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Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors
Volume 3: Procedures and Applications
- 2nd Edition - July 29, 2024
- Editors: Francesco D'Auria, Yassin A. Hassan
- Language: English
- Paperback ISBN:9 7 8 - 0 - 3 2 3 - 8 5 6 0 8 - 9
- eBook ISBN:9 7 8 - 0 - 3 2 3 - 8 5 6 0 9 - 6
Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 3, Procedures and Applications includes all new chapters which delve deeper into the topic, adding context a… Read more
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Request a sales quoteHandbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 3, Procedures and Applications includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more.
In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided.
- Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics
- Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix
- Covers applicable nuclear reactor safety considerations and design technology throughout
Graduate and undergraduate students of nuclear or thermal engineering, researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, engineers and technicians in thermal hydraulics, NPP operators, code developers, safety engineers and investigators, nuclear designers and vendors, Students and researchers in chemical and mechanical engineering
- Cover image
- Title page
- Table of Contents
- Copyright
- Dedication
- List of contributors
- Contributors for volumes 1, 2 and 3
- Foreword
- Glossary
- Preface to the first edition of the book
- Preface to the second edition of the book
- Acknowledgments (for the past) and wishes (for the future)
- 18. Subchannel modeling and codes
- Foreword
- 18.1. Introduction
- 18.2. The framework for subchannel analyses
- 18.3. The balance equations
- 18.4. The constitutive models
- 18.5. The codes
- 18.6. The validation
- 18.7. Applications and achievements
- 18.8. Conclusions
- Exercises and questions
- 19. Containment thermal hydraulics
- Foreword
- 19.1. Introduction (evolution and role of containment)
- 19.2. Containment in existing water-cooled nuclear reactors
- 19.3. Containment for advanced reactors (AP-1000 and ESBWR)
- 19.4. Containment in SMR (NuScale, SMR160, CAREM, SMART, etc.)
- 19.5. Phenomena in the containment during transients
- 19.6. Computer codes for simulation of containment
- 19.7. Scaling of containment phenomena
- 19.8. Test facilities for experimental investigation of containment phenomena
- 19.9. Summary and conclusions
- Exercises and questions
- 20. Numerical methods in nuclear thermal hydraulics
- Foreword
- 20.1. An introduction to numerical methods: basic concepts on the discretization of partial differential equations
- 20.2. The solution of parabolic PDE
- 20.3. The solution of elliptic PDE
- 20.4. The solution of hyperbolic PDE
- 20.5. The validity of computer codes solutions
- 20.6. Automatic computation of sensitivities to parameters in TH codes
- Exercises and questions
- 21. Scaling in nuclear thermal hydraulics
- Foreword
- Part 1: Scaling background
- Part 2: Scaling techniques (approaches and methods)
- Part 3: Scaling database
- Part 4: Scaling achievements
- 22. Good practices in V&V for system thermal-hydraulic codes
- Foreword
- 22.1. Introduction
- 22.2. Scope for the SYS TH code and requirements
- 22.3. SYS TH code development process
- 22.4. Verification
- 22.5. Validation
- 22.6. Independent assessment and SYS TH code maintenance
- 22.7. SYS TH code application
- 22.8. The V&V&C
- 22.9. Conclusions and recommendations
- Exercises and questions
- 23. Elements of thermal hydraulic design of water-cooled nuclear reactors
- Foreword
- 23.1. Introduction
- 23.2. General design parameters for WCNRs
- 23.3. Boiling water reactors
- 23.4. Pressurized water reactors
- 23.5. VVER (Russian design PWR)
- 23.6. AP-1000
- 23.7. CANDU
- 23.8. Atucha-II PHWR
- 23.9. RBMK
- 23.10. Selected water-cooled SMRs
- 23.11. Containment
- 23.12. Balance of plant (BoP)
- 23.13. Passive systems and reliability of thermal-hydraulic passive systems
- 23.14. Final remarks and relevant questions and answers
- Exercises and questions
- 24. Perspectives in nuclear thermal hydraulics
- Foreword
- 24.1. Introduction
- 24.2. Modeling
- 24.3. Validation
- 24.4. Scaling
- 24.5. Uncertainty
- 24.6. Applications of NTH
- 24.7. Final remarks for status in NTH
- 24.8. The NTH framework for establishing recommendations
- 24.9. The connection of NTH with the evolving NRS
- 24.10. Managing the repetitions in the book
- 24.11. Conclusions
- Exercises and questions
- List of symbols and abbreviations
- Questions and answers from Chapters 18 to 24
- References
- Index
- No. of pages: 844
- Language: English
- Edition: 2
- Published: July 29, 2024
- Imprint: Woodhead Publishing
- Paperback ISBN: 9780323856089
- eBook ISBN: 9780323856096
FD
Francesco D'Auria
Francesco D’Auria is a Professor at the University of Pisa, Italy, and Founder and Head of the University’s San Piero a Grado Nuclear Research Group. He was Founder and Editor-in-Chief of the J. Science & Technology of Nuclear Installations (Hindawi) and has been a member of the Advisory Editorial Board of the J. Nuclear Engineering and Design (Elsevier) since 1990. He has been Chairman and/or Organizer of almost 100 sessions in Conferences since 1982 and was recently General Chairman of the ANS NURETH-15 Conference held in Pisa in 2013. He is a Member of the Technical Review Committee of the JANSI (Japan Nuclear Safety Institute), Member of various international groups in IAEA and OECD/NEA, Chair of the ENS TopSafe Conferences of 2008 and 2012 and forthcoming 2017, as well as Foreign Member of the Academy of Science in Buenos Aires. He received several recognitions including the gold medal ‘N. A. Dollezhal’ from NIKIET in Russia. D’Auria is co-author of more than 900 papers (more than 150 of which have been published in International Journals) and more than 1000 reports.
Affiliations and expertise
Professor, University of Pisa, Italy; Founder and Head, University’s San Piero a Grado Nuclear Research GroupYH
Yassin A. Hassan
Dr. Yassin Hassan is the Department Head and Professor at Texas A&M University. He received his master’s and doctorate in nuclear in nuclear engineering from the University of Illinois, and a master’s in mechanical engineering from the University of Virginia. He is a fellow of the American Association for the Advancement of Science, the American Society of Mechanical of Mechanical Engineers and American Nuclear Society (ANS). In 2007, Hassan was sworn in as a part-time technical judge to the Atomic Safety and Licensing Board Panel of the U.S. Nuclear Regulatory Commission. He has authored more than 490 refereed publications in technical journals and conference proceedings (195 technical journals and 295 conferences) and more than 380 summaries in American Nuclear Society transactions (the largest for any ANS member since its establishment in 1950). He also serves as editor-in-chief of the Journal of Nuclear Engineering and Design and is associate editor of the Journal of Verification, Validation and Uncertainty Quantification. He is elected to National Academy of Engineering in 2019.
Affiliations and expertise
Professor and Department Head, Texas A&M University, USARead Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors on ScienceDirect