Akimoto Hajime | 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
Critical Power in 7-Rod Tight Lattice Bundle(International Conferences on Power and Energy System)
ICONE11-36099 CRITICAL POWER CHARACTERISTICS OF TIGHT LATTICE BUNDLES
Applicability of REFLA/TRAC Code to a Small-Break LOCA of PWR
Pressure Drop Characteristics in Tight-Lattice Bundles for Reduced-Moderation Water Reactors(International Conferences on Power and Energy System)
ICONE11-36172 EVALUATION OF CRITICAL HEAT FLUX OF TIGHT LATTICE CORE WITH SUBCHANNEL ANALYSIS CODE NASCA
ICONE11-36098 PRESSURE DROP CHARACTERISTICS IN TIGHT-LATTICE ROD BUNDLES FOR REDUCED-MODERATION WATER REACTERS
PREDICTED THREE-DIMENSIONAL BUBBLY AND LIQUID FILM FLOW BEHAVIOR IN NARROW FUEL CHANNELS(Liquid Flow)
ICONE11-36097 DEVELOPMENT OF MECHANISTIC BOILING TRANSITION MODEL IN ROD BUNDLES
FLOW VISUALIZATION OF A WAKE STRUCTURE AROUND THIN PLATE BY USING DYNAMIC PIV SYSTEM(Measurement)
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
Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles: III - Numerical Evaluation of Fluid Mixing Phenomena using Advanced Interface-Tracking Method -
Development of Design Technology on Thermal-hydraulic Performance in Tight-lattice Rod Bundles: V-Estimation of Void Fraction
Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundle: IV Large Paralleled Simulation by the Advanced Two-fluid Model Code
Numerical Investigation of Cross Flow Phenomena in a Tight-Lattice Rod Bundle Using Advanced Interface Tracking Method
Downcomer effective water head during reflood in postulated PWR LOCA.
Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data.
Experimental study of system behavior during reflood phase of PWR-LOCA using CCTF.
Oscillatory flows induced by direct contact condensation of flowing steam with injectes water.
Core radial power profile effect on system and core cooling behavior during reflood phase of PWR-LOCA with CCTF data.
System pressure effect on system and core cooling behavior during reflood phase of PWR LOCA.
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
Assessment of core radial power profile effect model for REFLA code by using CCTF data.
Pressure drop through broken cold leg during reflood phase of loss-of-coolant accident of pressurized water reactor.
Applicability of Core Thermal-Hydraulic Models in REFLA Code to 17*17 Type Fuel Assembly of PWR.
Elimination of Numerical Pressure Spikes Induced by Two-Fluid Model.

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