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Department Of Nuclear Engineering Kyoto University | 論文
- Carbonate Complexation of Np(VI) in Near-Neutral Solutions.
- Pool-boiling heat transfer in liquid nitrogen.
- Electrical Characteristics of MHD Generator with Resistive Segmented Electrodes in Thermal Equilibrium
- Behaviors of americium in aqueous solutions containing iron.
- Neutron nuclear data evaluation for thorium-232.
- On the Burn-Up Characteristics of Large Pu-U Fast Reactors
- The Comparative Study of the Sodium Loss Reactivity Effect of Large Pu-U and Pu-Th Fast Reactors
- Energy multiplication and fissile production of D-D fusion-fission hybrid reactors.
- Nuclear characteristics of D-D fusion reactor blanket. II. Thermal blanket and blanket-shield designs.:Thermal Blanket and Blanket-Shield Designs
- Control of thermal instability of pure and catalyzed D-D fusion reactor plasmas.
- Nuclear characteristics of gas-suspended boron carbide cooling catalyzed D fusion reactor blanket.
- Boiling detection by acoustic analysis applying linear discriminant function.
- Effects of neutron source ratio on nuclear characteristics of D-D fusion reactor blankets and shields.
- Effect of gas introduction on temperature distribution for tube flow with internal heat sources.
- Heat transfer in downstream of blockage with discrete permeability in rectangular channel.
- Heat Transfer in Turbulent Flow with Internal Heat Generation in Concentric Annulus, (II):Thermal Entrance Region
- Systematic analysis of fission cross sections of actinides by means of double-humped barrier model.
- Turbulent Heat Transfer by Downward Flow of Liquid Bismuth in a Concentric Annulus
- Heat Transfer by Slug Flow in Annulus
- Heat Transfer in Laminar Flow with Internal Heat Generation in Concentric Annulus