Applications and development of the PORFLO 3D code in nuclear power plant thermal hydraulics

Keyphrases

• Nuclear Power Plant 100%
• Thermal-hydraulics 100%
• Debris Bed 100%
• Horizontal Steam Generator 100%
• Core Debris 100%
• 3D Code 100%
• Main Application 100%
• Hydraulic Safety 50%
• Safety Analysis 50%
• Reactor Pressure Vessel 50%
• Heat Transfer 50%
• Two-phase Flow 50%
• Severe Accident Analysis 50%
• Two-phase Flow Model 50%
• Complex Geometry 50%
• Simulation Code 50%
• Pressure Loss 50%
• VVER-1000 Reactor 50%
• Code Development 50%
• Porous Core 50%
• Closure Model 50%
• Friction Transfer 50%
• CFD Software 50%
• Conservation Equations 50%
• Porous Media Approach 50%
• Interfacial Friction 50%
• Flow Conservation 50%

INIS

• simulation 100%
• applications 100%
• nuclear power plants 100%
• thermal hydraulics 100%
• comparative evaluations 50%
• modeling 50%
• reactors 50%
• porous materials 50%
• two-phase flow 50%
• steam generators 50%
• solutions 25%
• geometry 25%
• friction 25%
• experimental data 25%
• computer codes 25%
• equations 25%
• losses 25%
• closures 25%
• severe accidents 25%
• heat transfer 25%
• safety analysis 25%
• pressure vessels 25%
• wwer type reactors 25%
• dryout 25%

Engineering

• Simulation Result 100%
• Thermal Hydraulics 100%
• Nuclear Power Plant 100%
• Steam Generator 100%
• Main Application 100%
• Two-Phase Flow 100%
• Flow Simulation 50%
• Severe Accident 50%
• Simulation Code 50%
• Pressure Loss 50%
• Reactor Pressure Vessel 50%
• Computational Fluid Dynamics 50%
• Safety Analysis 50%
• Conservation Equation 50%
• Porosity 50%