Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and iPWR-SMRs
- 1st Edition - March 3, 2025
- Imprint: Academic Press
- Editor: Christophe Herer
- Language: English
- Paperback ISBN:9 7 8 - 0 - 3 2 3 - 9 0 4 9 4 - 0
- eBook ISBN:9 7 8 - 0 - 3 2 3 - 9 0 4 9 5 - 7
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 re… Read more
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Request a sales quoteThermal-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.
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.
- Presents key phenomena and basic models without complex equations
- Focuses on DNB and LOCA thermal-hydraulic safety analyses
- Includes simple applications and tools for the evaluation of order of magnitude
Students in engineering disciplines who require knowledge of thermal hydraulics of nuclear reactors and safety, technicians and engineers in nuclear settings, non-nuclear engineers working in a nuclear setting
1 Introduction: Thermal-hydraulics and two-phase flows
2 Key definitions
2.1 Hydraulic diameter
2.2 Enthalpy balance
2.3 Thermodynamic quality
2.4 Two-phase flow variables (focus on flow regime, void fraction, and slip)
3 Key models
3.1 Homogeneous Equilibrium Model
3.2 Drift Flux
4 Main phenomena and associated models
4.1 Void Fraction
4.2 Pressures drops and flow rate
4.3 Critical flow
4.4 Heat transfer
4.5 Natural circulation
5 Nuclear safety
5.0.1 Methodology for deterministic thermal-hydraulic analyses
5.0.2 Code qualification
5.0.3 Order of magnitude of thermal-hydraulic parameters in PWR
5.1 DNB analyses
5.1.1 Subchannel analysis code
5.1.2 CHF correlations for PWR
5.2 LOCA analyses
5.2.1 Thermal-hydraulic system codes
5.2.2 Large Break LOCAs
5.2.3 Intermediate and small break LOCA
5.3 Other transients
5.3.1 Other analytical tools (CFD, CMFD)
5.3.2 Dilution, PTS
6. Conclusion
7. Glossary
8. Units, acronyms, notations, symbols and main relations
- Edition: 1
- Published: March 3, 2025
- No. of pages (Paperback): 274
- Imprint: Academic Press
- Language: English
- Paperback ISBN: 9780323904940
- eBook ISBN: 9780323904957
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Christophe Herer
Christophe Herer is a fluid mechanics and energy engineer. He worked for more than 23 years at Framatome in core thermal-hydraulics where he was nominated senior expert. Christophe joined the IRSN international development division IRSN in 2009 where he managed several projects in Egypt, Jordan, Mexico among others. At the IRSN thermalhydraulic simulation department since 2013, he is responsible of the development of international collaborations and of innovative passive systems assessment. Christophe is also the chairman of the OECD/NEA WGAMA 3D SYSTH activity on 3D capabilities of thermalhydraulic system codes. Christophe Herer is also a regular lecturer at the engineering school "Institut Mines Atlantique/ Ecole des Mines" in Nantes (France).
Affiliations and expertise
Institute for Radiological Protection and Nuclear Safety, Fontenay-aux-Roses Cedex, FranceRead Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and iPWR-SMRs on ScienceDirect