Table of Contents
Preface v
About the Authors ix
Acknowledgments xix
List of Tables xxvii
List of Figures xxix
1 Regulatory Status S. M. Bajorek 1
1.1 Introduction 1
1.2 Design-Basis Transients and Accidents 12
1.3 Deterministic versus "Risk-Informed" Regulation 14
References 15
2 The Safety Case S. Ergün M. McCloskey R. P Martin 17
2.1 Safety Case Basics 18
2.2 The Nuclear Power Safety Case 21
2.3 Engineering Organization Supporting Nuclear Safety 30
2.4 Safety Case Development Considerations 33
2.5 Nuclear Safety Case Reports 39
2.6 Potential Limitations of Safety Cases 43
References 46
3 Design-Basis Event Characterization R. P. Martin 49
3.1 Regulatory Background and Expectation 50
3.2 Consideration of the Single-Failure Criterion 52
3.3 Categorization of DBEs, Figures-of-Merit and Acceptance Criteria 56
3.4 DBE Scenario Definition 62
3.5 Common LWR Design-Basis Event Categories 71
3.6 Conclusion 74
References 75
4 Analytical Requirements and Software R. P. Martin D. L. Aumiller C. Frepoli 77
4.1 Analytical Requirements 77
4.2 Thermal-Hydraulic Modeling of Two-Phase Flow 85
4.3 Two-Fluid Governing Equations 87
4.4 Model Closure and Resolving Interfacial Phenomena 92
4.5 Drift Flux Model 98
4.6 The FLASH Fluid Model Case Study 103
4.7 Conclusion 121
References 122
5 Verification and Validation K. Ohkawa R. K. Ratnayake 125
5.1 Introduction 125
5.2 Verification 133
5.3 Validation against Experimental Test Data 140
5.4 Input to Uncertainty Analysis in an Evaluation Model Prediction 158
5.5 References 158
6 Similarity and Scaling José N. Reyes, Jr Cesare Frepoli 181
6.1 Introduction 181
6.2 Phenomena Identification and Ranking Tables (PIRT) 190
6.3 Hierarchical Two-Tiered Scaling (H2TS) Methodology 194
6.4 Reactor Coolant System Depressurization (LOCA Blowdown) 202
6.5 Comparison of APEX and SPES-2 Passive Safety System Responses 208
6.6 Fractional Scaling Analysis Methodology 213
6.7 Dynamical System Scaling 219
References 261
7 Deterministic and Best-Estimate Analysis Methods R. P. Martin A. Petruzzi C. Frepoli 265
7.1 Evaluation Model Reprise 267
7.2 Uncertainty in Evaluation Models 269
7.3 Deterministic Methods 276
7.4 Best-Estimate Analysis Methods 289
7.5 Deterministic versus BEPU; Current Status of Applications in Safety Analysis 323
7.6 Conclusions 325
References 326
8 PWR LOCA/Non-LOCA Design-Basis Events F. X. Buschman M. J. Meholic 333
8.1 Introduction to PWRs 333
8.2 Design-Basis Accidents and Anticipated Transients 334
8.3 Loss-of-Coolant Accident 336
8.4 Anticipated Transients and Non-LOCA Accidents 353
References 369
9 BWR LOCA/Non-LOCA Design-Basis Events D. R. Todd 371
9.1 Introduction 371
9.2 Summary of the BWR Concept and History 372
9.3 Loss-of-Coolant Accident 383
9.4 Non-LOCA 397
References 408
10 LWR - Reactivity Transients and Accidents M. Avramova K. N. Ivanov 411
10.1 Introduction 411
10.2 Description of Scenarios 420
10.3 Specific Phenomena to be Addressed in Modeling 423
10.4 Peculiarities/Specifics for Different Types of LWRs and Fuels 449
10.5 Analysis Methodologies 459
10.6 Verification and Validation of Analysis Methodologies 473
10.7 Benchmarks and Comparative Analysis 485
10.8 Uncertainty Quantification 487
10.9 Applications to Design and Safety Evaluations and Licensing 489
10.10 Summary and Conclusions 492
References 494
11 LWR Impact on Containment J. W. Lane S. C. Franz 497
11.1 General Characteristics of Containments 498
11.2 Containment Designs and Safety Systems 503
11.3 Containment Safety Analysis Considerations 511
11.4 Important Phenomena 518
11.5 Analysis Codes and Methods 524
References 528
12 Radiological Evaluations J. E. Metcalf J. E. Chang 531
12.1 Introduction 531
12.2 Definitions Unique to Radiological Evaluations 532
12.3 Design-Basis Event Radiological Evaluation Scope 534
12.4 Role of Plant Procedures and Severe Accident Management Guidance in Radiological Evaluations 538
12.5 Source Terms 539
12.6 Pathways 556
12.7 Analysis of Radiological Consequences - General 596
12.8 Analysis of Onsite Radiological Consequences 603
12.9 Analysis of Offsite Radiological Consequences 618
References 626
13 Accident Tolerant Designs and Corresponding Analyses - Generation IV/SMRs F. Aydogan 631
13.1 Introduction 631
13.2 Radiation Barriers for SMRs and GEN-IV Reactors 633
13.3 Accident Tolerant Fuels 633
13.4 Accident Tolerant Fuel Claddings 635
13.5 Emergency Core Coolant Systems 636
13.6 Accident Tolerant Reactor and Containment Designs 638
13.7 Analyses of the Accident Tolerant Systems 642
13.8 Conclusions 643
Acknowledgment 643
References 643
14 Licensing Considerations B. A. McIntyre 645
14.1 Overview of the U.S. Nuclear Regulatory Commission Licensing Process 645
14.2 Design Control of Design-Basis Envelope 654
References 658
Glossary 659
Index 673
