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Nuclear Engineering Research Laboratory | 論文
- Visualization Study for Pseudo-Boiling in Supercritical Carbon Dioxide under Forced Convection in Rectangular Channel
- Physical and Chemical Aspects of Hydrogen Transport in Fusion Reactor Materials
- Development of method based on perturbation theory for estimating and correcting errors in numerical solution of transport equation.
- Concept and nuclear performance of power-producing fast fission blankets for fusion-fission hybrid reactors using equilibrium fissile fuel.