Two-phase Flow Patterns in a Four by Four Rod Bundle
スポンサーリンク
概要
- 論文の詳細を見る
Air-water two-phase flow patterns in a four by four square lattice rod bundle consisting of an acrylic channel box of 68 mm in width and transparent rods of 12 mm in diameter were observed by utilizing a high speed video camera, FEP (fluorinated ethylene propylene) tubes for rods, and a fiberscope inserted in a rod. The FEP possesses the same refractive index as water, and thereby, whole flow patterns in the bundle and local flow patterns in subchannels were successfully visualized with little optical distortion. The ranges of gas and liquid volume fluxes, 〈JG〉 and 〈JL〉, in the present experiments were 0.1<〈JL〉<2.0 m/s and 0.06<〈JG〉<8.85 m/s, which covered typical two-phase flow patterns appearing in a fuel bundle of a boiling water nuclear reactor. As a result, the following conclusions were obtained: (1) the region of slug flow in the 〈JG〉–〈JL〉 flow pattern diagram is so narrow that it can be regarded as a boundary between bubbly and churn flows, (2) the boundary between bubbly and churn flows is close to the boundary between bubbly and slug flows of the Mishima and Ishii’s flow pattern transition model, and (3) the boundary between churn and annular flows is close to the Mishima and Ishii’s model.
- 社団法人 日本原子力学会の論文
- 2007-06-25
著者
-
TOMIYAMA Akio
Graduate School of Engineering, Kobe University
-
MISHIMA Kaichiro
Research Reactor Institute, Kyoto University
-
TOMIYAMA Akio
Faculty of Engineering, Kobe University
-
Akira Sou
神戸大学自然科学研究科
-
Mizutani Yoshitaka
Faculty Of Engineering Kobe University
-
Sou Akira
Faculty Of Engineering Kobe University
-
Sou Akira
Graduate School Of Kobe University
-
Kudo Yoshiro
Global Nuclear Fuel-japan Co. Ltd.
-
Kudo Yoshiro
Global Nuclear Fuel
-
Tomiyama Akio
Graduate School Of Engineering Kobe University
-
Tomiyama Akio
Faculty Of Engineering Kobe University
-
HOSOKAWA Shigeo
Faculty of Engineering, Kobe University
-
Hosokawa Shigeo
Faculty Of Engineering Kobe University
-
Mishima Kaichiro
Research Reactor Institute Kyoto University
関連論文
- Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling (II) : Numerical Simulation of 1/15-Scale Air-Water Tests
- Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling (I) : Air-Water Tests for 1/15-Scale Model of a PWR Hot Leg
- Effects of Nozzle Geometry on Cavitation in Nozzles of Pressure Atomizers
- Ligament Formation Induced by Cavitation in a Cylindrical Nozzle
- Dimensionless Index for Cavitation in Nozzles of Various Geometries
- A Numerical Method for Two-Phase Flow Based on a Phase-Field Model
- PIV Measurement of Pressure Distributions about Single Bubbles
- Simulation of Bubble Motion under Gravity by Lattice Boltzmann Method
- Influence of Scattered Neutrons on Void Fraction Measurement of Two-Phase Flow Using Thermal Neutron Radioscopy
- Numerical Simulation of Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling
- Void Fraction in a Four by Four Rod Bundle under a Stagnant Condition
- Effects of Swirler Shape on Two-Phase Swirling Flow in a Steam Separator
- Effect of Subchannel Void Fraction Distribution on Lattice Physics Parameters for Boiling Water Reactor Fuel Bundles
- Research Project on Accelerator-driven Subcritical System Using FFAG Accelerator and Kyoto University Critical Assembly
- Drag Coefficients of Single Bubbles under Normal and Micro Gravity Conditions
- Experimental Study on Transient Boiling Heat Transfer in an Annulus with a Narrow Gap
- ICONE11-36177 EXPERIMENTAL STUDY ON TRANSIENT BOILING HEAT TRANSFER IN AN ANNULUS WITH A NARROW GAP
- Interaction of Twe Bubbles in Train
- Heat Transfer Study for Thermal-Hydraulic Design of the Soild-Target of Spallation Neutron Source
- Numerical Simulation of Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling
- TED-AJ03-389 IMPROVED MEASUREMENT METHOD FOR INTERFACIAL AREA CONCENTRATION IN A LARGE DIAMETER TUBE
- Nondimensional Expression of Volumetric Fractions of Gas-Liquid-Solid Three-Phase Bubbly Flow in Vertical Pipes : Application of the Multiplier Method
- A302 NUMERICAL MODELING OF TWO-PHASE BUBBLY FLOWS IN A SUBCOOLED BOILING CHANNEL WITH A THREE-DIMENSIONAL PARTICLE-TRACKING METHOD(Subcooled boiling)
- Shapes and Rising Velocities of Single Bubbles rising through an Inner Subchannel
- Two-Phase Flow Model Based on Local Relative Velocity
- Orientation Effects on Critical Heat Flux due to Flooding in Thin Rectangular Channel
- H205 EVALUATION OF RELATIVE VELOCITY BETWEEN SINGLE BUBBLES AND LIQUID IN HORIZONTAL TURBULENT PIPE FLOW(Bubble behavior)
- Dryout in a Boiling Channel under Oscillatory Flow Condition
- Two-phase Flow Patterns in a Four by Four Rod Bundle
- Cavitation in a Two-Dimensional Nozzle and Liquid Jet Atomization : LDV Measurement of Liquid Velocity in a Nozzle
- Effects of cavitation in a nozzle on liquid jet atomization
- Surface Wettability Caused by Radiation Induced Surface Activation
- Effect of Surface Wettability Caused by Radiation Induced Surface Activation on Leidenfrost Condition
- ICONE11-36523 SURFACE WETTABILITY AND LEIDENFROST CONDITION ON OXIDIZED METALS CAUSED BY RADIATION INDUCED SURFACE ACTIVATION
- Post-Dryout Heat Transfer Analysis Model with Droplet Lagrangian Simulation(International Conferences on Power and Energy)
- Numerical Simulation of a Taylor Bubble in a Stagnant Liquid inside a Vertical Pipe
- Numerical Analysis of a Single Bubble by VOF Method
- Current Status of the Post Boiling Transition Research in Japan Integrity Evaluation of Nuclear Fuel Assemblies after Boiling Transition and Development of Rewettin Correlations
- Application of a Two Phase Flow Model Based on Local Relative Velocity to Gas-Liquid-Solid Three-Phase Flows
- An Improvement of the Computational Efficiency of the SOLA Method
- ICONE11-36062 A STUDY ON THE CHARACTERISTICS OF UPWARD AIR-WATER TWO-PHASE FLOW ALONG A LARGE PIPE
- E110 EVALUATION OF CRITICAL HEAT FLUX FOR LATERALLY HALF-HEATED TUBE USING RIVULET FORMATION MODEL(Critical heat flux)
- H208 A NON-EQUILIBRIUM MECHANISTIC MEAT TRANSFER MODEL FOR POST-DRYOUT DISPERSED FLOW REGION(BWR thermal hydraulics)
- Immersed Boundary-Finite Difference Lattice Boltzmann Method for Liquid-Solid Two-Phase Flows
- Effects of Liquid Properties on CCFL in a Scaled-Down Model of a PWR Hot Leg
- Correlation for countercurrent flow limitation in a PWR hot leg
- Liquid Mixing in a Bubble Column
- Application of Neutron Radiography to Visualization and Void Fraction Measurement of Air-Water Two-Phase Flow in a Small Diameter Tube.
- Volume Tracking Simulation of Bubble Motion with Low Spatial Resolution
- Two-Phase Swirling Flow in a Gas-Liquid Separator