| Description |
1 online resource (xxi, 477 pages) : illustrations |
| Contents |
880-01 Front Matter -- Risk and Safety of Engineered Systems -- Probabilities of Events -- Reliability Data -- Reliability of Multiple-Component Systems -- Availability and Reliability of Systems with Repair -- Probabilistic Risk Assessment -- Computer Programs for Probabilistic Risk Assessment -- Nuclear Power Plant Safety Analysis -- Major Nuclear Power Plant Accidents and Incidents -- PRA Studies of Nuclear Power Plants -- Passive Safety and Advanced Nuclear Energy Systems -- Risk-Informed Regulations and Reliability-Centered Maintenance -- Dynamic Event Tree Analysis -- Appendix A: Reactor Radiological Sources -- Appendix B: Some Special Mathematical Functions -- Appendix C: Some Failure Rate Data -- Appendix D: Linear Kalman Filter Algorithm -- Answers to Selected Exercises -- Index |
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880-01/(S Machine generated contents note: 1. Risk and Safety of Engineered Systems -- 1.1. Risk and Its Perception and Acceptance -- 1.2. Overview of Risk and Safety Analysis -- 1.3. Two Historical Reactor Accidents -- 1.4. Definition of Risk -- 1.5. Reliability, Availability, Maintainability, and Safety -- 1.6. Organization of the Book -- References -- 2. Probabilities of Events -- 2.1. Events -- 2.2. Event Tree Analysis and Minimal Cut Sets -- 2.3. Probabilities -- 2.3.1. Interpretations of Probability -- 2.3.2. Axiomatic Approach to Probabilities -- 2.3.3. Intersection of Events -- 2.3.4. Union of Events -- 2.3.5. Decomposition Rule for Probabilities -- 2.4. Time-Independent Versus Time-Dependent Probabilities -- 2.5. Time-Independent Probabilities -- 2.5.1. Introduction -- 2.5.2. Time-Independent Probability Distributions -- 2.6. Normal Distribution -- 2.7. Reliability Functions -- 2.8. Time-Dependent Probability Distributions -- 2.8.1. Erlangian and Exponential Distributions -- 2.8.2. Gamma Distribution -- 2.8.3. Lognormal Distribution -- 2.8.4. Weibull Distribution -- 2.8.5. Generalized "Bathtub" Distribution -- 2.8.6. Selection of a Time-Dependent Probability Distribution -- 2.9. Extreme-Value Probability Distributions -- 2.10. Probability Models for Failure Analyses -- References -- Exercises -- 3. Reliability Data -- 3.1. Estimation Theory -- 3.1.1. Moment Estimators -- 3.1.2. Maximum Likelihood Estimators -- 3.1.3. Maximum Entropy Estimators -- 3.1.4. Comparison of Estimators -- 3.2. Bayesian Updating of Data -- 3.2.1. Bayes Equation -- 3.2.2. Applications of the Bayes Equation -- 3.3. Central Limit Theorem and Hypothesis Testing -- 3.3.1. Interpretation of the Central Limit Theorem -- 3.3.2. Hypothesis Testing with the Central Limit Theorem -- 3.4. Reliability Quantification -- 3.4.1. Central Limit Theorem for Reliability Quantification -- 3.4.2. Engineering Approach for Reliability Quantification -- 3.4.3. χ2-Distribution for Reliability Quantification -- 3.4.4. Three-Way Comparison and Concluding Remarks -- References -- Exercises -- 4. Reliability of Multiple-Component Systems -- 4.1. Series and Active-Parallel Systems -- 4.1.1. Systems with Independent Components -- 4.1.2. Systems with Redundant Components -- 4.1.3. Fail-to-Safety and Fail-to-Danger Systems -- 4.2. Systems with Standby Components -- 4.3. Decomposition Analysis -- 4.4. Signal Flow Graph Analysis -- 4.5. Cut Set Analysis -- References -- Exercises -- 5. Availability and Reliability of Systems with Repair -- 5.1. Introduction -- 5.2. Markov Method -- 5.2.1. Markov Governing Equations -- 5.2.2. Solution of Markov Governing Equations -- 5.2.3. Elementary Example -- 5.3. Availability Analyses -- 5.3.1. Rules for Constructing Transition Rate Matrices -- 5.3.2. Availability Transition Rate Matrices -- 5.3.3. Time-Dependent Availability Examples -- 5.3.4. Steady-State Availability -- 5.4. Reliability Analyses -- 5.4.1. Reliability Transition Rate Matrices -- 5.4.2. Time-Dependent Reliability Examples -- 5.4.3. Mean Time to Failure -- 5.5. Additional Capabilities of Markov Models -- 5.5.1. Imperfect Switching Between System States -- 5.5.2. Systems with Nonconstant Hazard Rates -- References -- Exercises -- 6. Probabilistic Risk Assessment -- 6.1. Failure Modes -- 6.2. Classification of Failure Events -- 6.2.1. Primary, Secondary, and Command Failures -- 6.2.2. Common Cause Failures -- 6.2.3. Human Errors -- 6.3. Failure Data -- 6.3.1. Hardware Failures -- 6.3.2. Human Errors -- 6.4. Combination of Failures and Consequences -- 6.4.1. Inductive Methods -- 6.4.2. Event Tree Analysis -- 6.5. Fault Tree Analysis -- 6.5.1. Introduction -- 6.5.2. Fault Tree Construction -- 6.5.3. Qualitative Fault Tree Analysis -- 6.5.4. Quantitative Fault Tree Analysis -- 6.5.5. Common Cause Failures and Fault Tree Analysis -- 6.6. Master Logic Diagram -- 6.7. Uncertainty and Importance Analysis -- 6.7.1. Types of Uncertainty in PRAs -- 6.7.2. Stochastic Uncertainty Analysis -- 6.7.3. Sensitivity and Importance Analysis -- References -- Exercises -- 7. Computer Programs for Probabilistic Risk Assessment -- 7.1. Fault Tree Methodology of the SAPHIRE Code -- 7.1.1. Gate Conversion and Tree Restructuring -- 7.1.2. Simplification of the Tree -- 7.1.3. Fault Tree Expansion and Reduction -- 7.2. Fault and Event Tree Evaluation with the SAPHIRE Code -- 7.3. Other Features of the SAPHIRE Code -- 7.4. Other PRA Codes -- 7.5. Binary Decision Diagram Algorithm -- 7.5.1. Basic Formulation of the BDD Algorithm -- 7.5.2. Generalization of the BDD Formulation -- 7.5.3. Zero-Suppressed BDD Algorithm and the FTREX Code -- References -- Exercises -- 8. Nuclear Power Plant Safety Analysis -- 8.1. Engineered Safety Features of Nuclear Power Plants -- 8.1.1. Pressurized Water Reactor -- 8.1.2. Boiling Water Reactor -- 8.2. Accident Classification and General Design Goals -- 8.2.1. Plant Operating States -- 8.2.2. Accident Classification in 10 CFR 50 -- 8.2.3. General Design Criteria and Safety Goals -- 8.3. Design Basis Accident: Large-Break LOCA -- 8.3.1. Typical Sequence of a Cold-Leg LBLOCA in PWR -- 8.3.2. ECCS Specifications -- 8.3.3. Code Scaling, Applicability, and Uncertainty Evaluation -- 8.4. Severe (Class 9) Accidents -- 8.5. Anticipated Transients Without Scram -- 8.5.1. History and Background of the ATWS Issue -- 8.5.2. Resolution of the ATWS Issues -- 8.5.3. Power Coefficients of Reactivity in LWRs -- 8.6. Radiological Source and Atmospheric Dispersion -- 8.6.1. Radiological Source Term -- 8.6.2. Atmospheric Dispersion of Radioactive Plume -- 8.6.3. Simple Models for Dose Rate Calculation -- 8.7. Biological Effects of Radiation Exposure -- References -- Exercises -- 9. Major Nuclear Power Plant Accidents and Incidents -- 9.1. Three Mile Island Unit 2 Accident -- 9.1.1. Sequence of the Accident---March 1979 -- 9.1.2. Implications and Follow-Up of the Accident -- 9.2. PWR In-Vessel Accident Progression -- 9.2.1. Core Uncovery and Heatup -- 9.2.2. Cladding Oxidation -- 9.2.3. Clad Melting and Fuel Liquefaction -- 9.2.4. Molten Core Slumping and Relocation -- 9.2.5. Vessel Breach -- 9.3. Chernobyl Accident -- 9.3.1. Cause and Nature of the Accident---April 1986 -- 9.3.2. Sequence of the Accident -- 9.3.3. Estimate of Energy Release in the Accident -- 9.3.4. Accident Consequences -- 9.3.5. Comparison of the TMI and Chernobyl Accidents -- 9.4. Fukushima Station Accident -- 9.4.1. Sequence of the Accident---March 2011 -- 9.4.2. March 2011 Perspectives on the Fukushima SBO Event -- 9.5. Salem Anticipated Transient Without Scram -- 9.5.1. Chronology and Cause of the Salem Incident -- 9.5.2. Implications and Follow-Up of the Salem ATWS Event -- 9.6. LaSalle Transient Event -- 9.6.1. LaSalle Nuclear-Coupled Density-Wave Oscillations -- 9.6.2. Simple Model for Nuclear-Coupled Density-Wave Oscillations -- 9.6.3. Implications and Follow-Up of the LaSalle Incident -- 9.7. Davis-Besse Potential LOCA Event -- 9.7.1. Background and Chronology of the Incident -- 9.7.2. NRC Decision to Grant DB Shutdown Delay -- 9.7.3. Causes for the Davis-Besse Incident and Follow-Up -- References -- Exercises -- 10. PRA Studies of Nuclear Power Plants -- 10.1. WASH-1400 Reactor Safety Study -- 10.2. Assessment of Severe Accident Risks: NUREG-1150 -- 10.2.1. Background and Scope of the NUREG-1150 Study -- 10.2.2. Overview of NUREG-1150 Methodology -- 10.2.3. Accident Frequency Analysis -- 10.2.4. Accident Progression Analysis -- 10.2.5. Radionuclide Transport Analysis -- 10.2.6. Offsite Consequence Analysis -- 10.2.7. Uncertainty Analysis -- 10.2.8. Risk Integration -- 10.2.9. Additional Perspectives and Comments on NUREG-1150 -- 10.3. Simplified PRA in the Structure of NUREG-1150 -- 10.3.1. Description of the Simplified PRA Model -- 10.3.2. Parametric Studies and Comments on the Simplified PRA Model -- References -- Exercises -- 11. Passive Safety and Advanced Nuclear Energy Systems -- 11.1. Passive Safety Demonstration Tests at EBR-II -- 11.1.1. EBR-II Primary System and Simplified Model -- 11.1.2. Unprotected Loss-of-Flow and Loss-of-Heat-Sink Tests -- 11.1.3. Simplified Fuel Channel Analysis -- 11.1.4. Implications of EBR-II Passive Safety Demonstration Tests -- 11.2. Safety Characteristics of Generation III+ Plants -- 11.2.1. AP1000 Design Features -- 11.2.2. Small-Break LOCA Analysis for AP1000 -- 11.2.3. Economic Simplified Boiling Water Reactor -- 11.2.4. Reliability Quantification of SBWR Passive Safety Containment -- 11.3. Generation IV Nuclear Power Plants -- 11.3.1. Sodium-Cooled Fast Reactor -- 11.3.2. Hypothetical Core Disruptive Accidents for Fast Reactors -- 11.3.3. VHTR and Phenomena Identification and Ranking Table -- References -- Exercises -- 12. Risk-Informed Regulations and Reliability-Centered Maintenance -- 12.1. Risk Measures for Nuclear Plant Regulations -- 12.1.1. Principles of Risk-Informed Regulations and Licensing -- 12.1.2. Uncertainties in Risk-Informed Decision Making -- 12.1.3. Other Initiatives in Risk-Informed Regulations -- 12.2. Reliability-Centered Maintenance -- 12.2.1. Optimization Strategy for Preventive Maintenance -- 12.2.2. Reliability-Centered Maintenance Framework -- 12.2.3. Cost-Benefit Considerations -- References -- Exercises -- 13. Dynamic Event Tree Analysis |
| Summary |
"The book has been developed in conjunction with NERS 462, a course offered every year to seniors and graduate students in the University of Michigan NERS program. The first half of the book covers the principles of risk analysis, the techniques used to develop and update a reliability data base, the reliability of multi-component systems, Markov methods used to analyze the unavailability of systems with repairs, fault trees and event trees used in probabilistic risk assessments (PRAs), and failure modes of systems. All of this material is general enough that it could be used in non-nuclear applications, although there is an emphasis placed on the analysis of nuclear systems. The second half of the book covers the safety analysis of nuclear energy systems, an analysis of major accidents and incidents that occurred in commercial nuclear plants, applications of PRA techniques to the safety analysis of nuclear power plants (focusing on a major PRA study for five nuclear power plants), practical PRA examples, and emerging techniques in the structure of dynamic event trees and fault trees that can provide a more realistic representation of complex sequences of events. The book concludes with a discussion on passive safety features of advanced nuclear energy systems under development and approaches taken for risk-informed regulations for nuclear plants"-- Provided by publisher |
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"The first half of the book covers the principles of risk analysis, the techniques used to develop and update a reliability data base, the reliability of multi-component systems, Markov methods used to analyze the unavailability of systems with repairs, fault trees and event trees used in probabilistic risk assessments (PRAs), and failure modes of systems. All of this material is general enough that it could be used in non-nuclear applications, although there is an emphasis placed on the analysis of nuclear systems. The second half of the book covers the safety analysis of nuclear energy systems, an analysis of major accidents and incidents that occurred in commercial nuclear plants, applications of PRA techniques to the safety analysis of nuclear power plants (focusing on a major PRA study for five nuclear power plants), practical PRA examples, and emerging techniques in the structure of dynamic event trees and fault trees that can provide a more realistic representation of complex sequences of events"-- Provided by publisher |
| Bibliography |
Includes bibliographical references and index |
| Notes |
Print version record |
| Subject |
Nuclear facilities -- Security measures
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Nuclear engineering -- Safety measures.
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Nuclear engineering -- Risk assessment
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TECHNOLOGY & ENGINEERING -- Chemical & Biochemical.
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Nuclear engineering -- Safety measures
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Nuclear facilities -- Security measures
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| Form |
Electronic book
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| Author |
McCormick, Norman J., author.
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| ISBN |
9781118043462 |
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1118043464 |
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9780470907566 |
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0470907568 |
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9781118043448 |
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1118043448 |
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1118043456 |
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9781118043455 |
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1283256142 |
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9781283256148 |
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