スポンサーリンク
Japan Nuclear Cycle Dev. Inst. | 論文
- Synthesis and Sintering of AIN using Enriched Nitrogen
- Analysis of Minor Actinides in Mixed Oxide Fuel Irradiated in Fast Reactor, (I) Determination of Neptunium-237
- Effect of Fast Neutron Irradiation on the Properties of Boron Carbide Pellet
- Development of Oxide Dispersion Strengthened Steels for FBR Core Application, (II) Morphology Improvement by Martensite Transformation
- Improvement of Critical Heat Flux Correlation for Research Reactors using Plate-Type Fuel
- A Fast Prediction of Plant Behaviour in the Steam Generator Tube Rupture Accident at Mihama Unit 2 Using a Similar Case
- Visualization of Flow Fields and Numerical Calculation of Collection Efficiency in Low Pressure Impactor
- Uranium Isotope Exchange between Uranium Hexafluoride and Uranium Pentafluoride