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Nippon Nuclear Fuel Development Co., Ltd. | 論文
- Microstructure effects on fracture strength of UO2 fuel pellets.
- Melting temperature of irradiated UO2 and UO2-2wt%Gd2O3 fuel pellets up to burnup of about 30GWd/tU.
- 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
- Simple model for describing axial fission gas transport in fuel rod.
- Effect of iodine on fatigue properties of zircaloy-2 fuel cladding under cyclic tensile stress.
- Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2 Fuels.