Plasma Potential in Toroidal Devices: T-10, TJ-II, CHS and LHD
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概要
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Direct measurements of the electric potential φ, using the Heavy Ion Beam Probing, have been undertaken in the T-10 tokamak, and in the helical devices with various magnetic topology: TJ-II, CHS and LHD. L-mode plasmas were considered. Despite the large differences in machine sizes, heating methods and the topology of the magnetic field, the observed φ shows the striking similarities: (i) Similar magnitudes of Er; (ii) For low densities, ne <0.5×1019 m−3, φ is positive, and an increase in ne is associated with the decrease of positive φ and formation of a negative Er; (iii) For higher densities, ne >(0.5-1)×1019 m−3, both φ and Er tends to be negative despite the use of different heating methods: Ohmic and ECR heating in T-10, ECRH and/or NBI in TJ-II, CHS and LHD; (iv) Application of ECRH, causing a rise in Te, results in more positive values for φ and Er. The analysis show that the main features of the φ dependences on the ne and Te agree with neoclassical predictions on the four devices within experimental and simulation precisions.
- 社団法人 プラズマ・核融合学会の論文
著者
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IDO Takeshi
National Institute for Fusion Science
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Shimizu Akihiro
National Inst. For Fusion Sci. Toki 509-5292 Jpn
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Ido Takeshi
National Inst. For Fusion Sci. Toki 509-5292 Jpn
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Fujisawa Akihide
Research Institute For Applied Mechanics Kyushu University
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LYSENKO Sergey
Institute of Tokamak Physics, NRC "Kurchatov Institute", 123182, Moscow, Russia
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MELNIKOV Alexer
Institute of Tokamak Physics, NRC 'Kurchatov Institute
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HIDALGO Carlos
Association EURATOM-CIEMAT
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DYABILIN Konstantin
Institute of Tokamak Physics, NRC 'Kurchatov Institute
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MELNIKOV Alexer
Institute of Tokamak Physics, NRC 'Kurchatov Institute
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DYABILIN Konstantin
Institute of Tokamak Physics, NRC 'Kurchatov Institute
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