Experimental Study on Transient Boiling Heat Transfer in an Annulus with a Narrow Gap
スポンサーリンク
概要
- 論文の詳細を見る
The importance of heat transfer in a narrow gap has been pointed out in relation to the in-vessel retention of molten core under a severe accident condition of a light water reactor. In this study, heat transfer experiment has been carried out using internally heated annuli with a narrow gap and closed bottom. Effects of gap clearances (1.0, 2.0, 4.0 mm) on the cooling process were examined. The inner wall initially heated up to 800°C was cooled down by water supplied to the upper plenum, the transient rod temperature being measured. From the temperature history, transient boiling curves were obtained, which were compared with predictions by existing heat transfer correlations for nucleate boiling critical heat flux (CHF) and film boiling. In narrow gap channels water penetration to the gap was restricted by counter-flowing vapor, which lead to a decrease of heat transfer coefficients.
- 社団法人 日本原子力学会の論文
- 2004-03-25
著者
-
MURASE Michio
Institute of Nuclear Safety System, Inc.
-
Murase M
Institute Of Nuclear Safety System
-
Murase Michio
Institute Of Nuclear Safety System Incorporated
-
MISHIMA Kaichiro
Research Reactor Institute, Kyoto University
-
NAGAE Takashi
Institute of Nuclear Safety System, Incorporated
-
Juarsa Mulya
Graduate School Of Energy Science Kyoto University
-
TANAKA Futoshi
Graduate School of Energy Science, Kyoto University
-
Murase Michio
Institute Of Nuclear Safety System
-
Nagae Takashi
Institute Of Nuclear Safety System Incorporated
-
Nagae Takashi
Institute Of Nuclear Safety System
-
Tanaka Futoshi
Graduate School Of Energy Science Kyoto 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
- Evaluation of Incipient Cavitation Erosion on Pipe Walls Downstream from an Orifice
- 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
- Analysis of Noncondensable Gas Recirculation Flow in Steam Generator U-Tubes during Reflux Condensation Using RELAP5
- Research Project on Accelerator-driven Subcritical System Using FFAG Accelerator and Kyoto University Critical Assembly
- 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
- 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
- Orientation Effects on Critical Heat Flux due to Flooding in Thin Rectangular Channel
- Dryout in a Boiling Channel under Oscillatory Flow Condition
- Two-phase Flow Patterns in a Four by Four Rod Bundle
- 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)
- Modeling and Validation of In-Vessel Debris Cooling during LWR Severe Accident
- 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)
- 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
- 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
- Application of Neutron Radiography to Visualization and Void Fraction Measurement of Air-Water Two-Phase Flow in a Small Diameter Tube.