Document Type Journal Article Subsidiary J Článek ve WOS Title Experimental evidence of very short power decay lengths in H-mode discharges in the COMPASS tokamak Author(s) Hečko, Jan (UFP-V)
Komm, Michael (UFP-V) RID, ORCID
Šos, Miroslav (UFP-V) ORCID
Adámek, Jiří (UFP-V) RID, ORCID
Bílková, Petra (UFP-V) RID
Bogár, Klára (UFP-V) ORCID
Böhm, Petr (UFP-V) RID
Jaulmes, Fabien (UFP-V) ORCID
Mysiura, Illia (UFP-V)
Tomeš, Matěj (UFP-V)
Vondráček, Petr (UFP-V) RID, ORCID
Hron, Martin (UFP-V) RID, ORCID
Pánek, Radomír (UFP-V) RIDNumber of authors 13 Article number 015013 Source Title Plasma Physics and Controlled Fusion. - : Institute of Physics Publishing - ISSN 0741-3335
Roč. 66, č. 1 (2024)Number of pages 10 s. Language eng - English Country US - United States Keywords divertor heat flux ; H-mode ; power decay length ; scaling ; sol Subject RIV BL - Plasma and Gas Discharge Physics OECD category Fluids and plasma physics (including surface physics) R&D Projects LM2018117 GA MŠMT - Ministry of Education, Youth and Sports (MEYS) EF16_013/0001551 GA MŠMT - Ministry of Education, Youth and Sports (MEYS) GA19-15229S GA ČR - Czech Science Foundation (CSF) Method of publishing Open access Institutional support UFP-V - RVO:61389021 UT WOS 001121381400001 EID SCOPUS 85181871318 DOI 10.1088/1361-6587/ad08f0 Annotation Analysis of heat fluxes in scrape-off layer (SOL) plasma is important for the prediction of divertor tile heat loads in future reactor-sized tokamak machines. Typically, the radial heat flux profile can be accurately characterized by the decay length parameter λ q . The predictions are then based on the dependence of λ q on plasma and machine parameters. In recent years, several empirical scaling models were derived from a collective database of decay lengths observed in several large tokamaks as well as two spherical tokamaks. Most recently, a report from the TCV tokamak showed a deviation from several of the proposed models (Maurizio et al (TCV team) 2021 Nucl. Fusion 61 024003). In this work, ∼ 100 edge plasma profiles of ELMy H-mode discharges were collected from the COMPASS tokamak database for heat flux analysis. The COMPASS tokamak has a similar machine size and plasma parameters to the TCV tokamak, offering a valuable comparison. The λ q was measured in both downstream and upstream SOL utilizing a divertor probe array validated by an IR camera and Thomson scattering diagnostics. A comparison with the predictions of several scaling models indicated an occurrence of anomalously short (by a factor of 2-5) inter-ELM power decay lengths in both upstream and downstream, as well as a difference in λ q between these two regions. Possible causes related to the accuracy of magnetic reconstruction were eliminated and physics-based sources of apparent compression effects were hypothesized as a motivation for future research. Workplace Institute of Plasma Physics Contact Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Year of Publishing 2024 Electronic address https://iopscience.iop.org/article/10.1088/1361-6587/ad08f0
Number of the records: 1