Fuel Particle Balance Study in FFHR DEMO Reactor
スポンサーリンク
概要
- 論文の詳細を見る
Tritium particle balance in the FFHR DEMO reactor is investigated with consideration of the fueling efficiency by pellet injection system, retention loss in a vacuum vessel and permeation loss from the fuel processing system. In order to satisfy the fuel balance and the tritium safety management, it was necessary to suppress the tritium retention rate to be 10−5 and the DFs in the tritium cycle systems to above 107 with the tritium breeding ratio of 1.08. The processing throughput for the tritium processing system is estimated to be about 400 mol/h, which is almost same as the throughput of the fuel stream for the ITER. Therefore, the tritium processing system for vacuum exhaust gas for the DEMO will not be necessary to improve the system for the ITER further. On the other hands, the significant development of the tritium processing system for the effluent disposal and the waste materials from the safety aspect and the social acceptance will be required toward the DEMO reactor.
- 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 Masahiro
National Institute For Fusion Science
-
GOTO Takuya
National Institute for Fusion Science
-
KOZAKI Yasuji
National Institute for Fusion Science
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
- Application of Proton-conducting Ceramics and Polymer Permeable Membranes for Gaseous Tritium Recovery
- Hydrogen Extraction Characteristics of Proton-conducting Ceramics under a Wet Air Atmosphere for a Tritium Stack Monitor
- Effect of Plated Platinum Electrode on Hydrogen Extraction Performance Using CaZrO_3-based Proton-Conducting Ceramic for Tritium Recovery System
- Hydrogen Extraction Using One-end Closed Tube Made of CaZrO_3-based Proton-conducting Ceramic for Tritium Recovery System
- Design of Gaseous Tritium Recovery System Applying Commercially Available Membrane-Type Dehumidifier
- High-Temperature Superconducting Coil Option for the LHD-Type Fusion Energy Reactor FFHR
- Adsorption Characteristics of Water Vapor on Zeolitic Materials for Honeycomb-Type Adsorbent
- 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
- Interaction of Microwaves with Synthetic Type A Zeolite Containing Water
- 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
- Electromagnetic Fields Measurement and Safety Consideration in Magnetic Confinement Fusion Test Facilities
- 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
- Interaction of Microwaves with Synthetic Type A Zeolite Containing Water (Special Issue : Advanced Plasma Science and Its Applications for Nitrides and Nanomaterials)
- 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
- Comparative Study of Cost Models for Tokamak DEMO Fusion Reactors
- 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
- Optical Emission and Mass Spectra Observations during Hydrogen Combustion in Atmospheric Pressure Microwave Plasma
- 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