Jul 2 – 6, 2018
Žofín Palace
Europe/Prague timezone

P5.1030 L-mode heat flux scaling at tokamaks JET, EAST and COMPASS at vertical and horizontal divertors

Jul 6, 2018, 2:00 PM
2h
Mánes

Mánes

Speaker

Jan Horacek

Description

See the full Abstract at http://ocs.ciemat.es/EPS2018ABS/pdf/P5.1030.pdf L-mode heat flux scaling at tokamaks JET, EAST and COMPASS at vertical and horizontal divertors J. Horacek1 , J. Adamek1 , J. Seidl1 , P. Vondracek1,2 , M. Komm1 , K. Jirakova1 , R. Panek1 , Ch. Guillemaut3 , A. Jardin4,5 , G. Deng6,7,8 , X. Gao6,7 , L. Wang6,7,9 , R. Ding6 , G. Matthews10 , M.E.F.M. Mostafa11 , K.M. Camacho12 , MST1 Contributors and JET Contributors∗ 1 Institute of Plasma Physics of the CAS, Za Slovankou 3, Prague, 18000, Czech Republic 2 Faculty of Mathematics and Physics, Charles University, Prague, Czech Republic 3 Instituto de Plasmas e Fusao Nuclear, IST, Universidade Lisboa, Portugal 4 CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France 5 Institute of Nuclear Physics, Polish Academy of Sciences, PL-31-342, Krakow, Poland 6 Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China 7 University of Science and Technology of China, Hefei 230026, China 8 Lawrence Livermore National Laboratory, Livermore, CA 94550, USA 9 School of Physics and Optoelectronic Technology, Dalian University of Technology, China 10 Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, OX14 3DB, UK 11 University of Carlos III Madrid, Leganes, Spain 12 Universite de Lorraine, Nancy, France ∗ See the author list of X. Litaudon et al 2017 Nucl. Fusion 57 102001 Established scalings of divertor target power decay length are based on infra-red thermog- raphy (IR) which cannot access the JET vertical targets. This paper presents experiments in tokamaks JET, EAST and COMPASS, aiming at enlarging the span in scaling parameters and in case of JET for configurations with the strike points at ITER-relevant location - the vertical divertor targets. We analyzed hundreds of Langmuir+ball-pen probe divertor profiles, described omp principally by the plasma radial decay length 1 mm< λq <15 mm. The data set contains omp L-mode, 2.5< q95 <8, 1.7< ne [1019 m−3 ] <9 and plasma current 0.15< Ip [MA] <3. λq with errors below 50% are only taken into account; especially some of the JET inner target profiles are removed due to magnetic shadowing. Cross-checking with IR camera shows difference, however, within the error bars. Previously published scaling seems consistent with those new divertor probe data from JET, COMPASS and EAST at both bottom horizontal and outer verti- cal targets. This is probably because the edge plasma density is nearby the inner/outer divertor symmetry point. We look for a new scaling taking into account all these aspects.

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