High-Temperature Superconducting Coil Option for the LHD-Type Fusion Energy Reactor FFHR
スポンサーリンク
概要
- 論文の詳細を見る
Large-current-capacity high-temperature superconducting (HTS) conductors using YBCO tapes are being considered as an option for the LHD-type fusion energy reactor FFHR. The typical operating current, magnetic field, and temperature of such conductors in FFHR are 100 kA, 13 T, and 20 K, respectively. A preliminary design of the HTS conductor has been proposed for the FFHR helical coils. Analyses have been performed on the proposed HTS conductor regarding thermal properties, mechanical structures, AC losses, and quench detection and protection. It is suggested that stainless steel might be a better choice for the outer jacket of the HTS conductor compared to aluminum alloy. Due to increased specific heats of conductor materials at 20 K, HTS magnets are supposed to be operated more stably compared to low-temperature superconducting (LTS) magnets operated at ∼4 K. The required refrigeration power is also reduced. Therefore, using HTS conductors, it is considered to be viable to assemble the continuous helical coils in segments with joints of conductors, as additional heat generation at the joints can be taken care by utilizing the surplus refrigeration power. According to these analyses, HTS conductors seem to be promising for the FFHR coils.
著者
-
SAGARA Akio
National Insitute for Fusion Science
-
MITO Toshiyuki
National Institute for Fusion Science
-
YANAGI Nagato
National Institute for Fusion Science
-
TAKAHATA Kazuya
National Institute for Fusion Science
-
BANSAL Gourab
The Graduate University for Advanced Studies, Toki, Gifu 509-5292, Japan
-
HEMMI Tsutomu
Japan Atomic Energy Agency, 801-1, Mukoyama, Naka 311-0193, Japan
関連論文
- 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
- 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
- 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)
- 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
- Axial Profile of Balmer-Alpha Emission near a Tungsten Target in the Compact PWI Simulator APSEDAS
- 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
- 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
- Hysteresis Loss in Poloidal Coils of the Large Helical Device
- 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
- Design, Fabrication, and Persistent Current Operation of the REBCO Floating Coil for the Plasma Experimental Device Mini-RT
- Behaviors of Deuterium Retention and Microstructure Change of Tungsten Simultaneously Implanted with Carbon and/or Helium Ions