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E-grāmata: Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants

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This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)
Preface v
About the Authors ix
Acknowledgments xix
List of Tables xxvii
List of Figures xxix
1 Regulatory Status 1(16)
S.M. Bajorek
1.1 Introduction
1(11)
1.2 Design-Basis Transients and Accidents
12(2)
1.3 Deterministic versus "Risk-Informed" Regulation
14(1)
References
15(2)
2 The Safety Case 17(32)
S. Ergun, M. McCloskey
R.P. Martin
2.1 Safety Case Basics
18(3)
2.2 The Nuclear Power Safety Case
21(9)
2.3 Engineering Organization Supporting Nuclear Safety
30(3)
2.4 Safety Case Development Considerations
33(6)
2.5 Nuclear Safety Case Reports
39(4)
2.6 Potential Limitations of Safety Cases
43(3)
References
46(3)
3 Design-Basis Event Characterization 49(28)
R.P. Martin
3.1 Regulatory Background and Expectation
50(2)
3.2 Consideration of the Single-Failure Criterion
52(4)
3.3 Categorization of DBEs, Figures-of-Merit and Acceptance Criteria
56(6)
3.4 DBE Scenario Definition
62(9)
3.5 Common LWR Design-Basis Event Categories
71(3)
3.6 Conclusion
74(1)
References
75(2)
4 Analytical Requirements and Software 77(48)
R.P. Martin
D.L. Aumiller
C. Frepoli
4.1 Analytical Requirements
77(8)
4.2 Thermal-Hydraulic Modeling of Two-Phase Flow
85(2)
4.3 Two-Fluid Governing Equations
87(5)
4.4 Model Closure and Resolving Interfacial Phenomena
92(6)
4.5 Drift Flux Model
98(5)
4.6 The FLASH Fluid Model Case Study
103(18)
4.7 Conclusion
121(1)
References
122(3)
5 Verification and Validation 125(56)
K. Ohkawa
R.K. Ratnayake
5.1 Introduction
125(8)
5.2 Verification
133(7)
5.3 Validation against Experimental Test Data
140(18)
5.4 Input to Uncertainty Analysis in an Evaluation Model Prediction
158(1)
5.5 References
158(23)
6 Similarity and Scaling 181(84)
Jose N. Reyes Jr
Cesare Frepoli
6.1 Introduction
181(9)
6.2 Phenomena Identification and Ranking Tables (PIRT)
190(4)
6.3 Hierarchical Two-Tiered Scaling (H2TS) Methodology
194(8)
6.4 Reactor Coolant System Depressurization (LOCA B lowdown)
202(6)
6.5 Comparison of APEX and SPES-2 Passive Safety System Responses
208(5)
6.6 Fractional Scaling Analysis Methodology
213(6)
6.7 Dynamical System Scaling
219(42)
References
261(4)
7 Deterministic and Best-Estimate Analysis Methods 265(68)
R.P. Martin
A. Petruzzi
C. Frepoli
7.1 Evaluation Model Reprise
267(2)
7.2 Uncertainty in Evaluation Models
269(7)
7.3 Deterministic Methods
276(13)
7.4 Best-Estimate Analysis Methods
289(34)
7.5 Deterministic versus BEPU: Current Status of Applications in Safety Analysis
323(2)
7.6 Conclusions
325(1)
References
326(7)
8 PWR LOCA/Non-LOCA Design-Basis Events 333(38)
F.X. Buschman
M.J. Meholic
8.1 Introduction to PWRs
333(1)
8.2 Design-Basis Accidents and Anticipated Transients
334(2)
8.3 Loss-of-Coolant Accident
336(17)
8.4 Anticipated Transients and Non-LOCA Accidents
353(16)
References
369(2)
9 BWR LOCA/Non-LOCA Design-Basis Events 371(40)
D.R. Todd
9.1 Introduction
371(1)
9.2 Summary of the BWR Concept and History
372(11)
9.3 Loss-of-Coolant Accident
383(14)
9.4 Non-LOCA
397(11)
References
408(3)
10 LWR-Reactivity Transients and Accidents 411(86)
M. Avramova
K.N. Ivanov
10.1 Introduction
411(9)
10.2 Description of Scenarios
420(3)
10.3 Specific Phenomena to be Addressed in Modeling
423(26)
10.4 Peculiarities/Specifics for Different Types of LWRs and Fuels
449(10)
10.5 Analysis Methodologies
459(14)
10.6 Verification and Validation of Analysis Methodologies
473(12)
10.7 Benchmarks and Comparative Analysis
485(2)
10.8 Uncertainty Quantification
487(2)
10.9 Applications to Design and Safety Evaluations and Licensing
489(3)
10.10 Summary and Conclusions
492(2)
References
494(3)
11 LWR Impact on Containment 497(34)
J.W. Lane
S.C. Franz
11.1 General Characteristics of Containments
498(5)
11.2 Containment Designs and Safety Systems
503(8)
11.3 Containment Safety Analysis Considerations
511(7)
11.4 Important Phenomena
518(6)
11.5 Analysis Codes and Methods
524(4)
References
528(3)
12 Radiological Evaluations 531(100)
J.E. Metcalf
J.E. Chang
12.1 Introduction
531(1)
12.2 Definitions Unique to Radiological Evaluations
532(2)
12.3 Design-Basis Event Radiological Evaluation Scope
534(4)
12.4 Role of Plant Procedures and Severe Accident Management Guidance in Radiological Evaluations
538(1)
12.5 Source Terms
539(17)
12.6 Pathways
556(40)
12.7 Analysis of Radiological Consequences-General
596(7)
12.8 Analysis of Onsite Radiological Consequences
603(15)
12.9 Analysis of Offsite Radiological Consequences
618(8)
References
626(5)
13 Accident Tolerant Designs and Corresponding Analyses-Generation IV/SMRs 631(14)
E Aydogan
13.1 Introduction
631(2)
13.2 Radiation Barriers for SMRs and GEN-IV Reactors
633(1)
13.3 Accident Tolerant Fuels
633(2)
13.4 Accident Tolerant Fuel Claddings
635(1)
13.5 Emergency Core Coolant Systems
636(2)
13.6 Accident Tolerant Reactor and Containment Designs
638(4)
13.7 Analyses of the Accident Tolerant Systems
642(1)
13.8 Conclusions
643(1)
Acknowledgment
643(1)
References
643(2)
14 Licensing Considerations 645(14)
B.A. McIntyre
14.1 Overview of the U.S. Nuclear Regulatory Commission Licensing Process
645(9)
14.2 Design Control of Design-Basis Envelope
654(4)
References
658(1)
Glossary 659(14)
Index 673