Methods And Nuclear Power Applications
Norman J. McCormick
Department of Nuclear Engineering
University of Washington
Seattle, Washington
Contents
Preface | xi |
CHAPTER 1
Introduction | 1 | |
1-1 | Why Study Risk Analysis? | 1 |
1-2 | An Overview of Risk Analysis | 2 |
General References | 6 |
PART 1
METHODS
CHAPTER 2
Probability Concepts | 11 | |
2-1 | Interpretations and Laws of Probability | 11 |
2-2 | The Bayes Equation | 16 |
2-3 | Probability Distribution Functions | 20 |
2-4 | Probability Concepts for Failure Analyses | 21 |
Exercises | 28 | |
References | 29 |
CHAPTER 3
Probability Distributions for Describing Failures | 30 | |
3-1 | Discrete Distributions | 30 |
3-2 | Continuous Distributions | 34 |
3-3 | Synthesized Distributions | 46 |
3-4 | Extreme-Value Distributions | 50 |
Exercises | 54 | |
References | 57 |
CHAPTER 4
Data Manipulation Concepts | 58 | |
4-1 | Curve Fitting of Data | 58 |
4-2 | Introduction to Estimation Theory | 65 |
4-3 | Point Estimates for Continuous Dostributions | 68 |
Exercises | 76 | |
References | 77 |
CHAPTER 5
Failure Data | 79 | |
5-1 | Introduction | 79 |
5-2 | Sources of Failure Data | 80 |
5-3 | Examples of Failure Data for Hardware | 84 |
5-4 | Examples of Failure Data for Human Error | 85 |
5-5 | Common Cause and Common Mode Failures | 88 |
References | 90 |
CHAPTER 6
Reliability of Simple Systems | 91 | |
6-1 | System Reliability for Series and Active-Parallel Units | 91 |
6-2 | System Reliability for Sequentially Operating Units | 96 |
6-3 | System Reliability as Derived by the Decomposition Method | 98 |
6-4 | Reliability Obtained Using a Signal Flow Graph | 103 |
6-5 | Cut-Set Method for Determining Reliability | 105 |
6-6 | Systems with Common Cause Failures | 110 |
Exercises | 111 | |
References | 116 |
CHAPTER 7
Reliability and Availability of Systems with Repair | 117 | |
7-1 | Reliability, Availability, and Maintainability | 117 |
7-2 | Periodic Maintenance | 118 |
7-3 | Introduction to Markov Models | 120 |
7-4 | Markov Models for Systems | 127 |
7-5 | Time-Dependent Availablity and Reliability | 136 |
7-6 | Time-Dependent Unavailabity for Rare Failures | 142 |
7-7 | Steady-State Availability | 144 |
7-8 | Mean Time to Failure | 145 |
7-9 | Models for Common Cause Failures | 147 |
7-10 | Other Analysis Techniques | 149 |
Exercises | 150 | |
References | 152 |
CHAPTER 8
Fault Tree Analysis | 154 | |
8-1 | Introduction | 154 |
8-2 | Fault Tree Construction | 157 |
8-3 | Fault Tree Evaluation | 162 |
8-4 | Examples of Simple Fault Trees | 166 |
8-5 | Light Water Reactor Trip System Fault Trees | 175 |
8-6 | Light Water Reactor Safety Fault Trees | 179 |
8-7 | Spent Nuclear Fuel Truck Transport Fault Trees | 184 |
8-8 | Geologic Waste Disposal Fault Trees | 184 |
Exercises | 185 | |
References | 189 |
CHAPTER 9
Event Tree Analysis | 190 | |
9-1 | Event Tree Construction | 190 |
9-2 | Event Trees for Reactor Safety Analysis | 193 |
9-3 | Event Trees for Safeguards Analysis | 207 |
Exercises | 211 | |
References | 213 |
CHAPTER 10
Computer Programs for Fault Tree Analysis | 214 | |
10-1 | Qualitative and Quantitative Evaluations | 214 |
10-2 | Fault Tree Analysis with Common Cause Failures | 221 |
10-3 | Analysis of Data Uncertainties in a Fault Tree | 223 |
10-4 | Automated Fault Tree Construction | 226 |
References | 227 |
PART II
NUCLEAR POWER RISKS
CHAPTER 11
Risks Concepts | 231 | |
11-1 | Definition of Risk | 231 |
11-2 | Probabilistic Risk Assessment Prodecure | 235 |
Exercises | 238 | |
References | 238 |
CHAPTER 12
Risks for Light Water Reactors | 240 | |
12-1 | Introduction | 240 |
12-2 | Radioactive Inventory | 241 |
12-3 | Reactor Accidents | 242 |
12-4 | Methods for Consequence Analysis | 245 |
12-5 | Quantification of Radioactive Releases | 251 |
12-6 | Predicted Frequencies for Accident Sequences | 259 |
12-7 | Reactor Safety Study Findings | 271 |
12-8 | Limitations of the Reactor Safety Study | 280 |
12-9 | Critiques of the Reactor Safety Study | 282 |
12-10 | Follow-up Reactor Safety Studies | 284 |
12-11 | Three Mile Island Accident | 286 |
Exercises | 286 | |
References | 287 |
CHAPTER 13
Risks for Liquid Metal Fast Breeder and High | ||
Temperature Gas Reactors | 290 | |
13-1 | Liquid Metal Fast Breeder Reactor | 290 |
13-2 | High Temperature Gas Reactor | 300 |
Exercises | 303 | |
References | 303 |
CHAPTER 14
Risks for Nuclear Materials Transportation | 305 | |
14-1 | Analysis Procedure | 305 |
14-2 | Spent Nuclear Fuel Tansport | 306 |
14-3 | Uranium Hexafluoride Transport | 309 |
14-4 | Plutonium Transport | 310 |
14-5 | Nuclear Wastes Transport | 314 |
Exercises | 314 | |
References | 315 |
CHAPTER 15
Risks for Nuclear Waste Disposal | 316 | |
15-1 | Risks from Preclosure Accidents | 316 |
15-2 | Introduction to Risks from Postclosure Accidents | 316 |
15-3 | Interim Storage | 323 |
15-4 | Permanent Waste Disposal | 325 |
Exercises | 326 | |
References | 327 |
PART III
OTHER RISK ASSESSMENTS
CHAPTER 16
Comparison of Risks | 331 | |
16-1 | Conventional Energy Sources | 331 |
16-2 | Conventional and Nonconventional Energy Sources | 335 |
16-3 | Canvey Island | 343 |
16-4 | Dams | 347 |
16-5 | Other Risks | 349 |
Exercises | 353 | |
References | 354 |
CHAPTER 17
Risk-Benefit Assessments | 355 | |
17-1 | Economic Considerations | 355 |
17-2 | Different Approaches | 358 |
17-3 | Cost-Benefit Analysis of PWR Engineered Safety Features | 359 |
17-4 | Cost-Benefit Analyses of Various Health and Safety Measures | 363 |
Exercises | 365 | |
References | 365 |
CHAPTER 18
Risk Acceptance | 367 | |
18-1 | Factors Affecting Risk Acceptance | 367 |
18-2 | Statistical Risk Acceptance Analyses | 368 |
18-3 | Psychometric Risk Acceptance Analyses | 373 |
18-4 | Perception of Risks | 374 |
18-5 | Criteria for Risk Acceptance | 377 |
18-6 | Pathways Toward Risk Acceptance | 379 |
Exercises | 381 | |
References | 381 |
CHAPTER 19
Epilogue | 383 | |
References | 386 |
APPENDIXES
APPENDIX A | ||
Some Useful Mathematical Functions | 387 | |
APPENDIX B | ||
Failure Data | 391 | |
APPENDIX C | ||
Some Matrix Mathematics | 396 | |
APPENDIX D | ||
Failure Modes and Effects Analysis | 398 | |
APPENDIX E | ||
Light Water Reactor Safety Systems | 403 | |
APPENDIX F | ||
Additional Light Water Reactor Safety Study Fault Trees | 414 | |
APPENDIX G | ||
The GO Method | 421 | |
Answers to Selected Exercises | 427 | |
INDEX | 431 |