Počet záznamů: 1  

Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks

  1. 1.
    SYSNO ASEP0531255
    Druh ASEPJ - Článek v odborném periodiku
    Zařazení RIVJ - Článek v odborném periodiku
    Poddruh JČlánek ve WOS
    NázevScaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks
    Tvůrce(i) Horáček, Jan (UFP-V) RID, ORCID
    Adámek, Jiří (UFP-V) RID, ORCID
    Komm, Michael (UFP-V) RID, ORCID
    Seidl, Jakub (UFP-V) RID
    Vondráček, Petr (UFP-V) RID, ORCID
    Jardin, A. (FR)
    Guillemaut, C. (PT)
    Elmore, S. (GB)
    Thornton, A. (GB)
    Jiráková, Kateřina (UFP-V)
    Jaulmes, Fabien (UFP-V) ORCID
    Deng, G. (CN)
    Gao, X. (CN)
    Wang, L. (CN)
    Ding, R. (CN)
    Brunner, D. (US)
    LaBombard, B. (US)
    Olsen, J. (DK)
    Rasmussen, J.J. (DK)
    Nielsen, A.H. (DK)
    Naulin, V. (DK)
    Ezzat, M. (DK)
    Camacho, K. (FR)
    Hron, Martin (UFP-V) RID, ORCID
    Matthews, G. F. (GB)
    Celkový počet autorů25
    Číslo článku066016
    Zdroj.dok.Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
    Roč. 60, č. 6 (2020)
    Poč.str.12 s.
    Jazyk dok.eng - angličtina
    Země vyd.AT - Rakousko
    Klíč. slovaCOMPASS-Upgrade ; divertor ; heat flux ; iter ; L-mode ; scaling ; tokamak
    Vědní obor RIVBL - Fyzika plazmatu a výboje v plynech
    Obor OECDFluids and plasma physics (including surface physics)
    CEPGA19-15229S GA ČR - Grantová agentura ČR
    LM2015045 GA MŠMT - Ministerstvo školství, mládeže a tělovýchovy
    EF16_013/0001551 GA MŠMT - Ministerstvo školství, mládeže a tělovýchovy
    Způsob publikováníOpen access
    Institucionální podporaUFP-V - RVO:61389021
    UT WOS000535881300001
    EID SCOPUS85085610465
    DOI10.1088/1741-4326/ab7e47
    AnotaceThis contribution aims to improve existing scalings of the L-mode power decay length λqomp, especially for plasma configurations with strike points at the ITER-relevant location closed vertical divertor targets. We propose 13 new λqomp scalings based on data from the tokamaks JET, EAST, MAST, Alcator C-mod and COMPASS, and validate them against the output of the 2D turbulence code HESEL. The analysis covers 500 divertor heat flux profiles (obtained by probes or IR cameras), measured in L-mode discharges with varying 12 global plasma parameters (all well predictable). We find that the two previously published scalings (Eich 2013 J. Nucl. Mat. 438 S72) and (Scarabosio 2013 J. Nucl. Mat. 438 S426), which were based on outer target data from AUG and JET, describe the JET, C-mod and COMPASS profiles well. This holds not only at the outer horizontal and vertical targets, but surprisingly also at the inner vertical targets. In contrast, EAST, HESEL and especially MAST data are poorly described by these two scalings. We therefore derive 13 new scalings, which account for 85-92 % of the measured λqomp variability across all five tokamaks. Although each of the scalings is based on a different parameter combination, their predictions for the ITER and COMPASS-Upgrade tokamaks are very similar. Just before the L-H transition in the ITER baseline scenario, the presented scalings predict values λqomp = 3.0 ± 0.5 mm. For the COMPASS-Upgrade tokamak, all the scalings predict λqomp = 2.1 ± 0.5 mm with a single exception of the scaling based on the stored plasma energy which predicts only 1.2 mm for both tokamaks. We encourage the reader to use as many of these scalings as possible, depending on available data. In attached plasma and using significant assumptions, our results imply steady-state surface-perpendicular heat flux around 10 MW/m2 for ITER, and 20 MW/m2 for COMPASS-Upgrade.
    PracovištěÚstav fyziky plazmatu
    KontaktVladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975
    Rok sběru2021
    Elektronická adresahttps://iopscience.iop.org/article/10.1088/1741-4326/ab7e47/pdf
Počet záznamů: 1  

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