FusionPapers
図版検索AI要約wiki日本の研究装置ジャーナルChatGPTAbout
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Modelling of the micrometric erosion pattern observed on the Tore Supra limiter tiles

N. Mellet, C. Martin, B. Pégourié, G. Giacometti, J.P. Gunn, G. Cartry, P. Languille, C. Pardanaud, S. Panayotis, G. Amiard2014年被引用 11Nuclear FusionIF 3出版社

Recently, the surface of carbon fibre composite tiles of the toroidal pump limiter of Tore Supra has been analysed by scanning electron and atomic force microscopies. In regions where fibres are perpendicular to the surface, a specific erosion pattern has been observed. It is constituted of a striation oriented with an angle oblique with respect to the magnetic field. The characteristic wavelength of this structure is micrometric, and similar to the fibre size. Modelling has been undertaken to reproduce this micrometric pattern. It is shown to originate from the carbon composite structure, for which it has been found by measurement using laboratory plasma that the erosion rate of the fibres is different from that of the surrounding matrix. Modelling emphasizes the effect of the impinging flux angle distributions of deuterium ions and carbon impurities that are preliminarily determined from computation of the magnetic sheath. In the case of deuterium the sheath is shown to have little effect on the particle trajectories for the simulation parameters considered here, although when impurities are included the sheath deflection is significant. Furthermore this study shows how the fibre organization in the composite influences the striation direction and points out the importance of the angular dependence of the sputtering yield.

wiki

LimiterTore Supra
この論文にはまだAI要約がありません。

関連論文

ERO modeling and sensitivity analysis of locally enhanced beryllium erosion by magnetically connected antennas

2018Nuclear Fusion

Impact of gyro-motion and sheath acceleration on the flux distribution on rough surfaces

2010Nuclear Fusion

Integrated modeling of RF-induced tungsten erosion at ICRH antenna structures in the WEST tokamak

2025Nuclear Fusion

Material migration studies with an ITER first wall panel proxy on EAST

2015Nuclear Fusion

New linear stability parameter to describe low-β electromagnetic microinstabilities driven by passing electrons in axisymmetric toroidal geometry

2023Plasma Physics and Controlled Fusion

Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D

2022Nuclear Fusion

The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters

2012Nuclear Fusion

Overview of new MAST physics in anticipation of first results from MAST Upgrade

2019Nuclear Fusion

Engineering estimates of impurity fluxes on the ITER port plugs

2016Nuclear Fusion

Formation of orientation-dependent surface morphologies on tungsten after low energy helium plasma exposure: multiscale characterization and new insights

2024Nuclear Fusion