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

0454403 - ÚFP 2016 RIV PT eng C - Konferenční příspěvek (zahraniční konf.)
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]
Grant CEP: GA ČR(CZ) GAP205/12/2327; GA MŠMT(CZ) LM2011021
GRANT EU: European Commission(XE) 633053
Institucionální podpora: RVO:61389021
Klíčová slova: tokamak * plasma * SOL * ITER
Kód oboru RIV: BL - Fyzika plazmatu a výboje v plynech
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 ).
Trvalý link: http://hdl.handle.net/11104/0255087