Visualization of Magnetic Surfaces during Current Ramp-Up Phase Using Thermal Lithium Sheet Beam in CPD
スポンサーリンク
概要
- 論文の詳細を見る
Two dimensional electron density profile measurement has been performed in the spherical tokamak CPD (Compact PWI experimental Device) using Li sheet beam imaging technique. The topological change from the open magnetic field line configuration to the closed one is visualized by this technique. The plasma current can be driven by RF waves itself in a weak mirror configuration and a clear change is observed in plasma boundary as well as magnetic field topology associated with the transition of the current from low (∼1 kA) to high (∼3 kA) value.
著者
-
MORISAKI Tomohiro
National Insitute for Fusion Science
-
HASEGAWA Makoto
Research Institute for Applied Mechanics, Kyushu University
-
HANADA Kazuaki
Research Institute for Applied Mechanics, Kyushu University
-
ZUSHI Hideki
Research Institute for Applied Mechanics, Kyushu University
-
Idei Hiroshi
Research Institute For Applied Mechanics Kyushu University
-
YOSHINAGA Tomokazu
Research Institute for Applied Mechanics, Kyushu University, Kasuga, Fukuoka 816-8580, Japan
-
KIKUKAWA Tetsushi
Interdisciplinary Graduate School of Engineering Science, Kyushu University, Kasuga, Fukuoka 816-8580, Japan
-
BHATTACHARYAY Rajendraprasad
Interdisciplinary Graduate School of Engineering Science, Kyushu University, Kasuga, Fukuoka 816-8580, Japan
-
RYOUKAI Tomofumi
Interdisciplinary Graduate School of Engineering Science, Kyushu University, Kasuga, Fukuoka 816-8580, Japan
-
MORISAKI Tomohiro
National Institute for Fusion Science, Toki, Gifu, 509-8292, Japan
-
ZUSHI Hideki
Research Institute for Applied Mechanics, Kyushu University, Kasuga, Fukuoka 816-8580, Japan
関連論文
- Achievement of 10 keV Central Electron Temperatures by ECH in LHD
- Measurement of Edge Density Profiles and Fluctuations in the H-Mode Discharge of the Compact Helical System (CHS) with a Thermal Neutral Lithium Beam Probe
- Experimental Observation of Magnetic Fluctuations in NBI Heated Plasmas in CHS
- Model of Inductive Plasma Production Assisted by Radio-Frequency Wave in Tokamaks(Gases, plasmas, electric discharges, and beams)
- Local Impurity Deposition in a Magnetic Island by Means of a Tracer-Encapsulated Solid Pellet in the LHD
- Extension of Improved Particle and Energy Confinement Regime in the Core of LHD Plasma
- Steady-State Operation Scenario and the First Experimental Result on QUEST
- Impurity Retention Effect in the Edge Ergodic Layer of the Large Helical Device
- Reconstruction of Vacuum Magnetic Flux in QUEST
- Mode-Content Analysis and Field Reconstruction of Propagating Waves in Corrugated Waveguides of an ECH System
- Progress in Impurity-Related Physics Experiments in LHD
- Properties of Intermittent Bursts in Edge Plasma of LHD
- Investigation of the Clustering Condition for Various Gasses Ejected from a Fast Solenoid Valve for Supersonic Cluster Beam Injection
- Neutral Gas Compression in the Helical Divertor with a Baffle Structure in the LHD Heliotron
- First Ohmic Discharge Assisted with RF Power in QUEST Spherical Tokamak
- Plasma-Wall Interaction Study towards the Steady State Operation
- Development of a Bright Polychromator for Thomson Scattering Measurements
- A Plasma Shape Identification with Magnetic Analysis for the Real-time Control on QUEST
- A Plasma Shape Identification with Magnetic Analysis for the Real-time Control on QUEST
- Simulation Analysis of the Design of a Vacuum Pumping System for the Closed Helical Divertor in the Large Helical Device
- Observation of Electron-Temperature Fluctuations Triggered by Supersonic Gas Puffing in the LHD
- Two-Dimensional Measurement of Electron Density Profile in the Edge Region of the Large Helical Device Plasma by a Sheet-Shaped Thermal Lithium Beam
- Visualization of Magnetic Surfaces during Current Ramp-Up Phase Using Thermal Lithium Sheet Beam in CPD
- First Demonstration of Rotational Transform Control by Electron Cyclotron Current Drive in Large Helical Device
- Initial Plasma Production by Townsend Avalanche Breakdown on QUEST Tokamak
- Deuterium Retention in Plasma Sprayed Tungsten Exposed to Low Energy Deuterium Plasma
- Electron Temperature Measurement on QUEST Spherical Tokamak by Thomson Scattering System
- Assessment of Plasma Performance in a Magnetic Configuration with Reduced Poloidal Coils for a Helical DEMO Reactor FFHR-d1
- ECW/EBW Heating and Current Drive Experiment Results and Prospects for CW Operation in QUEST
- Deuterium Trapping in Rolled Polycrystalline Tungsten Exposed to Low Energy Plasma
- Density Regimes of Complete Detachment and Serpens Mode in LHD
- Pellet Injection and Internal Diffusion Barrier Formation in Large Helical Device
- Characteristics of Radiating Collapse at the Density Limit in the Large Helical Device
- Heat- and Particle-Deposition Distribution on Helical Divertor Plates in LHD During Real-Time Magnetic-Axis Swing Operations
- Scaling Laws of Intermittent Plasma Turbulence in Edge of Fusion Devices
- Effect of Ellipticity on Thermal Transport in ECH Plasmas in LHD
- Density Reconstruction Using a Multi-Channel Far-Infrared Laser Interferometer and Particle Transport Study of a Pellet-Injected Plasma on the LHD
- Experimental Results for Electron Bernstein Wave Heating in the Large Helical Device
- Blob/Hole Generation in the Divertor Leg of the Large Helical Device