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Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping

SYSNO ASEP	0443589
Document Type	J - Journal Article
R&D Document Type	Journal Article
Subsidiary J	Článek ve WOS
Title	Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping
Author(s)	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, ORCID}
Source Title	Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515 Roč. 55, č. 3 (2015), 033019-033019
Number of pages	16 s.
Publication form	Print - P
Language	eng - English
Country	AT - Austria
Keywords	plasma ; tokamak ; ITER ; first wall panel
Subject RIV	BL - Plasma and Gas Discharge Physics
R&D Projects	GAP205/12/2327 GA ČR - Czech Science Foundation (CSF)
	LM2011021 GA MŠMT - Ministry of Education, Youth and Sports (MEYS)
Institutional support	UFP-V - RVO:61389021
UT WOS	000352020500023
EID SCOPUS	84924078702
DOI	10.1088/0029-5515/55/3/033019
Annotation	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
Workplace	Institute of Plasma Physics
Contact	Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975
Year of Publishing	2016

Number of the records: 1