Multi-machine scaling of main SOL parallel heat flux width in tokamak limiter plasmas

0454403 - ÚFP 2016 RIV PT eng C - Conference Paper (international conference)
Horáček, Jan - Pitts, R.A. - Gunn, J. - Silva, C. - Rudakov, D. - Arnoux, G. - Marsen, S. - Vondráček, Petr - Maddaluno, G. - Pericoli, V. - Viola, B. - Xu, G.S. - Wang, H. - Nie, L. - LaBombard, B. - Brezinsek, S. - Xu, Y. - Shimada, M. - Adámek, Jiří - Popov, Tsv. - Dimitrova, Miglena - Seidl, Jakub - Janky, Filip - Pánek, Radomír - Goldston, R.J. - Stangeby, P.C.
Multi-machine scaling of main SOL parallel heat flux width in tokamak limiter plasmas.
EPS 2015:42nd European Physical Society Conference on Plasma Physics. Vol. 39E. Mulhouse: European Physical Society, 2015, O2.105-O2.105, č. článku O2.105. Europhysics Conference Abstracts, ECA, 39E. ISBN 2-914771-98-3.
[EPS 2015 Conference on Plasma Physics/42./. Lisbon (PT), 22.06.2015-26.06.2015]
R&D Projects: GA ČR(CZ) GAP205/12/2327; GA MŠMT(CZ) LM2011021
EU Projects: European Commission(XE) 633053
Institutional support: RVO:61389021
Keywords : tokamak * plasma * SOL * ITER
Subject RIV: BL - Plasma and Gas Discharge Physics
http://ocs.ciemat.es/EPS2015PAP/pdf/O2.105.pdf

Discharge on the ITER tokamak will preferably start and end up with plasma touching the inboard (HFS) limiter before shaping into the divertor configuration. In order to avoid exceeding the designed limit of the Beryllium enhanced heat flux limiters (4.7MW=m2), its shape has to be optimized in order to receive the power everywhere equally. The optimum shape has been derived based on observation that the SOL radial profile of the power flux decays mostly exponentially, qjj = q0jjexp(r=lomp q ).
Permanent Link: http://hdl.handle.net/11104/0255087