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
スポンサーリンク
概要
- 論文の詳細を見る
In the case of loss of residual heat removal systems under mid-loop operation during shutdown of a PWR plant, reflux cooling by a steam generator (SG) is expected, and steam generated in the reactor core and water condensed in the SG form a countercurrent flow in a hot leg. The flow is highly complicated because the hot leg consists of a horizontal pipe, an elbow, and an inclined pipe. In this study, a scale model of the PWR hot leg (1/15th of the actual plant size) is used to investigate flow patterns and characteristics of countercurrent flow limitation (CCFL). The following conclusions are obtained. (1) The effects of gas volumetric flux JG and water volumetric flux JG on flow pattern in the hot leg were made clear. Flow patterns in the elbow and inclined section are strongly affected by those in the horizontal section. (2) When the flow rate of the supplied water is constant, the value of JG at the onset of transition from stratified flow to wavy flow obtained by increasing JG is larger than that at the onset of transition from wavy flow to stratified flow obtained by decreasing JG. (3) CCFL characteristics obtained by increasing JG differ from those obtained by decreasing JG. CCFL data obtained by decreasing JG agree well with available data. (4) The boundary between wavy flow and stratified flow in the horizontal section obtained by decreasing JG agree well with the CCFL characteristics.
- 2010-02-01
著者
-
MINAMI Noritoshi
Institute of Nuclear Safety System, Inc.
-
MURASE Michio
Institute of Nuclear Safety System, Inc.
-
TOMIYAMA Akio
Graduate School of Engineering, Kobe University
-
NISHIWAKI Daisuke
Graduate School of Engineering, Kobe University
-
NARIAI Toshifumi
Graduate School of Engineering, Kobe University
-
Murase Michio
Institute Of Nuclear Safety System Inc.
-
Murase Michio
Institute Of Nuclear Safety System
-
Tomiyama Akio
Graduate School Of Engineering Kobe University
-
Minami Noritoshi
Institute Of Nuclear Safety System Inc.
-
Nariai Toshifumi
Graduate School Of Engineering Kobe University
-
Nishiwaki Daisuke
Graduate School Of Engineering Kobe 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
- Evaluation of Incipient Cavitation Erosion on Pipe Walls Downstream from an Orifice
- 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
- 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
- Analysis of Noncondensable Gas Recirculation Flow in Steam Generator U-Tubes during Reflux Condensation Using RELAP5
- 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
- Reflux Condensation Heat Transfer of Steam-Air Mixture under Turbulent Flow Conditions in a Vertical Tube
- Evaluation of Reflux Condensation Heat Transfer of Steam-Air Mixtures under Gas-Liquid Countercurrent Flow in a Vertical Tube
- Numerical Simulation of Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling
- Shapes and Rising Velocities of Single Bubbles rising through an Inner Subchannel
- H205 EVALUATION OF RELATIVE VELOCITY BETWEEN SINGLE BUBBLES AND LIQUID IN HORIZONTAL TURBULENT PIPE FLOW(Bubble behavior)
- 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
- Modeling and Validation of In-Vessel Debris Cooling during LWR Severe Accident
- 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
- Detection of Cavitation States with Microphone Placed Outside Pipe Components
- Influence of Local Flow Field on Flow Accelerated Corrosion Downstream from an Orifice
- Liquid Mixing in a Bubble Column
- Numerical Simulation of Water Temperature in a Spent Fuel Pit during the Shutdown of Its Cooling Systems
- Evaluation of Heat Loss and Water Temperature in a Spent Fuel Pit
- One-Region Model Predicting Water Temperature and Level in a Spent Fuel Pit during Loss of All AC Power Supplies
- Correlation between Flow Accelerated Corrosion and Wall Shear Stress Downstream from an Orifice
- Volume Tracking Simulation of Bubble Motion with Low Spatial Resolution
- Two-Phase Swirling Flow in a Gas-Liquid Separator