Sudo Yukio | Japan Atomic Energy Research Institute

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著作論文

Experimental Study of Falling Water Limitation under a Counter-Current Flow in a Vertical Rectangular Channel : 1st Report, Effect of Flow Channel Configuration and Introduction of CCFL Correlation
Heat Transfer Characteristics in Narrow Vertical Rectangular Channels Heated from Both Sides
Improvement of Critical Heat Flux Correlation for Research Reactors using Plate-Type Fuel
Mechanism of Falling Water Limitation under Counter-current Flow through a Vertical Flow Path
Experimental Study of Homogeneously Dispersed Two-phase Critical Flow
Core thermohydraulic design with 20% LEU fuel for upgraded research reactor JRR-3.
Experimental study of incipient nucleate boiling in narrow vertical rectangular channel simulating subchannel of upgraded JRR-3.
Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3.
Experimental study of differences in DNB heat flux between upflow and downflow in vertical rectangular channel.
Heat Transfer Calculation of Simulated Heater Rods throughout Reflood Phase in Postulated PWR-LOCA Experiments
Estimation of average void fraction in vertical two-phase flow channel under low liquid velocity.
Evaluation of Local Power Distribution with Fine-mesh Core Model for High Temperature Engineering Test Reactor (HTTR).
Effects of partial flow blockage on core heat transfer in forced-feed reflood tests.
Upper plenum dump during reflood in PWR loss-of-coolant accident.
Prediction of Dryout Heat Flux for Particle Bed Simulating Degraded Core in LWR Severe Core Damage Accidents
Combined forced and free convective heat transfer characteristics in narrow vertical rectangular channel heated from both sides.
Downcomer effective water head during reflood in postulated PWR LOCA.
Experimental study of differences in single-phase forced-convection heat transfer characteristics between upflow and downflow for narrow rectangular channel.
Experimental study of upper core quench in PWR reflood phase.
Parameter effects on downcomer penetration of ECC water in PWR-LOCA.
Analysis of saturated film boiling heat transfer in reflood phase of PWR-LOCA. Turbulent boundary layer model.:Turbulent Boundary Layer Model
Film boiling heat transfer during reflood phase in postulated PWR loss-of-coolant accident.

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