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Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST
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SYSNO ASEP 0552289 Druh ASEP J - Článek v odborném periodiku Zařazení RIV J - Článek v odborném periodiku Poddruh J Článek ve WOS Název Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST Tvůrce(i) Gaspar, J. (FR)
Corre, Y. (FR)
Fedorczak, N. (FR)
Gunn, J. P. (FR)
Bourdelle, C. (FR)
Brezinsek, S. (DE)
Bucalossi, J. (FR)
Chanet, N. (FR)
Dejarnac, Renaud (UFP-V) RID, ORCID
Firdaouss, M. (FR)
Gardarein, J.-L. (FR)
Laffont, G. (FR)
Loarer, T. (FR)
Pocheau, C. (FR)
Tsitrone, E. (IT)Celkový počet autorů 15 Číslo článku 096027 Zdroj.dok. Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
Roč. 61, č. 9 (2021)Poč.str. 10 s. Jazyk dok. eng - angličtina Země vyd. AT - Rakousko Klíč. slova diagnostics comparison ; divertor ; heat load pattern ; infrared ; Langmuir probes ; thermocouples Vědní obor RIV BL - Fyzika plazmatu a výboje v plynech Obor OECD Fluids and plasma physics (including surface physics) Způsob publikování Omezený přístup Institucionální podpora UFP-V - RVO:61389021 UT WOS 000684701900001 EID SCOPUS 85114022169 DOI 10.1088/1741-4326/ac1803 Anotace WEST is a full W tokamak with an extensive set of diagnostics for heat load measurements especially in the lower divertor. It is composed by infrared thermography, thermal measurement with thermocouples and fibre Bragg grating embedded few mm below the surface and flush mounted Langmuir probes. A large database including different magnetic equilibrium and input power is investigated to compare the heat load pattern (location, amplitude of the peak and heat flux decay length) on the inner and outer strike point regions: from the first ohmic diverted plasma (obtained during the second experimental campaign C2 in 2018) up to the high power (8 MW total injected) and high energy (up to 90 MJ injected energy in lower single null configuration) experiments performed in the last experimental campaign (C4 in 2019). Concerning the peak location, a good agreement (<1 cm) is obtained between thermal inversions and flush-mounted LP measurements. The peak heat flux from the whole set of diagnostics is in good agreement and mainly in the 20% range, while the heat flux decay length reported on the target shows significant discrepancy between diagnostics and location in the machine ( 40% range). Despite such discrepancy, heat flux decay length at target is found to scale mainly with the magnetic flux expansion through the variation of the X-point height, as expected. The improved plasma performances achieved during C4 enabled to reach significant heat load in the divertor, up to 6 MW m-2 with 4 MW of additional heating power showing the capability to reach the ITER relevant heat load (10 MW m-2 steady state) with about 7 MW of additional power in L-mode discharge. The heat load distribution is clearly asymmetric with a 3/4 and 1/4 distribution on the outer and inner strike point region respectively for the parallel heat flux. Pracoviště Ústav fyziky plazmatu Kontakt Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Rok sběru 2022 Elektronická adresa https://iopscience.iop.org/article/10.1088/1741-4326/ac1803
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