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

0443589 - ÚFP 2016 RIV AT eng J - Journal Article
Kocan, M. - Pitts, R.A. - Arnoux, G. - Balboa, I. - de Vries, P.C. - Dejarnac, Renaud - Furno, I. - Goldston, R.J. - Gribov, Y. - Horáček, Jan - Komm, Michael - Labit, B. - LaBombard, B. - Lasnier, C.J. - Mitteau, R. - Nespoli, F. - Pace, D. - Pánek, Radomír - Stangeby, P.C. - Terry, J.L. - Tsui, C. - Vondráček, Petr
Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping.
Nuclear Fusion. Roč. 55, č. 3 (2015), 033019-033019. ISSN 0029-5515. E-ISSN 1741-4326
R&D Projects: GA ČR(CZ) GAP205/12/2327; GA MŠMT(CZ) LM2011021
Institutional support: RVO:61389021
Keywords : plasma * tokamak * ITER * first wall panel
Subject RIV: BL - Plasma and Gas Discharge Physics
Impact factor: 4.040, year: 2015
http://iopscience.iop.org/0029-5515/55/3/033019/pdf/0029-5515_55_3_033019.pdf

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
Permanent Link: http://hdl.handle.net/11104/0246271