Burn-off and Production of CO and CO2 in the Oxidation of Nuclear Reactor-Grade Graphites in a Flow System.
スポンサーリンク
概要
- 論文の詳細を見る
The oxidation behaviors of IG-110 and PGX graphites were experimentally investigated in the temperature range from 500 to 1, 500-C for the oxygen concentration of 10 and 30 wt% (1.37 and 5.09 mol%) and the reacting gas velocities of 6.63 and 19.9 m/s (estimated at 900-C). The graphite specimens were prepared to simulate the annular coolant channel in the core of the HTGR. It has been found that the upstream surface is more oxidized for both IG-110 and PGX graphites, and that the oxidized surface of PGX is rougher than that of IG-110. The oxidation of IG-110 starts at about 700-C and reaches the maximum above 800 to 900-C accompanied by the maximum production of CO<SUB>2</SUB> around 850-C and a monotonic increase in CO with increasing temperature. The oxidation behavior of PGX is similar to that for IG-110, except that the oxidation starts at lower temperature and produces more CO<SUB>2</SUB> over 750 to 950-C while the concentration of CO becomes lower in this temperature range. The present result for the product ratio of CO to CO<SUB>2</SUB> deviates from the linear line in the Arrhenius plot in the region where the production of CO<SUB>2</SUB> increases. However, it agrees best with the Rossberg correlation among the previous empirical correlations. New empirical correlations for the product ratio of CO to CO<SUB>2</SUB> have been obtained from the present data which exclude those in the region of CO<SUB>2</SUB> increase.
- 一般社団法人 日本原子力学会の論文
著者
-
Sekimoto Hiroshi
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
-
Sekimoto Hiroshi
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
-
Takahashi Minoru
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
-
Kotaka Masahiro
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
関連論文
- Breeding Capability and Void Reactivity Analysis of Heavy-Water-Cooled Thorium Reactor
- The Onset of Cavitation and the Acoustic Noise Characteristics of Sodium Flow in a Venturi
- Study on Corrosion Properties of Welded Ferritic-Martensitic Steels in Liquid Lead-Bismuth at 600°C
- ICONE11-36126 Examination of applicability of IK method in the negative reactivity measurements
- ICONE11-36061 APPLICATION OF CANDLE BURNUP TO BLOCK-TYPE HIGH TEMPERATURE GAS COOLED REACTOR
- A New Estimation Method for Nuclide Number Densities in Equilibrium Cycle
- Radioactive Waste Transmutation and Safety Potentials of the Lead Cooled Fast Reactor in the Equilibrium State
- Comparison of the Burnup Characteristics and Radiotoxicity Hazards of Rock-like Oxide Fuel with Different Types of Additives
- Application of Monte Carlo Method to Solve the Neutron Kinetics Equation for a Subcritical Assembly
- ICONE11-36375 STUDY ON CORROSION PHENOMENA OF STEELS IN PB-BI FLOW
- Density Wave Instability of Sodium Boiling Two-phase Flow in a Vertical Annulus at Low Pressure
- Corrosion of Steels in Lead-Bismuth Flow
- Measurement of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of ^Bi
- Feasible Region of Design Parameters for Water Cooled Thorium Breeder Reactor
- Metallurgical Analysis of a Tube Ruptured in the Lead Bismuth Corrosion Test Facility
- Effects of Fuel and Coolant Temperatures and Neutron Fluence on CANDLE Burnup Calculation
- Sensitivities of Some Characteristics of Nuclear Equilibrium State to One-Group Constants
- Transport Equivalent Diffusion Constants for Reflector Region in PWRs
- ICONE11-36045 Removal of Polonium Contamination by Lead-Bismuth Eutectic in Nuclear Systems
- Calculational Method of One-Group Nuclear Constants in Nuclear Equilibrium State
- Design Concept of Fast Spectrum Pulse Reactor with Packed Core of Coated Dilute Fuel Particles
- Exact Error Estimation for Solutions of Nuclide Chain Equations
- Characteristics of Several Equilibrium Fuel Cycles of PWR
- Design and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
- Broadband active sound control system for air-conditioning duct noise
- Feasibility and Performance of Magnetic Theromosyphon with Magnetic Fluid in Non-Gravity Field
- Study on High Speed Lithium Jet For Neutron Source of Boron Neutron Capture Therapy (BNCT)
- Experimental Study on Thermal Interaction of Ethanol Jets in High Temperature Fluorinert
- Density Wave Instability of Sodium Boiling Two-phase Flow in a Vertical Annulus at Low Pressure
- Fast neutron spectrum in lithium fluoride pile with D-T neutron source.
- Fundamental studies on the ion-exchange separation of boron isotopes.
- Numerical Analysis of Lead-Bismuth-Water Direct Contact Boiling Heat Transfer
- 1,2-Migration of fluorine atom in CH2FCF2 radical produced by the addition of a hydrogen atom to trifluoroethylene.
- New method to analyze equilibrium cycle of pebble-bed reactors.
- Scalar fast neutron spectra in graphite-reflected lithium fluoride pile with D-T neutron source.
- Burn-off and Production of CO and CO2 in the Oxidation of Nuclear Reactor-Grade Graphites in a Flow System.
- Fast neutron spectrum generated in graphite pile with D-T neutron source.