SAGARA Akio | National Insitute for Fusion Science

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著作論文

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
Achievement of 10 keV Central Electron Temperatures by ECH in LHD
Comparative Study on Effect of Boronization and Titanium Gettering in Compact Helical System Heliotron/Torsatron Device
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
Impurity Deposition and Retention of Discharge Gas on Plasma Facing Wall in LHD
Helium Retention of 316L Stainless Steel Used for The First Wall of The Large Helical Device (LHD)
Conceptual Design and Development of an Indirect-cooled Superconducting Helical Coil in the FFHR
Axial Profile of Balmer-Alpha Emission near a Tungsten Target in the Compact PWI Simulator APSEDAS
High-Temperature Superconducting Coil Option for the LHD-Type Fusion Energy Reactor FFHR
High-Density, Low Temperature Ignited Operations in FFHR
A Robust Design Window for the Heliotron DEMO Reactors
Feasibility of Reduced Tritium Circulation in the Heliotron Reactor by Enhancing Fusion Reactivity Using ICRF
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
Toroidal Distributions of Amounts of Retained Gases and Deposited Impurities during 13th Experimental Campaign in the 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
Split and Segmented-Type Helical Coils for the Heliotron Fusion Energy Reactor
Flux Control of Carbon Nanoparticles Generated due to Interactions between Hydrogen Plasmas and Graphite Using DC-Biased Substrates
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
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
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)
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

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