スポンサーリンク
Advanced Nuclear System Research And Development Directorate Japan Atomic Energy Agency | 論文
- Investigation on Slit Jet through Upper Internal Structure (UIS) in Highly Compact Vessel of Sodium-Cooled Fast Reactor
- Improvement of Gas Entrainment Prediction Method : Introduction of Surface Tension Effect
- Formulations and Validations of a High-Precision Volume-of-Fluid Algorithm on Nonorthogonal Meshes for Numerical Simulations of Gas Entrainment Phenomena
- Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses
- Electrorefining Experiments to Recover Uranium with a Cadmium-Lithium Anode and Their Theoretical Evaluation
- Evaluation of Cadmium Pool Potential in a Electrorefiner with Ceramic Partition for Spent Metallic Fuel
- Experimental Study on Gas Entrainment at Free Surface in Reactor Vessel of a Compact Sodium-Cooled Fast Reactor
- Development of a New Thermochemical and Electrolytic Hybrid Hydrogen Production System for Sodium Cooled FBR(International Conferences on Power and Energy)
- Effect of Nano-Size Oxide Particle Dispersion and δ-Ferrite Proportion on Creep Strength of 9Cr-ODS Steel
- Removal of Liquid and Solid Impurities from Uranyl Nitrate Hexahydrate Crystalline Particles in Crystal Purification Process
- Separation of Trivalent Minor Actinides from Fission Products Using Single R-BTP Column Extraction Chromatography
- Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels
- Influence of Nitric Acid and Nitrous Acid on Oxidation and Extraction of Neptunium with Double Scrub Flow Sheet in Simplified Solvent Extraction Process
- JENDL-4.0 Benchmarking for Effective Delayed Neutron Fraction of Fast Neutron Systems
- Grain Boundary Deformation at High Temperature Tensile Tests in ODS Ferritic Steel
- Effects of Two-Step Cold Rolling on Recrystallization Behaviors in ODS Ferritic Steel
- Efficient fission neutron spectrum matrix representation by singular value decomposition technique
- Grain Boundary Related Deformation in ODS Ferritic Steel during Creep Test