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THE JAPAN ATOMIC POWER COMPANY | 論文
- Development of Advanced Fuel Handling Machine for JSFR
- Corrosion Test of 304 Stainless Steel in Hydrazine and Methanol Solutions at 320 °C under Gamma-Irradiation and Gamma Radiolysis of Hydrazine and Methanol
- An Experimental Study on the Cooling Characteristics of Passive Containment Cooling Systems
- Effect of Higher-Harmonic Flux in Exponential Experiment for Subcriticality Measurement
- Intrusive Effect of Wire Mesh Tomography on Gas-liquid Flow Measurement
- ICONE11-36075 A STUDY OF BUBBLY FLOW CHARACTERISTICS IN A VERTICAL TUBE USING WIRE MESH TOMOGRAPHY
- Investigation of Criticality Effects of Deuterium and Beryllium in Package Containing Fissile Material
- Seismic Isolation Design for JSFR
- ICONE11-36595 IMPLEMENTATION OF CONDITION-BASED MAINTENANCE AT THE JAPAN ATOMIC POWER
- Preliminary Test Results for Post Irradiation Examination on the HTTR Fuel
- ICONE11-36273 CORE AND CORE-INTERNAL DESIGN FOR INTEGRATED MODULAR WATER REACTOR (IMR)
- ICONE11-36144 DOSE REDUCTION MEASURES AT TSURUGA UNITS 3 AND 4
- Analytical Model for Peak Temperature within a Sodium-Water Reaction Jet
- Establishment of Analytical Model for Peak Temperature Within a Sodium-Water Reaction Jet, (I) : Axial Temperature Profile Within an Inert Hot Gas Jet Injected into a Cold Liquid
- TED-AJ03-581 EXPERIMENTAL STUDY OF THERMAL-HYDRAULIC BEHAVIOR OF COOLANT OUT OF NEUTRON REFLECTOR FOR APWR DURING REFLOODING OF LARGE BREAK LOCA
- ICONE11-36033 EXPERIMENTAL STUDY OF THERMAL-HYDRAULIC BEHAVIOR OF COOLANT OUT OF NEUTRON REFLECTOR FOR APWR DURING REFLOODING OF LARGE BREAK LOCA
- New Interfacial Drag Force Model Including Effect of Bubble Wake, (II) Model Validation Using Experimental Data of Steam-Water Bubbly Flow in Large-Diameter Pipes
- Optimization of Dissolved Hydrogen Concentration for Control of Primary Coolant Radiolysis in Pressurized Water Reactors
- Numerical Analysis of Droplet Breakup Behavior using Particle Method
- Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor