A Study of Particle Confinement Using Skin Radiative Approximation Method in JT-60 Tokamak
スポンサーリンク
概要
- 論文の詳細を見る
In order to analyse the particle behavior of hydrogen plasma based on the measurement data of Hα line radiation, 'skin radiative approximation method' has been used. The characteristics of particle confinement in the JT-60 tokamak are investigated by this model. This method will be applicable to large tokamak like JT-60, JET and TFTR.
- 社団法人応用物理学会の論文
- 1990-02-20
著者
-
NISHITANI Takeo
Japan Atomic Energy Agency
-
SHIMIZU Katsuhiro
Japan Atomic Energy Research Institute
-
Koide Shinji
Nuclear Institute For Fusion Science
-
Nishitani T
Japan Atomic Energy Research Institute
-
SUGIYAMA Takashi
Japan Atomic Energy Research Institute
-
SHIMIZU Katsuhiro
Japan Atomic Energy Agency
関連論文
- Neutron Spectrometer for DD/DT Burning Ratio Measurement in Fusion Experimental Reactor
- Point Defect Formation in V-4Cr-4Ti and F82H Irradiated with Fission and Fusion Neutrons
- Neutronics Experimental Study on Tritium Production in Solid Breeder Blanket Mockup with Neutron Reflector
- Measurement and Analysis of Neutron-Induced Alpha Particle Emission Double-Differential Cross Section of Carbon at 14.2MeV
- Electron Thermal Diffusivity in JFT-2 Tokamak with NBI Heating
- A Study of Particle Confinement Using Skin Radiative Approximation Method in JT-60 Tokamak
- Development of Supercritical Pressure Water Cooled Solid Breeder Blanket in JAERI
- Measurement of Charged-Particle Emission Double-Differential Cross Section of Fluorine for 14.2MeV Neutrons
- Neutron Shielding and Blanket Neutronics Study on Low Aspect Ratio Tokamak Reactor
- Spatial Structure of Volume Recombination in JT-60U Detached Divertor Plasmas
- Impact of Reflector on Calculation Accuracy of Tritium Production in DT Neutronics Blanket Experiment
- Integrated Modeling of Whole Tokamak Plasma
- Neutron Spectrometer for DD/DT Burning Ratio Measurement in Fusion Experimental Reactor
- Neutron Emission Profile Measurement and Fast Charge Exchange Neutral Particle Flux Measurement for Transport Analysis of Energetic Ions in JT-60U
- Development of Integrated SOL/Divertor Code and Simulation Study in JAEA