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Nuclear Power Reactor Designs
From History to Advances
- 1st Edition - December 1, 2023
- Authors: Sola Talabi, Sama Bilbao y Leon, Jun Wang
- Editors: Jun Wang, Sola Talabi, Sama Bilbao y Leon
- Language: English
- Paperback ISBN:9 7 8 - 0 - 3 2 3 - 9 9 8 8 0 - 2
- eBook ISBN:9 7 8 - 0 - 3 2 3 - 9 9 9 4 6 - 5
Nuclear Power Reactor Designs: From History to Advances analyzes nuclear designs throughout history and explains how each of those has helped to shape and inform the nuclear r… Read more
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Request a sales quoteNuclear Power Reactor Designs: From History to Advances analyzes nuclear designs throughout history and explains how each of those has helped to shape and inform the nuclear reactor designs of today and the future. Focused on the structure, systems and relevant components of each reactor design, this book provides the readers with answers to key questions to help them understand the benefits of each design. Each reactor design is introduced, their origin defined, and the relevant research presented before an analysis of its successes, what was learned, and how research and technology advanced as a result are presented.
Students, researchers and early career engineers will gain a solid understanding of how nuclear designs have evolved, and how they will continue to develop in the future.
- Presents reactor designs through history to present day, focusing on key structures, systems and components
- Provides readers with quick answers about various design principles and rationales
- Includes new approaches such as the micro-reactor and small-modular reactors
Graduate and undergraduate students and early career engineers in nuclear power reactors, nuclear researchers and scientists, nuclear designers, nuclear regulators, Engineers and researchers seeking to learn about nuclear power reactors from other disciplines and backgrounds
- Cover image
- Title page
- Table of Contents
- Copyright
- List of contributors
- Section 1: Nuclear power plant history
- Chapter 1. History of nuclear power plants development
- Abstract
- 1.1 Introduction
- 1.2 The early development: from Chicago Pile-1 to Shippingport
- 1.3 The golden age: from Shippingport to Chernobyl Accident
- 1.4 Fission plant development
- 1.5 The last decades: from Chernobyl accident to the present days
- Abbreviations
- References
- Chapter 2. Early graphite-moderated reactors
- Abstract
- References
- Chapter 3. Future challenges
- Abstract
- 3.1 The challenge of decarbonization
- 3.2 New technology deployment scenarios
- References
- Section 2: Light water reactor
- Chapter 4. History, specific design features, and evolution of VVER reactors
- Abstract
- 4.1 Introduction
- 4.2 Development of VVER-440 reactors
- 4.3 Development of VVER-1000 reactors
- 4.4 Large VVER reactors currently being implemented
- References
- Chapter 5. Boiling water reactors (Gen II)
- Abstract
- 5.1 Introduction
- 5.2 Design characteristics
- 5.3 Accident-tolerant fuels
- References
- Chapter 6. Advanced pressurized water reactors (Gen III)
- Abstract
- 6.1 Features of advanced PWRs
- 6.2 Categories of advanced PWRs
- 6.3 Summary
- References
- Chapter 7. Advanced boiling water reactor (ABWR)
- Abstract
- 7.1 Introduction
- 7.2 ABWR projects around the world
- 7.3 Major improvements of ABWR
- 7.4 Core and fuel design
- 7.5 Thermal hydraulic features of ABWR
- 7.6 Moving forward from ABWR
- Abbreviations
- References
- Section 3: Generation IV advanced reactors
- Chapter 8. An overview of high-temperature gas-cooled reactors
- Abstract
- 8.1 Introduction
- 8.2 Development of high-temperature gas-cooled reactors
- 8.3 Features of high-temperature gas-cooled reactors
- 8.4 Development direction and application prospect of High-temperature gas-cooled reactors
- 8.5 Summary
- References
- Chapter 9. Molten salt reactors
- Abstract
- 9.1 Overview of molten salt reactors
- 9.2 Development of molten salt reactors
- 9.3 Features of molten salt reactors
- 9.4 Conclusion and future perspectives
- References
- Chapter 10. Sodium fast reactors
- Abstract
- 10.1 Introduction
- 10.2 Development history and current situation
- 10.3 Typical configurations
- 10.4 Safety characteristics
- 10.5 Summary and prospect
- References
- Chapter 11. Lead fast reactors
- Abstract
- 11.1 Lead and LBE coolant
- 11.2 The development of lead-cooled fast reactor
- 11.3 Lead-cooled fast reactor designs
- 11.4 Numerical modeling methods
- References
- Chapter 12. Gas-cooled fast reactor
- Abstract
- 12.1 Overview of gas-cooled fast reactor
- 12.2 Characteristics of GFR design
- 12.3 History of GFR
- 12.4 Path forward
- References
- Chapter 13. Supercritical water-cooled reactor
- Abstract
- 13.1 Japanese supercritical water-cooled reactor
- 13.2 European supercritical water-cooled reactor
- 13.3 Canadian supercritical water-cooled reactor
- 13.4 Chinese mixed spectrum supercritical water-cooled reactor
- 13.5 Numerical modeling methods
- References
- Section 4: Small reactors
- Chapter 14. Small modular reactors
- Abstract
- 14.1 Introduction
- 14.2 Small modular reactor designs
- 14.3 Major challenges to small modular reactor adoption
- 14.4 Conclusions
- References
- Chapter 15. Microreactors
- Abstract
- 15.1 Introduction
- 15.2 History of micro reactor development
- 15.3 Major design schemes for micro reactor
- 15.4 Future challenges for micro reactor
- 15.5 Conclusions
- References
- Section 5: Other reactors
- Chapter 16. An overview of heavy water reactors
- Abstract
- 16.1 Introduction
- 16.2 Classification of heavy water reactors
- 16.3 Characteristics of heavy water reactor
- 16.4 Structure principle of CANDU
- 16.5 Glossary
- References
- Chapter 17. Offshore floating reactors
- Abstract
- 17.1 Introduction
- 17.2 Advantages and key challenges
- 17.3 Thermo-hydraulic analysis of floating reactors
- References
- Chapter 18. Fusion reactors
- Abstract
- 18.1 Fusion basic
- 18.2 Development of typical fusion reactors
- 18.3 Some issues toward the fusion energy
- References
- Index
- No. of pages: 464
- Language: English
- Edition: 1
- Published: December 1, 2023
- Imprint: Academic Press
- Paperback ISBN: 9780323998802
- eBook ISBN: 9780323999465
JW
Jun Wang
Dr. Jun Wang is a Research Scientist at the University of Wisconsin, Madison. He has over 10 years of experience in code development, validation, and application, and his research areas include nuclear thermal hydraulics and safety, severe accident, fuel performance, and advanced reactors. Wang has over 50 peer-review articles published on top nuclear journals and conferences. He also has over 200 peer-review experience in 20 journals and conferences, such as the International Journal of Heat and Mass Transfer, Applied Thermal Engineering, Annals of Nuclear Energy, Nuclear Technology, Nuclear Engineering and Design, and Progress in Nuclear Energy.
Affiliations and expertise
Research Associate, University of Wisconsin, Madison, USAST
Sola Talabi
Dr. Sola Talabi ([email protected]) is a Principal with Pittsburgh Technical, a nuclear consulting firm specializing in advanced reactor design and deployment. He is also an adjunct professor of nuclear engineering at the University of Pittsburgh and the University of Michigan. Sola's experience includes design, computational numerical analysis, manufacturing, installation, and nuclear power plant components testing. His experience includes serving as Risk Manager at Westinghouse Electric Company, where he was responsible for risk awareness, assessment, and response for advanced reactors, including AP1000 and SMR.
Affiliations and expertise
Principal, Pittsburgh Technical, Pittsburgh, Pennsylvania, USASL
Sama Bilbao y Leon
Dr. V. H. Sanchez-Espinoza ([email protected]) is a nuclear engineer with a PhD from the Dresden University of Technology, Germany. He is Deputy Institute Director and Head of the Group "Reactor Physic and Dynamics" at the Institute of Neutron Physics and Reactor Technology (INR) of the Karlsruhe Institute of Technology (KIT). He has more than 20 years of experience on reactor physics, safety-related thermal hydraulics and reactor safety for research reactors and nuclear power plants of Gen-II, III, including SMR.
Affiliations and expertise
Deputy Institute Director, Institute of Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Karlsruhe, Germany