Light water reactor safety

1 INTRODUCTION 2 HISTORICAL REVIEW 5 2.1 Developments in the USA 5 2.2 Developments in Sweden 12 References 18 3 ELEMENTS OF REACTOR TECHNOLOGY 20 3.1 Basic Principles 20 3.2 Reactor Fuel 22 3.3 Fission Power 25 3.4 Heat Transfer 42 3.5 Structural Mechanics 53 References 58 4 BOILING WATER REACTORS 59 4.1 Reactor Vessel and Internals 59 4.2 Primary Process Systems 63 4.3 Reactor Containment 67 4.4 Turbine-Generator Plant 69 4.5 Control and Monitoring Systems 72 4.6 Electrical Systems 76 4.7 Main Technical Data for Swedish BWRs 79 References 81 5 PRESSURIZED WATER REACTORS 82 5.1 Reactor Vessel and Internals 82 5.2 Reactor Coolant System 86 5.3 Reactor Containment 91 5.4 Control Systems 93 5.5 Main Technical Data for Swedish PWRs 95 References 976 NUCLEAR RADIATION 98 6.1 Basic Concepts 98 6.2 Emission Rates 101 6.3 Fission Product Behaviour 106 6.4 Fission Product Release 109 6.5 Activity Removal Facilities 113 6.6 Radiation Protection 117 References 125 7 SAFETY PRINCIPLES 126 7.1 Radiological Criteria 126 7.2 Safety Design 129 7.3 Safety During Operation 137 7.4 Safety Administration 140 References 147 . 8 SAFETY SYSTEMS 148 8.1 Boiling Water Reactors 148 8.2 Pressurized Water Reactors 157 8.3 Safety Functions 163 8.4 Data for Safety Systems 167 References 169 9 DETERMINISTIC SAFETY ANALYSIS 170 9.1 Type of Events 170 9.2 Criteria 173 9.3 Analytical Methods 176 9.4 LOCA in BWR 177 9.5 LOCA in PWR 185 9.6 Transients in BWR 190 9.7 Transients in PWR 200 9.8 External Events 206 References 208 10 PROBABILISTIC SAFETY ANALYSIS 209 10.1 Scope of Analysis 209 10.2 Reliability Technology 210 10.3 Plant Analyses 224 10.4 Fracture Probabilities 247 10.5 External Events 249 References 255 1 1 SEVERE ACCIDENT ANALYSIS 257 11.1 Core Meltdown 257 11.2 Thermohydraulic Analysis 263 11.3 Internal Source Terms 267 11.4 Containment Analysis 274 11.5 External Source Terms 280 References 29012 CONSEQUENCE ANALYSIS 291 12.1 Methodology 291 1 2.2 Deterministic Analysis 302 12.3 Probabilistic Analysis 309 12.4 Risk Assessment 328 References 332 13 OPERATING EXPERIENCE 334 13.1 Plant Availability 334 13.2 Activity Release and Occupational Exposure 337 13.3 Safety-related Events 341 13.4 Significant Events 348 13.S The Three Mile Island Accident 3S0 13.6 Feedback of Experience 3S9 13.7 The Chernobyl Accident 362 References 377 14 SAFETY IMPROVEMENT 379 14.1 Generic Safety Issues 379 14.2 Impact of the TMI Accident 388 14.3 Plant Modification 392 References 396 15 REACTOR SAFETY RESEARCH 398 IS.1 Heat Transfer and Fluid Flow 398 IS.2 Fuel and Cladding 407 IS.3 Materials and Mechanics 412 IS.4 Corrosion and Water Chemistry 41S IS.S Instrumentation and Control 418 IS.6 Reliability and Uncertainties 421 IS.7 Core Melting and Containment Behaviour 424 References 434 16 SECURE REACTORS 437 16.1 Safety Philosophy 437 16.2 The PIUS Principle 438 16.3 SECURE-H 440 16.4 SECURE-P 441 References 442