Reflux Condensation Heat Transfer of Steam-Air Mixture under Turbulent Flow Conditions in a Vertical Tube
スポンサーリンク
概要
- 論文の詳細を見る
Under certain hypothetical accident circumstances in a pressurized water reactor, reflux condensation in the steam generator U-tubes may be an effective heat removal mechanism. Non-condensable gas (air) may be present in the reactor coolant system and is well known to inhibit steam from condensing. In a previous study, local condensation heat transfer coefficients for reflux condensation with air were measured, and an empirical correlation intended for a laminar flow of steam-air mixtures was developed, which was a function of the partial pressure ratio, (Psteam⁄Pair). In this study, heat transfer coefficients measured under turbulent flows were used to modify the empirical correlation for improved prediction accuracy. The modified empirical correlation considers convection and is proportional to (Psteam⁄Pair)0.75Reg0.8 where Reg is the steam-air mixture Reynolds number. The correlation was verified against the data of Moon et al. and then incorporated into the transient analysis code RELAP5/SCDAPSIM/MOD3.2. The temperature distributions of the steam-air mixture calculated by the code for six reflux condensation tests are shown to agree well with the measured results.
- 社団法人 日本原子力学会の論文
- 2007-02-25
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
-
NAGAE Takashi
Institute of Nuclear Safety System, Incorporated
-
CHIKUSA Toshiaki
Institute of Nuclear Safety System, Incorporated
-
Vierow K
Advanced Simulation Systems Department Nuclear Power Engineering Corporation
-
Vierow Karen
Purdue University
-
Vierow Karen
Nuclear Power Engineering Corporation
-
Murase Michio
Institute Of Nuclear Safety System
-
WU Tiejun
Purdue University
-
Nagae Takashi
Institute Of Nuclear Safety System Incorporated
-
Nagae Takashi
Institute Of Nuclear Safety System
-
Chikusa Toshiaki
Institute Of Nuclear Safety System Incorporated
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
- 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
- Deterministic Trigger Model for the VESUVIUS Steam Explosion Code
- 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
- Development of the VESUVIUS Code for Steam Explosion Analysis : Part 2 : Verification of Jet Breakup Modeling
- Development of the VESUVIUS Code for Steam Explosion Analysis : Part 1 : Molten Jet Breakup Modeling
- 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
- Modeling and Validation of In-Vessel Debris Cooling during LWR Severe Accident
- 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