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Nippon Nuclear Fuel Development Co., Ltd. | 論文
- Effects of Hydrogen/Water Vapor Atmospheres upon Vaporization of UO2-Based Complex Oxides with Sr, Ba, and Cs by Means of High Temperature Mass Spectrometry (高温質量分析特集号)
- Segregation Behavior Induced by Various Particle Irradiations in Austenitic Stainless Steels
- Effect of Gd_2O_3 Dispersion on the Thermal Conductivity of UO_2
- Equilibrium Evaporation Behavior of Polonium and Its Homologue Tellurium in Liquid Lead-Bismuth Eutectic
- Annealing Study on Neutron Irradiation Effects in Resonance Frequencies of Zircaloy Plates by EMAR Method
- Interpretation of Acoustic Parameters Obtained by EMAR Measurement for Non-destructive Hydrogen Concentration Measurement in Zr Alloy
- A New Non-destructive Technique for Hydrogen Level Assessment in Zirconium Alloys using EMAR Method
- Thermal Conductivity Measurements on UO_ from 300 to 1, 400 K
- Radial Die Wall Pressure during Ceramic Powder Compression and Unloading
- Thermal Conductivities of Granular UO_2 Compacts with/without Uranium Particles
- Tensile Strengths of Ceramic Powder Compacts
- Powder Characteristics Influencing Density Distribution in Green Pellet
- Fission Gas Release from Externally Restrained Uramium Dioxide Fuel
- Formation of Peller-Cladding Bonding Layer in High Burnup BWR Fuels
- Crystallography of Zirconium Hydrides in Recrystallized Zircaloy-2 Fuel Cladding by Electron Backscatter Diffraction
- Thermal Conductivity of UO_2-BeO Pellet
- Stress Reorientation of Hydrides in Recrystallized Zircaloy-2 Sheet
- Finite Element Model for Analysis of Fission Gas Release from UO2 Fuel
- Proton irradiation creep of zirconium.
- Radiolysis of N2-H2O systems.