Handbook of Generation IV Nuclear Reactors

Handbook of Generation IV Nuclear Reactors

1st Edition - June 9, 2016

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  • Editor: Igor Pioro
  • eBook ISBN: 9780081001622
  • Hardcover ISBN: 9780081001493

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Handbook of Generation IV Nuclear Reactors presents information on the current fleet of Nuclear Power Plants (NPPs) with water-cooled reactors (Generation III and III+) (96% of 430 power reactors in the world) that have relatively low thermal efficiencies (within the range of 32 36%) compared to those of modern advanced thermal power plants (combined cycle gas-fired power plants – up to 62% and supercritical pressure coal-fired power plants – up to 55%). Moreover, thermal efficiency of the current fleet of NPPs with water-cooled reactors cannot be increased significantly without completely different innovative designs, which are Generation IV reactors. Nuclear power is vital for generating electrical energy without carbon emissions. Complete with the latest research, development, and design, and written by an international team of experts, this handbook is completely dedicated to Generation IV reactors.

Key Features

  • Presents the first comprehensive handbook dedicated entirely to generation IV nuclear reactors
  • Reviews the latest trends and developments
  • Complete with the latest research, development, and design information in generation IV nuclear reactors
  • Written by an international team of experts in the field


Engineers and specialists in nuclear, power and other related industries as well as researchers and scientists working on nuclear power and generation IV nuclear reactors.

Table of Contents

    • Related titles
    • List of contributors
    • Woodhead Publishing Series in Energy
    • Foreword
    • Preface
    • Nomenclature
    • 1. Introduction: A survey of the status of electricity generation in the world
      • 1.1. Statistics on electricity generation in the world
      • 1.2. Thermal power plants
      • 1.3. Modern nuclear power plants
      • 1.4. Conclusions
      • Abbreviations
    • Part One. Generation IV nuclear-reactor concepts
      • Preface to Part One
      • 2. Introduction: Generation IV International Forum
        • 2.1. Origins of the Generation IV International Forum
        • 2.2. Generation IV goals
        • 2.3. Selection of Generation IV systems
        • 2.4. Six Generation IV nuclear energy systems
        • 2.5. Summary
      • 3. Very high-temperature reactor
        • 3.1. Development history and current status
        • 3.2. Technology overview
        • 3.3. Detailed technical description
        • 3.4. Applications and economics
        • 3.5. Summary
        • Acronyms
      • 4. Gas-cooled fast reactors
        • 4.1. Rationale and generational research and development bridge
        • 4.2. Gas-cooled fast reactor technology
        • 4.3. Conclusions
      • 5. Sodium-cooled fast reactor
        • 5.1. Introduction
        • 5.2. Development history
        • 5.3. System characteristics
        • 5.4. Safety issues
        • 5.5. Future trends and key challenges
      • 6. Lead-cooled fast reactor
        • 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. Future trends
        • Sources of further information
        • Nomenclature
      • 7. Molten salt fast reactors
        • 7.1. Introduction
        • 7.2. The molten salt fast reactor concept
        • 7.3. Fuel salt chemistry and material issues
        • 7.4. Molten salt fast reactor fuel cycle scenarios
        • 7.5. Safety issues
        • 7.6. Concept viability: issues and demonstration steps
        • 7.7. Conclusion and perspectives
        • Nomenclature
      • 8. Super-critical water-cooled reactors
        • 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. Future trends
        • Acronyms
        • Nomenclature
    • Part Two. Current status of Generation IV activities in selected countries
      • Preface to Part Two
      • 9. Generation IV: USA
        • 9.1. Generation IV program evolution in the United States
        • 9.2. Energy market in the United States and the potential role of Generation IV systems: electricity, process heat, and waste management
        • 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. Deployment perspectives for Generation IV systems in the United States and deployment schedule
        • 9.6. Conclusions
        • Abbreviations
      • 10. Euratom research and training program in Generation-IV systems: Breakthrough technologies to improve sustainability, safety and reliability, socioeconomics, and proliferation resistance
        • 10.1. Background: Euratom (nuclear fission research and training) within the Energy Union (European Union energy mix policy)
        • 10.2. Generation-I, -II, -III, and -IV of nuclear fission reactors: research, development, and continuous improvement for more than five decades
        • 10.3. “Goals for Generation-IV nuclear energy systems” and “technology roadmap” for the six GIF systems (2002 and 2013)
        • 10.4. “European sustainable nuclear industrial initiative” and Euratom research and training program in fast neutron reactor systems
        • NB: Historical reminder about the “European fast reactor” project (1984–93)
        • 10.5. Sustainability (efficient resource utilization and minimization of radioactive waste)
        • 10.6. Safety and reliability (maximum safety performance through design, technology, regulation, and culture)
        • 10.7. Socioeconomics (economic advantage over other energy sources and better governance structure in energy decision-making process)
        • 10.8. Proliferation resistance and physical protection (protection against all kinds of terrorism)
        • 10.9. Conclusion: a new way of “developing/teaching science,” closer to the end-user needs of the 21-st century (society and industry)
        • Nomenclature
        • Appendix: Tentative training scheme for preconceptual Generation-IV design engineers (knowledge, skills, attitudes)
      • 11. Generation IV concepts: Japan
        • 11.1. Introduction
        • 11.2. JSFR design and its key innovative technologies
        • 11.3. Update of the Japan sodium-cooled fast reactor design with lessons learned from the Fukushima-Daiichi accident
        • 11.4. Concluding remarks
      • 12. Generation IV concepts: USSR and Russia
        • 12.1. Introduction
        • 12.2. History of the Soviet fast reactor program
        • 12.3. Sodium fast reactors
        • 12.4. Heavy liquid metal reactors
        • 12.5. Supercritical water reactor
        • 12.6. Conclusion
        • Nomenclature
      • 13. Generation IV concepts in Korea
        • 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
        • Acronyms
      • 14. Generation IV concepts: China
        • 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
        • Nomenclature
      • 15. Generation IV concepts: India
        • 15.1. Introduction
        • 15.2. Advanced heavy water reactors
        • 15.3. High-temperature reactors
        • 15.4. Fast breeder reactor
        • 15.5. Molten salt reactors
        • 15.6. Conclusions
        • Nomenclature
    • Part Three. Related topics to Generation IV nuclear reactor concepts
      • Preface to Part Three
      • 16. The safety of advanced reactors
        • 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 research and development for advanced reactors
        • 16.9. Natural-circulation loop and parallel channel thermal-hydraulics
        • 16.10. Literature review
        • 16.11. Modeling natural-circulation loops
        • 16.12. Conclusions
        • Nomenclature
        • Greek symbols
        • Nondimensional numbers
        • Subscripts
        • Acronyms and abbreviations
      • 17. Nonproliferation for advanced reactors: Political and social aspects
        • 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
        • Appendix 1: Euratom
        • Appendix 2: The 1997 IAEA additional protocol at a glance
        • Acronym
      • 18. Thermal aspects of conventional and alternative fuels
        • 18.1. Introduction
        • 18.2. Metallic fuels
        • 18.3. Ceramic fuels
        • 18.4. Hydride fuels
        • 18.5. Composite fuels
      • 19. Hydrogen cogeneration with Generation IV nuclear power plants
        • 19.1. Introduction
        • 19.2. Hydrogen review
        • 19.3. Hydrogen production methods
        • 19.4. Thermochemical cycles for hydrogen production
        • 19.5. Hydrogen cogeneration with Generation IV reactors
        • 19.6. Conclusions
      • 20. Advanced small modular reactors
        • 20.1. Introduction
        • 20.2. Early designs of small modular reactors
        • 20.3. Nuclear reactors
        • 20.4. Reactor coolant system components
        • 20.5. Fuels
        • 20.6. Containment
        • 20.7. Emergency core cooling system
        • 20.8. Economic and financing evaluation
        • 20.9. Security of small modular reactors
        • 20.10. Flexibility of small modular reactors
        • 20.11. Conclusions and future trends
        • Abbreviations
    • Appendix A1. Additional materials (schematics, layouts, T–s diagrams, basic parameters, and photos) on thermal and nuclear power plants
    • Appendix A2. Comparison of thermophysical properties of reactor coolants
    • Appendix A3. Thermophysical properties of fluids at subcritical and critical/supercritical conditions
    • Appendix A4. Heat transfer and pressure drop in forced convection to fluids at supercritical pressures
    • Appendix A5. World experience in nuclear steam reheat
    • Appendix A6. Comparison of thermophysical properties of selected gases at atmospheric pressure
    • Appendix A7. Supplementary tables
    • Appendix A8. Unit conversion
    • Index

Product details

  • No. of pages: 940
  • Language: English
  • Copyright: © Woodhead Publishing 2016
  • Published: June 9, 2016
  • Imprint: Woodhead Publishing
  • eBook ISBN: 9780081001622
  • Hardcover ISBN: 9780081001493

About the Editor

Igor Pioro

Professor Igor Pioro is an internationally recognized scientist within areas of nuclear engineering. He is author/co-author of 367 publications including 9 technical books, 15 chapters in technical books, 76 papers in refereed journals, 198 papers in refereed proceedings of international and national conferences and symposiums, 26 patents and inventions, and 43 major technical reports.

Professor Pioro graduated from the National Technical University of Ukraine/Kiev Polytechnic Institute with Master of Applied Science in Thermal Physics in 1979. After that, he worked in various positions, including an engineer, senior scientist, deputy director, professor, director of the graduate program in nuclear engineering, and associate dean. Currently, he is associated with the Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology (Canada).

Professor Pioro is a Founding Editor of the ASME Journal of Nuclear Engineering and Radiation Science (from 2014) and an Associate Editor of the ASME Journal of Engineering for Gas Turbines & Power. He was a Chair of the Executive Committee of the Nuclear Engineering Division of the ASME (2011-2012) and a Chair of the International Conference On Nuclear Engineering (ICONE20-POWER2012).

Professor Pioro has received many international and national awards and certificates of appreciation including an Honorary Doctor’s degree from the National Technical University of Ukraine “Kiev Polytechnic Institute” (2013); The Canadian Nuclear Society (CNS) Education and Communication Award (2011); The UOIT Research Excellence Award (2011); and the ICONE Award from the American Society of Mechanical Engineers (ASME) (2009).

Affiliations and Expertise

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

Ratings and Reviews

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  • DonaldBingaman Tue Sep 03 2019

    Generation IV Nuclear Power backgrounder

    An extremely comprehensive review of global efforts to revive the best shot we have at generating electrical power for 10 billion people with turning the Earth’s atmosphere into that of Venus with unacceptable CO2 concentrations. Highly recommended to understand a global systems engineering approach to solving an existential threat to mankind from global warming.

  • Ionut P. Thu Dec 28 2017

    Preparing the future

    A comprehensive book that prepares the reader for a very real and round the corner future. As a professor I recommend it to both old people in the field and especially to the young ones.