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Oarai Research and Development Center, Japan Atomic Energy Agency | 論文
- Experimental Study on Thermal Stratification in a Reactor Vessel of Innovative Sodium-Cooled Fast Reactor —Mitigation Approach of Temperature Gradient across Stratification Interface—
- Experimental Study on Thermal Stratification in a Reactor Vessel of Innovative Sodium-Cooled Fast Reactor : Mitigation Approach of Temperature Gradient across Stratification Interface
- Research and Development of Minor Actinide-containing Fuel and Target in a Future Integrated Closed Cycle System
- Effects of Microstructural Evolution on Charpy Impact Properties of Modified Ferritic/Martensitic Steel after Neutron Irradiation
- Development of Irradiation Capsules in Liquid Metal Environment in Joyo and Their Application to Irradiation Creep Measurement of Vanadium Alloys
- Mechanical Behavior of Oxide Dispersion Strengthened Steels Irradiated in JOYO
- Effect of Heat Treatment on TEM Microstructures of Zirconium Carbide Coating Layer in Fuel Particle for Advanced High Temperature Gas Cooled Reactor
- Effects of Fast Reactor Irradiation Conditions on Tensile and Transient Burst Properties of Ferritic/Martensitic Steel Claddings
- Swelling Behaviors in a Fuel Assembly for the Wrapping Wire and Duct Made of Modified 316 Austenitic Stainless Steel
- Thermal Performance of Intermediate Heat Exchanger during High-Temperature Continuous Operation in HTTR
- Thermal Performance of Intermediate Heat Exchanger during High-Temperature Continuous Operation in HTTR
- Development of Fast Reactor Structural Integrity Monitoring Technology Using Optical Fiber Sensors