An algorithm for risk-informed analysis of advanced nuclear reactors with a case study of pipe failure rate estimation

Keyphrases

• Risk Analysis 100%
• Advanced Reactors 100%
• Failure Rate Prediction 100%
• Pipe Failure Rate 100%
• Probabilistic Physics-of-failure 57%
• Methodological Framework 42%
• Reactor 28%
• Consensus Model 28%
• Operating Experience 28%
• Renewal Process 14%
• Explicit Model 14%
• Sensitivity Analysis 14%
• Maintenance Performance 14%
• Academic Literature 14%
• Data-driven Approach 14%
• Risky Decision Making 14%
• Nuclear Industry 14%
• Regulatory Agencies 14%
• Epistemic Uncertainty 14%
• Safety Assessment 14%
• Output Uncertainty 14%
• Physical Degradation 14%
• Degradation Performance 14%
• Probabilistic Validation 14%
• Probabilistic Risk 14%
• Water-cooled Reactors 14%
• Conventional Reactors 14%

Engineering

• Failure Rate 100%
• Advanced Nuclear Reactor 100%
• Applicability 50%
• Epistemic Uncertainty 50%
• Relevancy 50%
• Renewal Process 50%
• Safety Risk Assessment 50%
• Water Cooled Reactor 50%