Nitriding Treatment of Reduced Activation Ferritic Steel as Functional Layer for Liquid Breeder Blanket
スポンサーリンク
概要
- 論文の詳細を見る
The development of functional layers such as a tritium permeation barrier and an anti-corrosion layer is the essential technology for the development of a molten salt type self cooled fusion blanket. In the present study, the characteristics of a nitriding treatment on a reduced activation ferritic steel, JLF-1 (Fe-9Cr-2W-0.1C) as the functional layer were investigated. The steel surface was nitrided by an ion nitriding treatment or a radical nitriding treatment. The nitridation characteristic of the steel surface was made clear based on the thermodynamic stability. The thermal diffusivity, the hydrogen permeability and the chemical stability in the molten salt Flinak were investigated. The results indicated that the nitriding treatment can improve the compatibility in the Flinak without the decrease of the thermal diffusivity, though there was little improvement as the hydrogen permeation barrier.
- 社団法人 プラズマ・核融合学会の論文
著者
-
SAGARA Akio
National Insitute for Fusion Science
-
TANAKA Teruya
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan
-
TANAKA Teruya
National Institute for Fusion Science
-
KONDO Masatoshi
Tokai university, 4-1-1 Kitakaname, Hiratuka 259-1292, Japan
-
WATANABE Takashi
The graduate university for advanced studies, 322-6 Oroshi-cho, Toki 509-5292, Japan
-
ZHANG Dongxun
The graduate university for advanced studies, 322-6 Oroshi-cho, Toki 509-5292, Japan
-
KONDO Masatoshi
Tokai University
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
- 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
- Neutronics and Activation Analyses for Li/V-alloy and Flibe/V-alloy Blankets of FFHR2 with and without Beryllium
- 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
- Development of a Simple and Tough Alpha-Particle Detector Used at High Temperature
- 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