Recent Fusion Research in the National Institute for Fusion Science
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概要
- 論文の詳細を見る
The National Institute for Fusion Science (NIFS), which was established in 1989, promotes academic approaches toward the exploration of fusion science for steady-state helical reactor and realizes the establishment of a comprehensive understanding of toroidal plasmas as an inter-university research organization and a key center of worldwide fusion research. The Large Helical Device (LHD) Project, the Numerical Simulation Science Project, and the Fusion Engineering Project are organized for early realization of net current free fusion reactor, and their recent activities are described in this paper. The LHD has been producing high-performance plasmas comparable to those of large tokamaks, and several new findings with regard to plasma physics have been obtained. The numerical simulation science project contributes understanding and systemization of the physical mechanisms of plasma confinement in fusion plasmas and explores complexity science of a plasma for realization of the numerical test reactor. In the fusion engineering project, the design of the helical fusion reactor has progressed based on the development of superconducting coils, the blanket, fusion materials and tritium handling.
- 社団法人 プラズマ・核融合学会の論文
著者
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KOMORI Akio
National Insitute for Fusion Science
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YAMADA Hiroshi
National Insitute for Fusion Science
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SAGARA Akio
National Insitute for Fusion Science
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SAKAKIBARA Satoru
National Insitute for Fusion Science
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TAKEIRI Yasuhiko
National Insitute for Fusion Science
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HORIUCHI Ritoku
National Institute for fusion Science
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HORIUCHI Ritoku
National Institute for Fusion Science, Toki 509-5292, Japan
関連論文
- Abrupt Flushing of High-Density Core in Internal Diffusion Barrier Plasmas and its Suppression by Plasma Shape Control in LHD
- Stability and Confinement Studies of High-Performance NBI Plasmas in the Large Helical Device Toward a Steady-State Helical Fusion Reactor
- Conceptual Design of Magnets with CIC Conductors for LHD-type Reactors FFHR2m
- Development of Advanced Pellet Injector Systems for Plasma Fueling
- Increase of Central Ion Temperature after Carbon Pellet Injection in Ne-Seeded NBI Discharges of LHD
- 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
- Effect of Plasma Current on Magnetohydrodynamic Modes in Neutral Beam Heated Plasmas in Compact Helical System
- Experimental Observation of Magnetic Fluctuations in NBI Heated Plasmas in CHS
- Comparative Study on Effect of Boronization and Titanium Gettering in Compact Helical System Heliotron/Torsatron Device
- Effect of Rotational Transform and Magnetic Shear on Confinement of Stellarators
- Retention and Desorption of Hydrogen and Helium in Inner Wall Material Used for The Large Helical Device (LHD) : Simulation experiments using a glow discharge apparatus
- Extension of Improved Particle and Energy Confinement Regime in the Core of LHD Plasma
- Dynamic Simulation of Erosion and Redeposition Patterns and Impurity Depth Profile of an LHD Divertor Plate
- A Shift Down Test of Resonance Frequency for the Cascading Bifurcations to Chaos
- Retention and Desorption of Discharge Gases in Wall Materials Used for Large Helical Device
- Possibility of Profile Control using Compact Toroid Injection on Large Helical Device
- Impurity Deposition and Retention of Discharge Gas on Plasma Facing Wall in LHD
- Development of a Hierarchy-Integrated Simulation Code for Toroidal Helical Plasmas, TASK3D
- Steady-State Operation Scenario and the First Experimental Result on QUEST
- Impurity Retention Effect in the Edge Ergodic Layer of the Large Helical Device
- Helium Retention of 316L Stainless Steel Used for The First Wall of The Large Helical Device (LHD)
- DC Power System for Superconducting Coils of Fusion Plasma Test Facility LHD
- Conceptual Design and Development of an Indirect-cooled Superconducting Helical Coil in the FFHR
- Structurally-Unstable Electrostatic Potentials in Plasmas : Condensed Matter and Statistical Physics
- Physics of Heliotron J Confinement
- Effects of Rotating Magnetic Islands Driven by External Perturbation Fields in the TU-Heliac
- Axial Profile of Balmer-Alpha Emission near a Tungsten Target in the Compact PWI Simulator APSEDAS
- Dynamic Visualization of Stress Distribution of Metal Surface by Mechanoluminescence Image
- Photocell system driven by Mechanoluminescence
- Progress in Impurity-Related Physics Experiments in LHD
- Studies on AC Electroluminescence Device Made of BaTiO_3-CaTiO_3:Pr^ Diphase Ceramics
- Long Range Temperature Fluctuation 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
- Transport Dynamics and Multi-Scale Coupling of Turbulence in LHD
- Electron Heat Transport Analysis of Low-Collisionality Plasmas in the Neoclassical-Transport-Optimized Configuration of LHD
- Effect of Toroidal Current on Rotational Transform Profile by MHD Activity Measurement in Heliotron J
- Particle Transport and Fluctuation Characteristics around the Neoclassically Optimized Configuration in LHD
- Improvement of Ion Confinement in Core Electron-Root Confinement (CERC) Plasmas in Large Helical Device
- Configuration Effects on Local Transport in High-Beta LHD Plasmas
- Observation of Cross-Field Transport of Pellet Plasmoid in LHD
- Discriminating Acquisition of 15-MeV Protons from D-3He Fusion Reaction in LHD
- High-Temperature Superconducting Coil Option for the LHD-Type Fusion Energy Reactor FFHR
- Mechanoluminescence of Europium-Doped SrAMgSi2O7 ($\text{A}=\text{Ca}$, Sr, Ba)
- Bi-Coherence Analysis of Fluctuations with Long Distance Correlation in Toroidal Plasmas
- High-Density, Low Temperature Ignited Operations in FFHR
- Transport Study of LHD High-Beta Plasmas Based on Power Balance Analysis with TASK3D Code Module
- Simulation Analysis of the Design of a Vacuum Pumping System for the Closed Helical Divertor in the Large Helical Device
- Modeling of Drift Displacement of the Pellet Ablated Material for Outboard Side Injection in Large Helical Device
- A Robust Design Window for the Heliotron DEMO Reactors
- Observation of Electron-Temperature Fluctuations Triggered by Supersonic Gas Puffing in the LHD
- Feasibility of Reduced Tritium Circulation in the Heliotron Reactor by Enhancing Fusion Reactivity Using ICRF
- Photocell System Driven by Mechanoluminescence
- Hydrogen Retention Behavior in Boron Films Affected by Impurities Introduced by Hydrogen Plasma Exposure in the LHD
- Assessment of Plasma Performance in a Magnetic Configuration with Reduced Poloidal Coils for a Helical DEMO Reactor FFHR-d1
- Activation Analysis for LHD Experiments with Deuterium Gases
- Toroidal Distributions of Amounts of Retained Gases and Deposited Impurities during 13th Experimental Campaign in the LHD
- Density Regimes of Complete Detachment and Serpens Mode in LHD
- Characterization of Dust Particles Ranging in Size from 1 nm to 10 µm Collected in the LHD
- Investigation of Carbon Films on Material Probes in the Vicinity of Local Island Divertor in the Large Helical Device
- New Control Method of the Unstable Operating Point in the FFHR Helical Reactor
- 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
- Dependence of EC-Driven Current on the EC-Wave Beam Direction in LHD
- Observation of Minor Collapse of Current-Carrying Plasma in LHD
- Effects of Resonant Magnetic Fluctuations on Plasma Confinement in Current Carrying high-β Plasmas of LHD
- Onset of Resistive Interchange Mode in the Large Helical Device
- ECCD Experiment Using an Upgraded ECH System on LHD
- Observation of the Effect of Energetic Ions on Pellet Ablation in the Large Helical Device
- Spectroscopic Diagnostics for Spatial Density Distribution of Plasmoid by Pellet Injection in the Large Helical Device
- Split and Segmented-Type Helical Coils for the Heliotron Fusion Energy Reactor
- Analysis of Energy Spectra of Fast Ion in the Large Helical Device
- Flux Control of Carbon Nanoparticles Generated due to Interactions between Hydrogen Plasmas and Graphite Using DC-Biased Substrates
- Density Reconstruction Using a Multi-Channel Far-Infrared Laser Interferometer and Particle Transport Study of a Pellet-Injected Plasma on the LHD
- Plasma Diagnostics Required for a Heliotron-Type DEMO Reactor
- Measurement of the Joint Resistance of Large-Current YBCO Conductors
- Microstructure of Oxide Insulator Coating before and after Thermal Cycling Test
- Tritium Retention on Stainless Steel Surface Exposed to Plasmas in LHD
- Design Window Analysis for the Helical DEMO Reactor FFHR-d1
- 2-D PSD Diagnostic System for the Pellet Trajectory in LHD Plasmas
- Nitriding Treatment of Reduced Activation Ferritic Steel as Functional Layer for Liquid Breeder Blanket
- Experimental Results for Electron Bernstein Wave Heating in the Large Helical Device
- Fuel Particle Balance Study in FFHR DEMO Reactor
- Blob/Hole Generation in the Divertor Leg of the Large Helical Device
- Flux Control of Carbon Nanoparticles Generated due to Interactions between Hydrogen Plasmas and Graphite Using DC-Biased Substrates (Special Issue : Advanced Plasma Science and Its Applications for Nitrides and Nanomaterials)
- Study of a Closed Divertor Configuration for the Three-Dimensionally Complicated Magnetic Structure in the LHD Plasma Periphery
- Recent Fusion Research in the National Institute for Fusion Science
- Design and Optimization of Support Posts for Cryogenic Components in FFHR
- Alpha Particle Slowing-Down Characteristics and the Effect on MHD Instability Excitation at High-Density Operation Points in FFHRs
- Corrosion Characteristics of Hydrogen Permeation Materials in Molten Salt Flinak
- Ignition Analysis for D Plasma with Non-Maxwellian 3He Minority in Fusion Reactors
- Feasibility of HTS Magnet Option for Fusion Reactors
- Evaluation of Adhesion Strength of Er2O3 Coating Layer for an Advanced Breeding Blanket System Applied to Thermal Cycles using Nano-Scratch Method
- Microstructures and Deuterium-Retention Behavior of Tungsten Exposed to D+(He and/or Be) Mixture Plasmas
- Behaviors of Deuterium Retention and Microstructure Change of Tungsten Simultaneously Implanted with Carbon and/or Helium Ions