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Nippon Nuclear Fuel Development Co. Ltd. | 論文
- Vibro-Packing Experiment of Non-Spherical Uranium Dioxide Particles with Spherical Metallic Uranium Particles
- Development of the Ultra-microhardness Technique for Post Irradiation Examination of Fuel Cladding Tubes
- Stress Reorientation of Hydrides in Recrystallized Zircaloy-2 Sheet
- Ab initio study of hydrogen diffusion in zirconium oxide
- Effects of Gadolinium Doping on Electrical Properties of UO2 Grain Boundaries.
- Measurements of friction coefficient and strain concetration of barriered fuel claddings under mechanical interaction with pellets.
- Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation. (I). Yield loci obtained from knoop hardness.:Yield Loci Obtained from Knoop Hardness
- Effects of Soluble Fission Products on Thermal Conductivities of Nuclear Fuel Pellets.
- Effect of oxygen content on tensile properties of low oxygen zircaloy-2.
- Stress corrosion cracking of zircaloy-2 by metal iodides.
- Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation. (II). Numerical simulations of yield loci.:Numerical Simulations of Yield Loci
- Thermal Expansion of UO2-Gd2O3 Fuel Pellets
- Effect of iodine on fatigue properties of zircaloy-2 fuel cladding under cyclic tensile stress.