Počet záznamů: 1
Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping
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SYSNO ASEP 0443589 Druh ASEP J - Článek v odborném periodiku Zařazení RIV J - Článek v odborném periodiku Poddruh J Článek ve WOS Název Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping Tvůrce(i) Kocan, M. (FR)
Pitts, R.A. (FR)
Arnoux, G. (GB)
Balboa, I. (GB)
de Vries, P.C. (FR)
Dejarnac, Renaud (UFP-V) RID, ORCID
Furno, I. (CH)
Goldston, R.J. (US)
Gribov, Y. (FR)
Horáček, Jan (UFP-V) RID, ORCID
Komm, Michael (UFP-V) RID, ORCID
Labit, B. (CH)
LaBombard, B. (US)
Lasnier, C.J. (US)
Mitteau, R. (FR)
Nespoli, F. (CH)
Pace, D. (US)
Pánek, Radomír (UFP-V) RID
Stangeby, P.C. (CA)
Terry, J.L. (US)
Tsui, C. (CA)
Vondráček, Petr (UFP-V) RID, ORCIDZdroj.dok. Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
Roč. 55, č. 3 (2015), 033019-033019Poč.str. 16 s. Forma vydání Tištěná - P Jazyk dok. eng - angličtina Země vyd. AT - Rakousko Klíč. slova plasma ; tokamak ; ITER ; first wall panel Vědní obor RIV BL - Fyzika plazmatu a výboje v plynech CEP GAP205/12/2327 GA ČR - Grantová agentura ČR LM2011021 GA MŠMT - Ministerstvo školství, mládeže a tělovýchovy Institucionální podpora UFP-V - RVO:61389021 UT WOS 000352020500023 EID SCOPUS 84924078702 DOI 10.1088/0029-5515/55/3/033019 Anotace The inboard limiters for ITER were initially designed on the assumption that the parallel heat flux density in the scrape-off layer (SOL) could be approximated by a single exponential with decay length λq. This assumption was found not to be adequate in 2012, when infra-red (IR) thermography measurements on the inner column during JET limiter discharges clearly revealed the presence of a narrow heat flux channel adjacent to the last closed flux surface. This near-SOL decay occurs with λq ~ few mm, much shorter than the main SOL λq, and can raise the heat flux at the limiter apex a factor up to~4 above the value expected from a single, broader exponential. The original logarithmically shaped ITER inner wall first wall panels (FWPs) would be unsuited to handling the power loads produced by such a narrow feature. A multi-machine study involving the C-Mod, COMPASS, DIII-D and TCV tokamaks, employing inner wall IR measurements and/or inner wall reciprocating probes, was initiated Pracoviště Ústav fyziky plazmatu Kontakt Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Rok sběru 2016
Počet záznamů: 1