Prediction of Dryout Heat Flux Using Film Flow Model
スポンサーリンク
概要
- 論文の詳細を見る
- 2002-07-01
著者
-
NAITOH Masanori
Nuclear Power Engineering Corporation
-
Tomio Okawa
Department Of Mechanical Engineering Osaka University
-
Okawa Tomio
Department Of Mechanophysics Engineering Osaka University
-
Okawa Tomio
Osaka University
-
Naitoh Masanori
Advanced Simulation Systems Department Nuclear Power Engineering Corporation Fujita Kanko
-
Okawa Tomio
Osaka Univ.
-
Kataoka I
Department Of Mechanical Engineering Osaka University
-
Kataoka I
Department Of Mechanophysics Engineering Osaka University
-
KIM Saeyun
Osaka University
-
KATAOKA Isao
Osaka University
関連論文
- Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (II) : Evaluation of Corrosive Conditions in PWR Secondary Cooling System
- Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (I) : Major Targets and Development Strategies of the Evaluation Methods
- Numerical Implementation of Interfacial Drag Force for One-Dimensional, Two-Way Bubble Tracking Method
- An Experimental Study on the Mass Transfer Rate of Droplets in Annular Two-Phase Flow(International Conferences on Power and Energy)
- Effects of a Flow Obstacle on the Deposition Rate of Droplets in Annular Two-Phase Flow
- Prediction of Critical Heat Flux in Annular Flow Using a Film Flow Model
- 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
- Critical Heat Flux Prediction Method Based on Two-Phase Turbulence Model
- ICONE11-36187 APPLICABILITY OF TWO-FLUID MODEL AND ITS CONSTITUTIVE EQUATIONS TO GAS-LIQUID TWO-PHASE FLOW IN SUDDEN EXPANSION
- Prediction of Dryout Heat Flux Using Film Flow Model
- Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles,(I) Models and Verifications for Boiling Water Reactor Application
- Numerical Simulation of Single Bubbles Located in Turbulent Flow in Vertical Pipes Using Bubble Tracking Method
- Numerical Study of Particle Concentration Effect on Deposition Characteristics in Turbulent Pipe Flows
- Analysis on Pipe Rupture of Steam Condensation Line at Hamaoka-1, (II) Hydrogen Combustion and Pipe Deformation
- Analysis on Pipe Rupture of Steam Condensing Line at Hamaoka-1, (I) Accumulation of Non-condensable Gas in a Pipe
- Effects of Particle Relaxation Time and Continuous-Phase Reynolds Number on Particle Deposition in Vertical Turbulent Pipe Flows
- Severe Accident Analysis Code SAMPSON Improvement for IMPACT Project(Special Issue on International Conference on Power and Energy System)
- Analyses of the Radial Distributions of Average Velocity and Turbulent Velocity of the Liquid Phase in Bubbly Two-Phase Flow
- Prediction of Critical Heat Flux in Annular Flow Using a Film Flow Model