Determination of thermal-hydraulic loads on reactor internals in a DBA-situation

Keyphrases

• Accident Situation 100%
• Analysis Code 40%
• Code Element 20%
• Computational Fluid Dynamics 40%
• Computational Fluid Dynamics Analysis 20%
• Control Rod 20%
• Design Basis Accident 100%
• Downcomer 20%
• Dynamic Code 20%
• Dynamic Element 20%
• Finite Element Analysis 40%
• Fluid-structure Interaction 20%
• Hydraulic Load 100%
• Hydraulics Aspects 20%
• Interaction Coupling 20%
• Mechanical Aspects 20%
• Mechanical Load 20%
• Motivation to Study 20%
• Pipe Breaks 20%
• Pressure Boundary Condition 20%
• Reactor Internals 100%
• Regulatory Requirements 20%
• SBLOCA 20%
• System Code 20%
• Thermal-hydraulic Analysis 20%
• Thermal-hydraulic System Code 20%
• Thermal-hydraulics 100%
• Thermal-mechanical 40%
• Thermo-mechanical Analysis 20%

INIS

• accidents 33%
• boundary conditions 16%
• computational fluid dynamics 50%
• control rods 16%
• coupling 16%
• design-basis accidents 100%
• finite element method 33%
• fluid-structure interactions 16%
• large break loss-of-coolant accident 16%
• pipes 16%
• pwr type reactors 16%
• reactor internals 100%
• thermal hydraulics 100%
• tools 16%

Engineering

• Analysis Code 33%
• Boundary Condition 16%
• Computational Fluid Dynamics 50%
• Control Rod 16%
• Design Basis Accident 100%
• Downcomer 16%
• Finite Element Analysis 33%
• Fluid-Structure Interaction 16%
• Hydraulic System 16%
• Loss of Coolant Accidents 16%
• Mechanical Load 16%
• Regulatory Requirement 16%
• Thermal Hydraulics 100%