This title appears in the Scientific Report :
2021
Non-axisymmetricheatfluxdistributionscausedbymagnetictoroidal ripple on WEST
Non-axisymmetricheatfluxdistributionscausedbymagnetictoroidal ripple on WEST
Non-axisymmetric heat flux distributions caused by magnetic toroidalripple on WESTY. Gao1,2, E. Tsitrone3, N. Fedorczak3, R. Mitteau3, J. Morales3, M. H. Aumeunier3,Y. Corre3, M. Houry3, X. Courtois3, V. Moncada3, M. Jakubowski2,A. Dinklage2, S. Brezinsek1, and the West Team31Forschungszentrum Jülic...
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Personal Name(s): | Gao, Yichen (Corresponding author) |
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Tsitrone, E. / Fedorczak, N. / Mitteau, R. / Morales, J. / Aumeunier, M. H. / Corre, Y. / Houry, M. / Courtois, X. / Moncada, V. / Jakubowski, M. / Dinklage, A. / Brezinsek, S. / Team, ; the West | |
Contributing Institute: |
Plasmaphysik; IEK-4 |
Imprint: |
2021
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Conference: | 24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 2020), virtuell (virtuell), 2021-01-25 - 2021-01-29 |
Document Type: |
Abstract |
Research Program: |
Plasma-Wand-Wechselwirkung |
Publikationsportal JuSER |
Non-axisymmetric heat flux distributions caused by magnetic toroidalripple on WESTY. Gao1,2, E. Tsitrone3, N. Fedorczak3, R. Mitteau3, J. Morales3, M. H. Aumeunier3,Y. Corre3, M. Houry3, X. Courtois3, V. Moncada3, M. Jakubowski2,A. Dinklage2, S. Brezinsek1, and the West Team31Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik,Partner of the Trilateral Euregio Cluster (TEC), 52425 Jülich, Germany2Max-Planck-Institut für Plasmaphysik, Wendelsteinstraße 1, 17491 Greifswald, Germany3CEA, IRFM, F-13108 Saint-Paul-lez-Durance, FranceW-tungsten Environment in Steady-state Tokamak (WEST) was upgraded from Tore-Supra witha poloidal X-point divertor concept to demonstrate the power handling performances of theITER-like actively cooled mono-block tungsten divertor [1]. WEST is potentially capable forlong-pulse operation, due to the 18 superconducting toroidal field (TF) coils, as well as thecurrent drive and heating system dominated by the high frequency electromagnetic waves.Magnetic toroidal ripple is large on WEST because of the discrete TF coils and the closenessof the plasma to the coils, with a variation of∼±2 % at the outer mid-plane of the separa-trix. This gives rise to a toroidal modulation of grazing angleαof magnetic field lines to thedivertor surfaces with a field period of 18. The perpendicular heat flux to the surface is accord-ingly modulated byP⊥,surf=P‖sinα, whereP‖is the parallel heat flux along the field lines.Experimentally infra-red thermography systems [2] installed with wide-angle optics show cleartoroidal modulation of the power loads onto the divertor, with a typical variation of∼±50 %.This study utilizes diffusive field-line tracer [3] and mapping method [4] developed on Wen-delstein 7-X to support the understanding of divertor heat distributions on WEST. Preliminarysimulations have reproduced experimental observations, indicating that higher X-point height(dx) would narrow the magnetic flux expansion, increaseα, thus lead to smaller wetted area.The toroidal variation of the divertor thermal loads increases from∼±30 % at dx∼11 mmto infinity at dx∼4 mm, due to an increased toroidally shadowed range on the divertor withdecreased dx. Additional modelling with various diffusion coefficients will be performed.References[1] J. Bucalossiet al. Fusion Engineering and Design,89(7), 907 (2014).[2] X. Courtoiset al. Fusion Engineering and Design,136, 1499 (2018).[3] S. Bozhenkovet al. Fusion Engineering and Design,88(11), 2997 (2013).[4] Y. Gaoet al. Nuclear Fusion,59(6), 066007 (2019). |