READY special report 1: Application of TRAB-3D to BWR and PWR transient calculations

Keyphrases

• Reactor 100%
• Reactor Dynamics 100%
• Cooling Circuit 100%
• Transient Calculation 100%
• Steam Line 100%
• Thermal-hydraulics 66%
• Heat Conduction 66%
• Circuit Model 66%
• Core Dynamics 66%
• Dynamic Code 66%
• Finland 33%
• Power Plant 33%
• Dynamic Model 33%
• Protection System 33%
• Three-dimensional (3D) 33%
• Steam 33%
• Control System 33%
• Safety Analysis 33%
• Reactor Physics 33%
• Accident Condition 33%
• Parameter Variation 33%
• Safety Research 33%
• Reactor Safety 33%
• Hydraulics 33%
• Simulation Code 33%
• Large Break LOCA 33%
• Diffusion Code 33%
• Main Steam Line Break 33%
• VVER-1000 Reactor 33%
• Code Development 33%
• Typical Application 33%
• Reactor Vessel 33%
• Coupling Method 33%
• Dome 33%
• Seventies 33%
• Conduction Heat Transfer 33%
• Accident Type 33%
• Broken Line 33%
• Small Break 33%
• Neutron Kinetics 33%
• Circuit Control 33%
• Fast Running 33%
• RELAP 33%
• Core Geometry 33%
• Circulatory System 33%
• Hexagonal Geometry 33%
• Similar Code 33%
• Channel Hydraulics 33%
• Neutronics Thermal-hydraulics Coupling 33%
• Running Simulation 33%
• Pump Trip 33%
• Small Break LOCA 33%
• Reactor Control System 33%
• Rectangular Lattice 33%
• Group Codes 33%
• Synthesis Model 33%
• OECD Benchmark 33%

INIS

• applications 100%
• pwr type reactors 100%
• bwr type reactors 100%
• dynamics 80%
• steam lines 80%
• accidents 60%
• thermal hydraulics 60%
• cooling 60%
• reactor kinetics 60%
• simulation 40%
• geometry 40%
• pumps 40%
• reactors 40%
• validation 40%
• loca 40%
• benchmarks 40%
• hydraulics 40%
• thermal conduction 40%
• comparative evaluations 20%
• control 20%
• finland 20%
• kinetics 20%
• fuels 20%
• coupling 20%
• one-dimensional calculations 20%
• transients 20%
• diffusion 20%
• variations 20%
• range 20%
• power plants 20%
• loading 20%
• steam 20%
• protection 20%
• heat transfer 20%
• synthesis 20%
• safety analysis 20%
• oecd 20%
• reactor physics 20%
• neutrons 20%
• leaks 20%
• reactor safety 20%
• reactor vessels 20%
• rbmk type reactors 20%
• atws 20%
• lattices (reactor) 20%
• reactor control systems 20%

Engineering

• Steam Piping Systems 100%
• Thermal Hydraulics 75%
• Core Model 75%
• Loss of Coolant Accidents 50%
• Circuit Model 50%
• Hydraulics 50%
• Control Systems 50%
• Reactor Dynamics 50%
• One Dimensional 25%
• Circulation System 25%
• Simulation Code 25%
• Related System 25%
• Reactor Vessel 25%
• Parameter Variation 25%
• Neutronics 25%
• Dynamic Models 25%
• Safety Analysis 25%
• Reactor Safety 25%
• Electric Power Plant 25%
• Safety Engineering 25%