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Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping
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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, ORCIDSource Title Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
Roč. 55, č. 3 (2015), 033019-033019Number 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