Preface |
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v | |
About the Authors |
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ix | |
Acknowledgments |
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xix | |
List of Tables |
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xxvii | |
List of Figures |
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xxix | |
1 Regulatory Status |
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1 | (16) |
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1 | (11) |
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1.2 Design-Basis Transients and Accidents |
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12 | (2) |
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1.3 Deterministic versus "Risk-Informed" Regulation |
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14 | (1) |
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15 | (2) |
2 The Safety Case |
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17 | (32) |
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18 | (3) |
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2.2 The Nuclear Power Safety Case |
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21 | (9) |
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2.3 Engineering Organization Supporting Nuclear Safety |
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30 | (3) |
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2.4 Safety Case Development Considerations |
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33 | (6) |
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2.5 Nuclear Safety Case Reports |
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39 | (4) |
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2.6 Potential Limitations of Safety Cases |
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43 | (3) |
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46 | (3) |
3 Design-Basis Event Characterization |
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49 | (28) |
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3.1 Regulatory Background and Expectation |
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50 | (2) |
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3.2 Consideration of the Single-Failure Criterion |
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52 | (4) |
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3.3 Categorization of DBEs, Figures-of-Merit and Acceptance Criteria |
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56 | (6) |
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3.4 DBE Scenario Definition |
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62 | (9) |
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3.5 Common LWR Design-Basis Event Categories |
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71 | (3) |
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74 | (1) |
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75 | (2) |
4 Analytical Requirements and Software |
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77 | (48) |
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4.1 Analytical Requirements |
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77 | (8) |
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4.2 Thermal-Hydraulic Modeling of Two-Phase Flow |
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85 | (2) |
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4.3 Two-Fluid Governing Equations |
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87 | (5) |
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4.4 Model Closure and Resolving Interfacial Phenomena |
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92 | (6) |
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98 | (5) |
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4.6 The FLASH Fluid Model Case Study |
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103 | (18) |
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121 | (1) |
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122 | (3) |
5 Verification and Validation |
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125 | (56) |
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125 | (8) |
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133 | (7) |
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5.3 Validation against Experimental Test Data |
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140 | (18) |
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5.4 Input to Uncertainty Analysis in an Evaluation Model Prediction |
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158 | (1) |
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158 | (23) |
6 Similarity and Scaling |
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181 | (84) |
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181 | (9) |
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6.2 Phenomena Identification and Ranking Tables (PIRT) |
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190 | (4) |
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6.3 Hierarchical Two-Tiered Scaling (H2TS) Methodology |
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194 | (8) |
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6.4 Reactor Coolant System Depressurization (LOCA B lowdown) |
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202 | (6) |
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6.5 Comparison of APEX and SPES-2 Passive Safety System Responses |
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208 | (5) |
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6.6 Fractional Scaling Analysis Methodology |
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213 | (6) |
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6.7 Dynamical System Scaling |
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219 | (42) |
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261 | (4) |
7 Deterministic and Best-Estimate Analysis Methods |
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265 | (68) |
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7.1 Evaluation Model Reprise |
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267 | (2) |
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7.2 Uncertainty in Evaluation Models |
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269 | (7) |
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7.3 Deterministic Methods |
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276 | (13) |
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7.4 Best-Estimate Analysis Methods |
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289 | (34) |
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7.5 Deterministic versus BEPU: Current Status of Applications in Safety Analysis |
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323 | (2) |
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325 | (1) |
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326 | (7) |
8 PWR LOCA/Non-LOCA Design-Basis Events |
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333 | (38) |
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333 | (1) |
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8.2 Design-Basis Accidents and Anticipated Transients |
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334 | (2) |
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8.3 Loss-of-Coolant Accident |
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336 | (17) |
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8.4 Anticipated Transients and Non-LOCA Accidents |
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353 | (16) |
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369 | (2) |
9 BWR LOCA/Non-LOCA Design-Basis Events |
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371 | (40) |
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371 | (1) |
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9.2 Summary of the BWR Concept and History |
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372 | (11) |
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9.3 Loss-of-Coolant Accident |
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383 | (14) |
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397 | (11) |
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408 | (3) |
10 LWR-Reactivity Transients and Accidents |
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411 | (86) |
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411 | (9) |
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10.2 Description of Scenarios |
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420 | (3) |
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10.3 Specific Phenomena to be Addressed in Modeling |
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423 | (26) |
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10.4 Peculiarities/Specifics for Different Types of LWRs and Fuels |
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449 | (10) |
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10.5 Analysis Methodologies |
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459 | (14) |
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10.6 Verification and Validation of Analysis Methodologies |
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473 | (12) |
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10.7 Benchmarks and Comparative Analysis |
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485 | (2) |
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10.8 Uncertainty Quantification |
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487 | (2) |
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10.9 Applications to Design and Safety Evaluations and Licensing |
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489 | (3) |
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10.10 Summary and Conclusions |
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492 | (2) |
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494 | (3) |
11 LWR Impact on Containment |
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497 | (34) |
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11.1 General Characteristics of Containments |
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498 | (5) |
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11.2 Containment Designs and Safety Systems |
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503 | (8) |
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11.3 Containment Safety Analysis Considerations |
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511 | (7) |
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518 | (6) |
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11.5 Analysis Codes and Methods |
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524 | (4) |
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528 | (3) |
12 Radiological Evaluations |
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531 | (100) |
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531 | (1) |
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12.2 Definitions Unique to Radiological Evaluations |
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532 | (2) |
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12.3 Design-Basis Event Radiological Evaluation Scope |
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534 | (4) |
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12.4 Role of Plant Procedures and Severe Accident Management Guidance in Radiological Evaluations |
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538 | (1) |
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539 | (17) |
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556 | (40) |
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12.7 Analysis of Radiological Consequences-General |
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596 | (7) |
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12.8 Analysis of Onsite Radiological Consequences |
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603 | (15) |
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12.9 Analysis of Offsite Radiological Consequences |
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618 | (8) |
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626 | (5) |
13 Accident Tolerant Designs and Corresponding Analyses-Generation IV/SMRs |
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631 | (14) |
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631 | (2) |
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13.2 Radiation Barriers for SMRs and GEN-IV Reactors |
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633 | (1) |
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13.3 Accident Tolerant Fuels |
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633 | (2) |
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13.4 Accident Tolerant Fuel Claddings |
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635 | (1) |
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13.5 Emergency Core Coolant Systems |
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636 | (2) |
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13.6 Accident Tolerant Reactor and Containment Designs |
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638 | (4) |
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13.7 Analyses of the Accident Tolerant Systems |
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642 | (1) |
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643 | (1) |
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643 | (1) |
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643 | (2) |
14 Licensing Considerations |
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645 | (14) |
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14.1 Overview of the U.S. Nuclear Regulatory Commission Licensing Process |
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645 | (9) |
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14.2 Design Control of Design-Basis Envelope |
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654 | (4) |
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658 | (1) |
Glossary |
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659 | (14) |
Index |
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673 | |