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Divertor impurity seeding experiments at the COMPASS tokamak
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SYSNO ASEP 0509575 Document Type J - Journal Article R&D Document Type Journal Article Subsidiary J Článek ve WOS Title Divertor impurity seeding experiments at the COMPASS tokamak Author(s) Komm, Michael (UFP-V) RID, ORCID
Khodunov, I. (BE)
Cavalier, Jordan (UFP-V) RID, ORCID
Vondráček, Petr (UFP-V) RID, ORCID
Henderson, S. (GB)
Seidl, Jakub (UFP-V) RID
Horáček, Jan (UFP-V) RID, ORCID
Naydenkova, Diana (UFP-V) RID, ORCID
Adámek, Jiří (UFP-V) RID, ORCID
Bílková, Petra (UFP-V) RID
Böhm, Petr (UFP-V) RID
Devitre, A. (CR)
Dimitrova, Miglena (UFP-V) ORCID
Elmore, S. (GB)
Faitsch, M. (DE)
Háček, Pavel (UFP-V) RID, ORCID
Havlíček, Josef (UFP-V) RID, ORCID
Havránek, Aleš (UFP-V) ORCID
Imríšek, Martin (UFP-V) RID
Krbec, Jaroslav (UFP-V)
Peterka, Matěj (UFP-V) RID, ORCID
Pánek, Radomír (UFP-V) RID
Samoylov, O. (RU)
Šos, Miroslav (UFP-V) ORCID
Tomeš, Matěj (UFP-V)
Tomova, B. (BG)
Weinzettl, Vladimír (UFP-V) RID, ORCIDNumber of authors 27 Article number 106035 Source Title Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
Roč. 59, č. 10 (2019)Number of pages 15 s. Language eng - English Country AT - Austria Keywords detachment ; divertor ; nitrogen ; nuclear fusion ; tokamak Subject RIV BL - Plasma and Gas Discharge Physics OECD category Fluids and plasma physics (including surface physics) R&D Projects GA15-10723S GA ČR - Czech Science Foundation (CSF) GA16-14228S GA ČR - Czech Science Foundation (CSF) LM2015045 GA MŠMT - Ministry of Education, Youth and Sports (MEYS) Method of publishing Limited access Institutional support UFP-V - RVO:61389021 UT WOS 000484508000005 EID SCOPUS 85072730806 DOI 10.1088/1741-4326/ab34d2 Annotation Partial detachment is the desired regime for the baseline burning plasma scenario in ITER and other next-step devices, as it allows for the dissipation of the majority of the energy carried by charged particles through the scrape-off-layer and thus avoids localised heat flux deposition in the divertor region. The COMPASS tokamak is equipped with an open divertor and has a relatively short connection length, both factors being unfavourable for access to detachment. As such, it only allows for the approach to naturally detached operation at very high line-averaged densities (>1020 m-3), which are incompatible with maintaining the ELMy H-mode regime. In order to achieve detachment at lower densities, impurities (such as nitrogen) must be injected into the plasma in the divertor region. A series of experiments with impurity injection in the range of 1-9 1020 molecules per second at different locations in the divertor were performed with the aim being to cool the plasma and influence particle and heat transport onto the divertor targets and provoke partial detachment. Previously reported results (Komm et al 2017 Proc. of the 44th EPS Conf. P1.118) were largely extended by injection of nitrogen at the outer divertor target. In order to analyze the divertor heat flux footprint in seeded plasmas, the buffered heat flux q B was introduced, with the radial profile being approximated by an exponential decay. A new set of generic parameters the peak heat flux , the fraction of power reaching the target and divertor footprint spreading factor S f were proposed to characterise the divertor footprint under detached conditions. Workplace Institute of Plasma Physics Contact Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Year of Publishing 2020 Electronic address https://iopscience.iop.org/article/10.1088/1741-4326/ab34d2
Number of the records: 1