ICONE11-36097 DEVELOPMENT OF MECHANISTIC BOILING TRANSITION MODEL IN ROD BUNDLES
スポンサーリンク
概要
著者
-
Ohnuki A
Japan Atomic Energy Agency
-
Ohnuki Akira
Japan Atomic Energy Research Institute
-
Ohnuki Akira
Japan Atomic Energy Agency
-
Akimoto Hajime
Japan Atomic Energy Agency
-
Akimoto H
Japan Atomic Energy Res. Inst. Ibaraki
-
Akimoto Hajime
Frontier Research System For Global Change
-
KURETA Masatoshi
Japan Atomic Energy Agency
-
YOSHIDA Hiroyuki
Japan Tobacco Inc. Applied Plant Research Center
-
TAKASE Kazuyuki
Japan Atomic Energy Research Institute
-
Yamamoto Kazuhiko
Japan Atomic Power Company
-
Okada Hiroyuki
Tokyo Electric Power Company
-
Yoshida Hiroyuki
Japan Atomic Energy Agency Nuclear Science And Engineering Directorate
-
Yoshida Hiroyuki
Japan Atomic Energy Research Institute
-
Takase Kazuyuki
Japan Atomic Energy Agency Nuclear Science And Engineering Directorate
-
Yoshida Hiroyuki
Japan Atomic Energy Agency
関連論文
- 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
- Cloning and heterologous expression of cDNAs encoding flavonoid glucosyltransferases from Dianthus caryophyllus
- Assessment of Applicability of Two-Fluid Model Code ACE-3D to Heat Transfer Test of Supercritical Water Flowing in an Annular Channel
- 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
- Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics
- Modeling Mixing Aerosols of Soil Dust, Sea-Salt, Black-Carbon and Sulfate over East Asia
- Intercomparison of chemical mechanisms in the Models-3 Community Multi-scale Air Quality (CMAQ) modeling system
- A MODELING STUDY OF LONG-RANGE TRANSPORT OF YELLOW SAND IN SPRING 2000
- 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
- Numerical Analysis of a Water-Vapor Two-Phase Film Flow in a Narrow Coolant Channel with a Three-Dimensional Rectangular Rib(International Conferences on Power and Energy System)
- Pressure Drop Characteristics in Tight-Lattice Bundles for Reduced-Moderation Water Reactors(International Conferences on Power and Energy System)
- ICONE11-36232 NUMERICAL ANALYSIS OF A WATER-VAPOR TWO-PHASE FILM FLOW IN A NARROW COOLANT CHANNEL WITH A THREE-DIMENSIONAL RECTANGULAR RIB
- 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
- Excision of Transposable Elements from the Chalcone Isomerase and Dihydroflavonol 4-Reductase Genes May Contribute to the Variegation of the Yellow-Flowered Carnation (Dianthus caryophyllus)
- Isolation and Characterization of a cDNA for Phenylalanine Ammonia-Lyase (PAL) from Dianthus caryophyllus (carnation)
- 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
- Breeding of Red-flowering Delphiniums using Interspecific Hybrids Produced by in Vitro Germination
- 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
- Pressure Drop and Heat Transfer for Flow-Boiling of Water in Small-Diameter Tubes
- Mechanism of Falling Water Limitation under Counter-current Flow through a Vertical Flow Path
- Numerical Evaluation of Fluid Mixing Phenomena in Boiling Water Reactor Using Advanced Interface Tracking Method
- 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 -
- Numerical Analysis on Thermal-Hydraulics of Supercritical Water Flowing in a Tight-Lattice Fuel Bundle (Selected Papers of the Joint International Conference of Supercomputing in Nuclear Applications and Monte Carlo : SNA + MC 2010)
- Development of Design Technology on Thermal-hydraulic Performance in Tight-lattice Rod Bundles: V-Estimation of Void Fraction
- Steam Water Pressure Drop under 15 MPa
- 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 Analysis of Heat Transfer Test of Supercritical Water in a Tube Using the Three-Dimensional 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.
- Build-up and decay of actinide nuclides in fuel cycle of nuclear reactors.
- Elimination of Numerical Pressure Spikes Induced by Two-Fluid Model.
- Experimental study on behavior of horizontal bubbly flow under structure vibration
- Progress in Research on Laser Transmission Systems, Atmospheric Influence on Laser Transmission, and Laser Photovoltaics in Laser Space Solar Power System