MAAP-MELCOR crosswalk phase 1 study

Keyphrases

• Phase 1 Study 100%
• Estimation Method 100%
• Crosswalk 100%
• Reactor Scale 100%
• Analysis Program 60%
• Accident Analysis 60%
• In-vessel 60%
• Separation Effect 40%
• Limited Information 40%
• Three Mile Island Unit 2 40%
• Core Melt Progression 40%
• Light Water Reactor 20%
• Reactor Core 20%
• High Temperature 20%
• Damage Event 20%
• Probabilistic Risk Assessment 20%
• Response Spectrum Analysis 20%
• Computer Code 20%
• Hydrogen Generation 20%
• Separate Effect Test 20%
• Reactor Accident 20%
• Beyond Design Basis Accident 20%
• Code Prediction 20%
• Pressure Boundary 20%
• Accident Management 20%
• Accident Progression 20%
• Scale Model 20%
• Core Damage 20%
• Physical Processes 20%
• Scaling Behavior 20%
• Pressure Containment 20%
• Plant Response 20%
• Management Effectiveness 20%
• Main Steam Line 20%
• Debris Morphology 20%
• Model Difference 20%
• Core Debris 20%
• Degree Condition 20%
• Accident Management Measures 20%
• Progression Modeling 20%

Engineering

• Progression 100%
• Crosswalk 100%
• Metrics 33%
• Light Water Reactors 33%
• Reactor Core 33%
• Design Basis Accident 33%
• Critical Role 33%
• Core Damage 33%
• Hydrogen Generation 33%
• Scale Model 33%
• Steam Piping Systems 33%