Handbook of Generation IV Nuclear Reactors

A Guidebook

2nd Edition - December 7, 2022
Editor: Igor Pioro
Language: English
Hardback ISBN:
9 7 8 - 0 - 1 2 - 8 2 0 5 8 8 - 4
eBook ISBN:
9 7 8 - 0 - 1 2 - 8 2 2 6 5 3 - 7

Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reacto… Read more

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Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research.

Cover image
Title page
Table of Contents
Copyright
Contributors
Foreword
Preface
Chapter 1 Introduction
Sub Chapter 1.1 Current status of electricity generation in the world
Sub Chapter 1.2 Current status and future trends in the world nuclear-power industry
Part I: Generation IV nuclear-reactor concepts
Chapter 2 Generation IV International Forum (GIF)
Abstract
Acknowledgments
2.1 Origins of GIF
2.2 Gen-IV goals
2.3 Selection of Gen-IV systems
2.4 Six Gen-IV nuclear-energy systems
2.5 Methodology working groups, task forces, cross-cutting items and the Senior Industrial Advisory Panel
2.6 Summary
References
Further reading
Chapter 3 Very High Temperature Reactor
Abstract
3.1 Development history and current status
3.2 Technology overview
3.3 Detailed technical description
3.4 Applications and economics
3.5 Summary
References
Chapter 4 Gas-cooled Fast Reactors (GFRs)
Abstract
4.1 Rationale and generational R&D bridge
4.2 Gas-cooled Fast Reactor technology
4.3 Evolution of Generation-IV GFRs into small modular reactor and micro reactors
4.4 Conclusions
References
Chapter 5 Sodium-cooled Fast Reactors (SFRs)
Abstract
5.1 Introduction
5.2 Development history
5.3 System characteristics
5.4 Safety issues
5.5 Future trends and key challenges
References
Chapter 6 Lead-cooled Fast Reactors (LFRs)
Abstract
Acknowledgments
6.1 Overview and motivation for lead-cooled fast reactor systems
6.2 Basic design choices
6.3 Safety principles
6.4 Fuel technology and fuel cycles for the lead-cooled fast reactor
6.5 Summary of advantages and key challenges of the lead-cooled fast reactor
6.6 Overview of Generation-IV lead-cooled fast reactor designs
6.7 Sources of further information
References
Chapter 7 Homogeneous Molten Salt Reactors (MSRs): The Molten Salt Fast Reactor (MSFR) concept
Abstract
Acknowledgments
7.1 Introduction
7.2 The MSFR concept
7.3 Fuel salt chemistry and material issues
7.4 MSFR fuel cycle scenarios
7.5 Safety methodology and risk analysis
7.6 Concept viability: Issues and demonstration steps
7.7 Conclusion and perspectives
References
Sources for further information
Chapter 8 SuperCritical Water-cooled Reactors (SCWRs)
Abstract
8.1 Introduction
8.2 Types of supercritical water-cooled reactor concepts and main system parameters
8.3 Example of a pressure vessel concept
8.4 Example of a pressure tube concept
8.5 Fuel cycle technology
8.6 Fuel-assembly concept
8.7 Safety system concept
8.8 Dynamics and control
8.9 Start-up
8.10 Stability
8.11 Advantages and disadvantages of supercritical water-cooled reactor concepts
8.12 Key challenges
8.13 Fuel qualification test
References
Part II: Current status of Generation IV activities in selected countries
Chapter 9 Generation IV: United States
Abstract
9.1 Generation-IV program evolution in the United States
9.2 Energy market in the United States and Generation-IV systems
9.3 Electrical grid integration of Generation-IV nuclear energy systems in the United States
9.4 Industry and utilities interests in Generation-IV nuclear energy systems in the United States
9.5 Evolution of Generation-IV nuclear energy systems into small modular reactors and micro reactors
9.6 Deployment perspectives for Generation-IV systems in the United States and deployment schedule
9.7 Conclusions
References
Further reading
Chapter 10 Generation IV: European Union: Breakthrough technologies to improve sustainability, safety & reliability, socio-economics and proliferation resistance
10.1 Introduction: “EU Energy Union” (2015) and “EU Green Deal” (2020)—Going climate neutral by 2050—Euratom contribution
10.2 EURATOM: Research & training; safety of nuclear installations; health and safety (radiation protection); safeguards; radwaste management
10.3 Generation-IV: Breakthrough developments in sustainability, safety and performance through multilateral collaboration (GIF, IAEA-INPRO)
10.4 Eight high-level goals for generation-IV nuclear energy systems and associated world-wide GIF R&D collaborative effort
10.5 Euratom research and training actions in innovative reactor systems and EU “Sustainable Nuclear Energy Technology Platform”
10.6 Experimental research reactors in the EU and small modular reactors
10.7 Conclusion: The Euratom research and training program—Maintaining EU leadership in nuclear fission developments
Chapter 11 ESFR SMART: A European Sodium Fast Reactor concept including the European feedback experience and the new safety commitments following Fukushima accident
Abstract
Acknowledgment
11.1 The ESFR-SMART project
11.2 Sodium fast reactors history in Europe
11.3 Safety improvement: Objectives and methodology
11.4 Some examples of safety improvement approach in the ESFR SMART
11.5 Description of ESFR SMART primary system including these new options
11.6 Description of ESFR SMART secondary loops
11.7 Safety analysis of the secondary loop
11.8 General layout of the plant
11.9 Handling systems
11.10 Conclusions on safety improvements
11.11 R&D needs for the ESFR SMART options
11.12 Conclusion
References
Chapter 12 Generation-IV Sodium-cooled Fast Reactor (SFR) concepts in Japan
Abstract
12.1 Introduction
12.2 JSFR design and its key innovative technologies
12.3 Update of the Japan sodium-cooled fast reactor design with lessons learned from the Fukushima Daiichi accident
12.4 Concluding remarks
References
Chapter 13 Generation-IV concepts in Korea
Abstract
13.1 Current status of nuclear power in Korea
13.2 Plans for advanced nuclear reactors in Korea
13.3 Current research and development on Generation-IV reactor in Korea
Appendix: Paper list related to PEACER (including P-demo and Pyroprocess), PASCAR, URANUS, and other SNU-NUTRECK activities
References
Further reading
Chapter 14 Generation-IV concepts: China
Abstract
14.1 Current status of nuclear power in China
14.2 Plans for advanced nuclear reactors in China
14.3 Current research and development on Generation-IV reactors in China
References
Chapter 15 Generation-IV concepts: India
Abstracts
Acknowledgments
15.1 Introduction
15.2 Advanced Heavy Water Reactors (AHWRs)
15.3 High-Temperature Reactors (HTRs)
15.4 Fast Breeder Reactor (FBR)
15.5 Molten Salt Reactors (MSRs)
15.6 Conclusions
Bibliography
Part III: Related topics to Generation IV nuclear reactor concepts
Chapter 16 The safety and risk assessment of Advanced Reactors (ARs)
Abstract
16.1 Basic safety principles
16.2 Safety and reliability goals
16.3 Safety objectives and the classification of advanced reactor types
16.4 Generic safety objectives and safety barriers
16.5 Risk informing safety requirements by learning from prior events
16.6 Major technical safety issues
16.7 Multiple modules and plant risk
16.8 The role of Safety R&D for ARs
16.9 Risk informing advanced reactor safety: Quantifying the probability and uncertainty of core damage due to loss of power and cooling
16.10 Natural circulation loop and parallel channel thermal-hydraulics
16.11 Conclusions
References
Further reading
Chapter 17 Non-proliferation for Advanced Reactors (ARs): Political and Social aspects
Abstract
17.1 Introduction
17.2 Nuclear history and basic science
17.3 A look at the future
17.4 The wider context
17.5 Fuel cycles: Sustainable recycling of used fuel compared to retrievable storage
Annex 1 EURATOM
Annex 2 The 1997 IAEA additional protocol at a glance
References
Chapter 18 Thermal aspects of conventional and alternative nuclear fuels
Abstract
18.1 Introduction
18.2 Metallic fuels
18.3 Ceramic fuels
18.4 Hydride fuels
18.5 Composite fuels
18.6 Analysis results
18.7 Discussions
References
Chapter 19 Hydrogen production pathways for Generation-IV reactors
Abstract
19.1 Introduction
19.2 Coupling hydrogen and Generation-IV reactor technologies
19.3 Biomass and fossil-based technologies
19.4 Electrolysis
19.5 Pure and hybrid thermochemical cycles
19.6 Nuclear hydrogen production toward climate change mitigation
19.7 Conclusion
References
Chapter 20 Small Modular Reactors (SMRs)
Sub Chapter 20.1 Systems of Advanced Small Modular Reactors (ASMRs)
Sub Chapter 20.2 Current status of SMRs and S&MRs development in the world
Chapter 21 Alternative power cycles for Generation-IV reactors
Sub Chapter 21.1 Alternative power cycles for selected Generation-IV reactors
Sub Chapter 21.2 Closed Brayton-cycle configurations for Gas-cooled Fast Reactors (GFRs) and Very-High-Temperature Reactors (VHTRs)
Chapter 22 Regulatory and licensing challenges with Generation-IV nuclear energy systems
Abstract
22.1 Introduction
22.2 The regulatory status
22.3 Regulatory requirements
22.4 Regulatory challenges for advanced reactors
22.5 Case study-Canadian perspectives on the design of Pressure Retaining Systems and Components (PRSCs) in small modular reactors
22.6 Conclusions
References
Further reading
Part IV: Nuclear-power technologies beyond Generation-IV concepts
Chapter 23 ITER, the way to fusion energy
Abstract
23.1 Nuclear fusion
23.2 The history of the ITER project
23.3 A gigantic fusion machine
23.4 A pharaonic worksite
23.5 Organizing a huge logistics
23.6 Delays and budget increases
23.7 The management challenge
23.8 Nuclear licensing
23.9 Safety and waste management
23.10 Natural hazards
23.11 The impact of ITER on the economy
23.12 Will fusion become commercial?
23.13 DEMO and the projects after ITER
23.14 Alternative technologies
23.15 The fusion era
References
Further reading
Appendix A1 Additional materials (layouts, T-s diagrams, basic parameters, photos, etc.) on thermal and nuclear power plants
A1.1 Introduction
A1.2 Fossil-fuel thermal power plants
A1.3 Current nuclear-power reactors and NPPs
A1.4 Conclusions
Acknowledgment
References
Appendix A2 Comparison of thermophysical properties of reactor coolants
A2.A Introduction
A2.B Reactor coolants by type
A2.C Thermophysical properties of Generation III, III+, and IV reactor coolants
A2.D Heat transfer coefficients in nuclear-power reactors
A2.E Conclusions
References
Index

Igor Pioro

Professor Igor Pioro – Ph.D. (1983); Doctor of Technical Sciences (1992); Professional Engineer (Ontario, Canada) (2008); Foreign Fellow of the National Academy of Sciences of Ukraine (2021); Fellow of the American Society of Mechanical Engineers (ASME) (2012), Canadian Society of Mechanical Engineers (CSME) (2015), and Engineering Institute of Canada (EIC) (2013); life-time member of the American Nuclear Society (ANS) (2004), and member of Canadian NS (CNS) (2010); is an internationally recognized scientist within the areas of nuclear engineering (thermalhydraulics of nuclear reactors, Generation-IV nuclear-reactor concepts, etc.) and thermal sciences / engineering (boiling, forced convection including supercritical pressures, etc.) He is author/co-author of more than 534 publications 12 technical books, 48 chapters in encyclopedias, handbooks and books, 101 papers in refereed journals, 300 papers in refereed proceedings of international and national conferences and symposiums, 26 patents and inventions, and 47 major technical reports. Dr. Pioro graduated from the National Technical University of Ukraine "Kiev Polytechnic Institute" with M.A.Sc. in Thermal Physics in 1979. After that, he worked on various positions including an engineer, senior scientist, deputy director, professor, director of a graduate program in nuclear engineering, and associate dean. Currently, he is associated with the Department of Energy and Nuclear Engineering Faculty of Engineering and Applied Science, University of Ontario Institute of Technology (brand name: Ontario Tech University) (Oshawa, Ontario, Canada). Dr. Pioro is a Founding Editor – Editor-in-Chief of the ASME Journal of Nuclear Engineering and Radiation Science (J. NERS). He was a Chair of the Executive Committee of the Nuclear Engineering Division (NED) of the ASME (2011-2012) and a Chair of the International Conference On Nuclear Engineering (ICONE-20) (2011-2012). Professor Pioro has received many international and national awards and certificates of appreciation including Certificate of Appreciation for establishing the ASME J. NERS and in recognition of outstanding and distinguished service as an Editor of the Journal 2014 – 2020 (ASME); Harold A. Smith Outstanding Contribution Award from CNS (2017), Medal 60th Anniversary of NED (Nuclear Engineering Division of ASME) (2016); Service Recognition Award from the ASME (2014); Honorary Doctor’s Degree from National Technical University of Ukraine “Kiev Polytechnic Institute” (2013); The CNS Education and Communication Award (2011); UOIT Research Excellence Award (2011); ICONE Award from ASME (2009); Medal of the National Academy of Sciences of Ukraine for the best scientific work of a young scientist (1990); Badge "Inventor of the USSR" for implementation of inventions into industry (1990); etc.

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Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology, Canada

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Handbook of Generation IV Nuclear Reactors

A Guidebook

Purchase options

Institutional subscription on ScienceDirect

Igor Pioro