Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and SMRs presents key phenomena, models, advantages, and drawbacks of current methods. The book guides the reader through the preparation and review of the thermal-hydraulic part of a safety analysis report and equips them with the knowledge to perform thermal-hydraulic studies with confidence. Starting with an introduction to thermal-hydraulics and two-phase flows, the book covers key models such as the Homogeneous Equilibrium Model and Drift Flux, Main Phenomena and associated models, including critical flow, heat transfer and void fraction, and then moves onto cover nuclear safety analyses and code.
It contains fundamental tools to help readers understand complicated phenomena that can happen in various accidental conditions, along with key principles to help readers when using advanced simulation tools. This book is suitable for a broad audience, including non-specialized readers seeking independent advice and technicians or engineers working in nuclear facilities. It will provide students in engineering disciplines with a solid understanding of the thermal-hydraulics of nuclear reactors and safety, which will enable them to work safely and efficiently and drive research forward.
1. Chapter 1. Introduction: Thermal-hydraulics and two-phase flows - p. 1 2. Chapter 2. Key definitions - p. 5 3. Chapter 3. Key models for two-phase flows - p. 25 4. Chapter 4. Main phenomena and associated models - p. 35 5. Abstract - p. 35 6. 4.1 Void fraction - p. 36 7. 4.2 Pressure and flow rate - p. 47 8. 4.3 Heat transfer - p. 60 9. 4.4 Critical flow - p. 70 10. 4.5 Countercurrent flow - p. 81 11. 4.6 Condensation - p. 84 12. 4.7 Natural circulation - p. 90 13. 4.8 Some definitions and phenomena specific to transient situations - p. 96 14. References - p. 102 15. Chapter 5. General principles of nuclear reactor safety analysis - p. 105 16. Chapter 6. Innovative passive systems - p. 135 17. Chapter 7. Departure from nucleate boiling (DNB) analyses - p. 145 18. Chapter 8. LOCA analyses and associated safety demonstration - p. 179 19. Chapter 9. Computational fluid dynamics applications and other transients - p. 203 20. Chapter 10. Specificities of PWR-SMRs - p. 215 21. Chapter 11. Conclusion - p. 222 22. Chapter 12. Applications - p. 227 23. Chapter 13. Glossary - p. 243 24. Chapter 14. Units and symbols - p. 247 25. Chapter 15. Steam tables - p. 253 26. Index - p. 259
Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and SMRs presents key phenomena, models, advantages, and drawbacks of current methods. The book guides the reader through the preparation and review of the thermal-hydraulic part of a safety analysis report and equips them with the knowledge to perform thermal-hydraulic studies with confidence. Starting with an introduction to thermal-hydraulics and two-phase flows, the book covers key models such as the Homogeneous Equilibrium Model and Drift Flux, Main Phenomena and associated models, including critical flow, heat transfer and void fraction, and then moves onto cover nuclear safety analyses and code.
It contains fundamental tools to help readers understand complicated phenomena that can happen in various accidental conditions, along with key principles to help readers when using advanced simulation tools. This book is suitable for a broad audience, including non-specialized readers seeking independent advice and technicians or engineers working in nuclear facilities. It will provide students in engineering disciplines with a solid understanding of the thermal-hydraulics of nuclear reactors and safety, which will enable them to work safely and efficiently and drive research forward.
1. Chapter 1. Introduction: Thermal-hydraulics and two-phase flows - p. 1 2. Chapter 2. Key definitions - p. 5 3. Chapter 3. Key models for two-phase flows - p. 25 4. Chapter 4. Main phenomena and associated models - p. 35 5. Abstract - p. 35 6. 4.1 Void fraction - p. 36 7. 4.2 Pressure and flow rate - p. 47 8. 4.3 Heat transfer - p. 60 9. 4.4 Critical flow - p. 70 10. 4.5 Countercurrent flow - p. 81 11. 4.6 Condensation - p. 84 12. 4.7 Natural circulation - p. 90 13. 4.8 Some definitions and phenomena specific to transient situations - p. 96 14. References - p. 102 15. Chapter 5. General principles of nuclear reactor safety analysis - p. 105 16. Chapter 6. Innovative passive systems - p. 135 17. Chapter 7. Departure from nucleate boiling (DNB) analyses - p. 145 18. Chapter 8. LOCA analyses and associated safety demonstration - p. 179 19. Chapter 9. Computational fluid dynamics applications and other transients - p. 203 20. Chapter 10. Specificities of PWR-SMRs - p. 215 21. Chapter 11. Conclusion - p. 222 22. Chapter 12. Applications - p. 227 23. Chapter 13. Glossary - p. 243 24. Chapter 14. Units and symbols - p. 247 25. Chapter 15. Steam tables - p. 253 26. Index - p. 259
