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Power exhaust by core radiation at COMPASS tokamak
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SYSNO ASEP 0542717 Document Type J - Journal Article R&D Document Type Journal Article Subsidiary J Článek ve WOS Title Power exhaust by core radiation at COMPASS tokamak Author(s) Komm, Michael (UFP-V) RID, ORCID
Mancini, D. (IT)
Morbey, M. (NL)
Cavalier, Jordan (UFP-V) RID, ORCID
Adámek, Jiří (UFP-V) RID, ORCID
Bernert, M. (DE)
Bílková, Petra (UFP-V) RID
Böhm, Petr (UFP-V) RID
Brida, D. (DE)
Février, C. (FR)
Henderson, S. (GB)
Hron, Martin (UFP-V) RID, ORCID
Jeřáb, Martin (UFP-V) ORCID
Imríšek, Martin (UFP-V) RID
Kripner, Lukáš (UFP-V) ORCID
Naydenkova, Diana (UFP-V) RID, ORCID
Pánek, Radomír (UFP-V) RID
Šos, Miroslav (UFP-V) ORCID
Vondráček, Petr (UFP-V) RID, ORCIDNumber of authors 19 Article number 036016 Source Title Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
Roč. 61, č. 3 (2021)Number of pages 11 s. Language eng - English Country AT - Austria Keywords Argon ; Detachment ; Impurity seeding ; Neon ; Nuclear fusion ; Plasma ; Tokamak 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) Method of publishing Limited access Institutional support UFP-V - RVO:61389021 UT WOS 000617157000001 EID SCOPUS 85101461070 DOI 10.1088/1741-4326/abd3ea Annotation Substantial power dissipation in the edge plasma is required for the safe operation of ITER and next-step fusion reactors, otherwise unmitigated heat fluxes at the divertor plasma-facing components (PFCs) would easily exceed their material limits. Traditionally, such heat flux mitigation is linked to the regime of detachment, which is characterised by a significant pressure gradient between upstream and downstream scrape-off layer (SOL). However, the physics phenomena responsible for power dissipation and pressure loss are distinctly different, especially when the power dissipation is achieved by impurity seeding. In principle, it is possible to achieve substantial mitigation of the heat fluxes while maintaining conservation of the pressure along the open field lines in the SOL. This regime can be accessed by injection of medium-or high-Z impurities, which mostly radiate inside the last closed flux surface. The critical question related to such an approach is the effect on confinement and perspective fusion power generation in future thermonuclear reactors. In this work, we report on experiments at COMPASS tokamak, where neon and argon impurities were injected in ohmic or NBI-heated low confinement plasmas. With appropriate seeding waveform, stable scenarios were achieved, avoiding the radiative collapse of plasmas. Significant reduction of heat fluxes at the outer target was observed, with heat flux pattern similar to the one previously achieved by nitrogen seeding. The reduction of downstream pressure was, however, accompanied by an equal reduction of upstream pressure, indicating that the power dissipation occurred inside the separatrix. Indeed, the impurity cooling is causing a significant drop of edge temperature, however, the effect in the plasma centre is much less pronounced. Workplace Institute of Plasma Physics Contact Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Year of Publishing 2022 Electronic address https://iopscience.iop.org/article/10.1088/1741-4326/abd3ea
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