Simulation-based level 2 multi-unit pra using raven and a simplified thermalhydraulic code

Keyphrases

• Thermal-hydraulics 100%
• Probabilistic Risk Assessment 100%
• Multi-unit 100%
• Raven 100%
• Simulation-based 100%
• Risk Metrics 66%
• Mechanistic Simulation 66%
• Risk Quantification 66%
• Static Model 66%
• Ensemble Model 66%
• Dynamic Model 33%
• Reactor Core 33%
• Thermal-hydraulic Code 33%
• Degradation Process 33%
• Boiling Water Reactor 33%
• Simulation Analysis 33%
• Reliability Analysis 33%
• Recovery Process 33%
• Risk Estimation 33%
• Statistical Analysis 33%
• Computational Framework 33%
• Risk Analysis 33%
• Dynamic Probabilistic Risk Assessment 33%
• Accident Scenario 33%
• Fault Tree 33%
• Accident Progression 33%
• Event Tree 33%
• Core Damage Frequency 33%
• Station Blackout Accident 33%
• Risk-informed Safety Margin Characterization 33%
• System Interaction 33%
• Multi-unit nuclear Power Plant 33%
• Loss of Offsite Power 33%
• Severe Accident Condition 33%
• Integrated Assessment 33%
• Model Risk 33%
• Large Early Release Frequency 33%
• Containment Event Tree 33%
• System Unit 33%
• Decay Heat Removal System 33%
• Level 2 Probabilistic Risk Assessment 33%
• Explosion Risk 33%
• Hydrogen Explosion 33%
• Markovian Model 33%
• Containment Performance 33%
• External Model 33%
• Plant Damage 33%
• Damage Status 33%

Engineering

• Metrics 100%
• Event Tree 100%
• Static Model 100%
• Dynamic Model 50%
• Thermal Hydraulics 50%
• Decay Heat 50%
• Nuclear Power Plant 50%
• Safety Margin 50%
• Reactor Core 50%
• Heat Removal 50%
• Degradation Process 50%
• Boiling Water Reactor 50%
• Recovery Process 50%
• Reliability Analysis 50%
• Severe Accident 50%
• Progression 50%
• Core Damage 50%
• Statistical Data 50%
• System Unit 50%
• Hydrogen Explosion 50%
• Explosion Risk 50%

Earth and Planetary Sciences

• Static Model 100%
• Dynamic Model 50%
• Reactor Core 50%
• Nuclear Power Plant 50%
• Fault Tree 50%
• Reliability Analysis 50%
• Boiling Water Reactor 50%
• Statistical Data 50%