Levitation Experiment Using a High-Temperature Superconductor Coil for a Plasma Confinement Device(Superconductors)
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概要
- 論文の詳細を見る
- 社団法人応用物理学会の論文
- 2001-10-01
著者
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三戸 利行
National Institute for Fusion Science
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柳 長門
National Institute for Fusion Science
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OGAWA Yuichi
High Temperature Plasma Center, the University of Tokyo
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MORIKAWA Junji
High Temperature Plama Center, the University of Tokyo
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MITO Toshiyuki
National Institute for Fusion Science
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YANAGI Nagato
National Institute for Fusion Science
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Yanagi N
National Inst. For Fusion Sci. Gifu Jpn
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OZAWA Daisaku
The School of Engineering, The University of Tokyo
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HAMAGUCHI Sinji
National Institute for Fusion Science
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Ozawa Daisaku
The School Of Engineering The University Of Tokyo
関連論文
- Improvement of Magnetohydrodynamic Stability and Beta Limit by Toroidal Plasma Current in Heliotron DR
- Effects of Light Impurities on Electron Temperature Measured by Soft X-Ray Filter Method
- Construction and Operation of an Internal Coil Device with a High Temperature Superconductor
- Extension of Improved Particle and Energy Confinement Regime in the Core of LHD Plasma
- Experiment on Deflection of High-Speed Plastic Pellets Using Curved Guide Tubes
- 大型ヘリカル装置用超伝導マグネット運転の現状 : 2001年秋
- Levitation Experiment Using a High-Temperature Superconductor Coil for a Plasma Confinement Device(Superconductors)
- Conceptual Design and Development of an Indirect-cooled Superconducting Helical Coil in the FFHR
- Quench Characteristics and Operational Stability of the TOPAZ Thin Superconducting Solenoid
- Performance of the TOPAZ Thin Superconducting Solenoid Wound with Internal Winding Method
- Plasma Production by Electron Cyclotron Heating on the Internal Coil Device Mini-RT
- Plasma Production by Electron Cyclotron Heating on the Internal Coil Device Mini-RT
- Advanced Target Design for the FIREX-I Project
- High-Temperature Superconducting Coil Option for the LHD-Type Fusion Energy Reactor FFHR
- Long-Term Monitoring of Hydraulic Characteristics of LHD Poloidal Coils
- A Robust Design Window for the Heliotron DEMO Reactors
- Feasibility of Reduced Tritium Circulation in the Heliotron Reactor by Enhancing Fusion Reactivity Using ICRF
- Hysteresis Loss in Poloidal Coils of the Large Helical Device
- Split and Segmented-Type Helical Coils for the Heliotron Fusion Energy Reactor
- Long-Lived Pure Electron Plasma in Ring Trap-1
- Measurement of the Joint Resistance of Large-Current YBCO Conductors
- Design Window Analysis for the Helical DEMO Reactor FFHR-d1
- Direct Measurement of a Mode-Converted Electron Bernstein Wave in the Internal Coil Device Mini-RT
- Ignition Analysis for D Plasma with Non-Maxwellian 3He Minority in Fusion Reactors
- Feasibility of HTS Magnet Option for Fusion Reactors
- Design, Fabrication, and Persistent Current Operation of the REBCO Floating Coil for the Plasma Experimental Device Mini-RT