OKUBO Tsutomu | Japan Atomic Energy Agency

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著作論文

FEMAXI-6 Code Verification with MOX Fuels Irradiated in Halden Reactor
Study on Characteristics of Void Reactivity Coefficients for High-Conversion-Type Core of FLWR for MA Recycling
ICONE11-36176 CONTAINMENT PRESSURE SUPPRESSION SYSTEM WITH FUNCTIONS OF WATER INJECTION AND NONCONDENSABLE GAS CONFINEMENT
Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics
Effect of Decontamination Factor on Core Neutronic Design of Light Water Reactors Using Recovered Uranium Reprocessed by Advanced Aqueous Method
Conceptual Design Study of 180MWt Small-Sized Reduced-Moderation Water Reactor Core
Correlation among FBR core characteristics for various fuel compositions
Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data.
Experimental study of ECC water injection rate effects on reflood phase of PWR-LOCA.
Experimental study of initial downcomer water accumulation velocity effects on reflood phase of PWR-LOCA.
Assessment of core thermo-hydrodynamic models of REFLA-1D code with CCTF data for reflood phase of PWR-LOCA.
Experimental study of system behavior during reflood phase of PWR-LOCA using CCTF.
Effect of loop seal on reflood phenomena in PWR.
CHF Experiments under Steady-State and Transient Conditions for Tight Lattice Core with Non-Uniform Axial Power Distribution.
Experimental Study on Difference in Reflood Core Heat Transfer among CCTF, FLECHT-SET and Predicted with FLECHT Correlation.
Visual study of flow behavior in upper plenum during simulated reflood phase of PWR-LOCA.

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