Nuclear Power Reactor Designs

From History to Advances

1st Edition - December 1, 2023
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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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 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.

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

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, USA

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, USA

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