Ohnuki Akira | Japan Atomic Energy Agency

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概要

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著作論文

Effect of Rod Bowing on Critical Power Based on Tight-Lattice 37-Rod Bundle Experiments
Gap Width Effect on Critical Power based on Tight-Lattice 37-Rod Bundle Experiments
Pressure Drop Experiments using Tight-Lattice 37-Rod Bundles
Critical Power Experiment with a Tight-Lattice 37-Rod Bundle
Critical Power Characteristics in 37-rod Tight Lattice Bundles under Transient Conditions
An Improved Critical Power Correlation for Tight-Lattice Rod Bundles
Critical Power Correlation for Tight-Lattice Rod Bundles
Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics
Applicability of REFLA/TRAC Code to a Small-Break LOCA of PWR
Core Liquid Level Responses Due to Secondary-Side Depressurization during PWR Small Break LOCA
ICONE11-36097 DEVELOPMENT OF MECHANISTIC BOILING TRANSITION MODEL IN ROD BUNDLES
Model Development for Bubble Turbulent Diffusion and Bubble Diameter in Large Vertical Pipes
Numerical Investigation of Heat Transfer Enhancement Phenomenon during the Reflood Phase of PWR-LOCA
Mechanism of Falling Water Limitation under Counter-current Flow through a Vertical Flow Path
Development of Design Technology on Thermal-hydraulic Performance in Tight-lattice Rod Bundles: V-Estimation of Void Fraction
Numerical Investigation of Cross Flow Phenomena in a Tight-Lattice Rod Bundle Using Advanced Interface Tracking Method
Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles: I-Master Plan and Executive Summary
Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles: II - Rod Bowing Effect on Boiling Transition under Transient Conditions
Applicability of Core Thermal-Hydraulic Models in REFLA Code to 17*17 Type Fuel Assembly of PWR.

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