1st Edition

Sodium Fast Reactors with Closed Fuel Cycle

    901 Pages
    by CRC Press

    904 Pages 44 Color & 675 B/W Illustrations
    by CRC Press

    Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world. Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book:

    • Offers in-depth coverage of reactor physics, materials, design, safety analysis, validations, engineering, construction, and commissioning aspects
    • Features a special chapter on allied sciences to highlight advanced reactor core materials, specialized manufacturing technologies, chemical sensors, in-service inspection, and simulators
    • Addresses design essentials with a focus on reactor assembly including core and coolant circuits, fuel handling, instrumentation and control, energy conversion, and containment systems
    • Provides design codes and standards with sufficient background information to ensure a solid understanding of the underlying mechanics
    • Supplies guidelines for concept selection, design, analysis, and validation

    Sodium Fast Reactors with Closed Fuel Cycle is a valuable reference for industry professionals involved in the construction of fast-reactor power plants, as well as graduate-level engineering students of the design and development of sodium-cooled fast-reactor systems and components.

    BASIS AND CONCEPTS
    Nuclear Fission and Breeding

    Introduction
    About the Neutron
    Nucleus Stability
    Energy from Fission
    Fission Neutrons and Energy Spectrum
    Chain Reaction
    Fissile and Fertile Materials
    About Breeding
    Working of Nuclear Reactors
    Reactor Control and Safety: Reactor Physics
    References
    Fast Spectrum Reactor vis-à-vis Pressurized Water Reactors
    Introduction
    Neutronic Characteristics
    Safety Characteristics
    Geometric Features of Core
    References
    Description of a Fast Spectrum Reactor
    Introduction
    Core and Reactor Assembly
    Main Heat Transport System
    Component Handling
    Steam-Water System
    Electrical Power Systems
    Instrumentation and Control
    Unique Worthiness of SFR
    Introduction
    Uranium Utilization in the Open Fuel Cycle Mode
    Uranium Utilization in the Closed Fuel Cycle Mode
    Fuel Utilization in the Fast Breeder Reactor: A Case Study
    High-Level Radioactive Waste Management and Environmental Issues
    Minor Actinide Burning Design Concepts
    Typical Minor Actinide Burning Scenario in Fast Spectrum Reactors (FSRs)
    References
    Design Objectives for the Efficient Use of Natural Uranium and Plutonium
    Introduction
    Growth
    Performance and Fuel Consumption Aspects
    References
    Prospect of Various Types of FSRs
    Introduction
    Sodium-Cooled Fast Reactors
    Lead-Cooled Fast Reactors
    Molten Salt Reactors
    Gas-Cooled Fast Reactors
    Comparison of Advanced Fast Reactors with SFRs
    Fast Reactors That Evolved Post-Fukushima
    References
    DESIGN OF SODIUM FAST REACTORS
    Choice of Materials and Their Performance
    Introduction
    Fuel
    Core Structural Materials
    Reactor Structures
    Coolant
    References
    System and Components
    Introduction
    Reactor Core
    Nuclear Steam Supply System
    Reactor Mechanisms
    Instrumentation and Control System
    Energy Conversion Systems
    References
    Design Basis
    Introduction
    Failure Modes
    Codes and Standards
    Design Criteria for the Aspects Not Covered in RCC-MR/ASME
    Thermal Hydraulic Design Criteria
    References
    Design Validations
    Introduction
    Structural Analysis Codes and Structural Design Methodology
    Thermal Hydraulic Codes
    Large-Scale Experimental Validations
    Experimental Facilities for Qualification of SFR Components in India
    Appendix A: 23-Parameter Chaboche Viscoplastic Model
    Appendix B: 20-Parameter Viscoplastic Model for 9Cr-1Mo Steel
    References
    Design Analysis and Methods
    Introduction
    Reactor Physics
    Thermal Hydraulics
    Structural Mechanics Analysis of Special Problems Relevant to SFR
    References
    SAFETY
    Safety Principles and Philosophy
    Introduction
    Inherent and Engineered Safety Features
    Operation Simplicity
    Radioactivity Release
    References
    Safety Criteria and Basis
    Introduction
    Generic Features of Fast Reactors to Be Addressed in the Safety Criteria
    Safety Issues Related to Sodium to Be Addressed in the Safety Criteria
    IAEA and Other International Safety Standards
    Safety Criteria for SFR: A Few Highlights
    Evolving Trends
    References
    Event Analysis
    Introduction
    Categorization of Events: Basis, Definition, and Explanation
    Methodology of Analysis
    Application of Plant Dynamics Study
    Summary
    References
    Severe Accident Analysis
    Introduction
    Initiating Events
    Severe Accident Scenarios
    Mechanical Energy Release and Consequences
    Postaccident Heat Removal
    Radiological Consequences
    References
    Sodium Safety
    Introduction
    Sodium Fire
    Sodium-Water Interaction
    Sodium-Concrete Interaction
    Sodium Fire Mitigation
    References
    Computer Codes and Validation
    Introduction
    Computer Codes for Severe Accident Analysis
    Computer Codes for the Mechanical Consequences
    Radioactive Release
    Sodium Fire Codes
    References
    Test Facilities and Programs
    Introduction
    Overview of Test Facilities Related to Core Safety
    Overview of Test Facilities Related to Molten Fuel-Coolant Interactions
    Test Facilities Related to Postaccident Heat Removal
    Test Facilities Related to Sodium Safety
    References
    Safety Experiments in Reactors
    Introduction
    Highlights of Safety Experiments
    Conclusion
    References
    Severe Accident Management
    Introduction
    Analysis for the Consequences of Design Extension Conditions: PFBR Case Study
    Improved Safety Features for Future SFRs
    Summary
    References
    Safety Analysis of PFBR: A Case Study
    Introduction
    Safety Features Incorporated in PFBR
    Severe Accident Analysis
    Assessment of Primary Containment Potential: Highlights of Analysis
    Sodium Leak through Top Shield and Containment Design Pressure
    Temperature and Pressure Rise in RCB
    Experimental Simulations
    Postaccident Heat Removal
    Site Boundary Dose
    Summary
    References
    CONSTRUCTION AND COMMISSIONING
    Specific Aspects of Civil Structures and Construction
    Introduction
    Specific Aspects of Reactor Buildings
    Challenges in Civil Construction
    References
    Manufacturing and Erection of Mechanical Components
    Specific Features of SFR Components w.r.t. Manufacturing and Erection
    Manufacturing and Erection Tolerances: Basis and Challenges
    Manufacturing Codes and Practices
    Summary
    References
    Illustrations from International SFRs
    Monju
    Super Phenix (SPX1)
    500 MWe Prototype Fast Breeder Reactor
    Summary
    References
    Commissioning Issues: Various Phases and Experiences
    Fast Flux Test Facility
    Phnéix
    BN-600 Reactor Commissioning Experience
    References
    INTERNATIONAL SFR EXPERIENCES
    SFR Program in Countries
    Introduction
    China
    France
    Germany
    India
    Japan
    Korea
    Russia
    United States
    References
    Feedback from Operating Experiences
    Introduction
    Design Concepts
    Material Behavior
    Safety Experience
    Operational Experience
    References
    Innovative Reactor Concepts for Future SFRs
    Motivation, Strategies, and Approaches
    INPRO: Closed Fuel Cycle with Fast Reactor (CNFC-FR)
    Concepts Specific to Nations
    References
    FUEL CYCLE FOR SFRS
    Fuel Cycle for SFRs
    Introduction
    Open and Closed Fuel Cycle
    Closed Fuel Cycle for Fast Reactors
    Fuel Types
    Performance Requirements of Fast Reactor Fuels
    Fuel Fabrication Processes
    Fuel Reprocessing
    Aqueous Reprocessing
    Special Features of Fast Reactor Fuel Reprocessing
    International Experience on Fast Reactor Fuel Reprocessing
    Pyrochemical Reprocessing
    Reprocessing of Carbide and Nitride Fuels
    Partitioning of Minor Actinides
    Waste Management for Fast Reactor Fuel Cycle
    Fast Reactors and Minor Actinides Burning
    Conclusion
    References
    DECOMMISSIONING ASPECTS
    Decommissioning Aspects
    Introduction
    Major Difference between Decommissioning Aspects of SFR and PWR
    Major Activities and Challenges Involved in Decommissioning of SFR
    Technological Strategies
    Experience and Feedback from Reactor Decommissioning
    Summary
    References
    Bibliography
    DOMAINS OF HIGH RELEVANCE TO SFR: TYPICAL EXAMPLES
    Material Science and Metallurgy
    Introduction
    Core Structural Materials
    Radiation-Resistant Steels
    Ion Beam Simulation
    Computer Simulation
    Compatibility of Clad Material with Coolant and Fuel
    Reactor Structural Materials
    Steam Generator Materials
    Hardfacing
    Summary
    References
    Chemical Sensors for Sodium Coolant Circuits
    Introduction
    Sensors for Monitoring Dissolved Hydrogen in Liquid Sodium
    Sensors for Monitoring Carbon Activity in Liquid Sodium
    Sensors for Monitoring Oxygen in Liquid Sodium Systems
    References
    Robotics, Automation, and Sensors
    Introduction
    In-Service Inspection of Components of Fast Breeder Reactor
    Remote Handing Tools and Robotic Devices for Nuclear Fuel Cycle Facilities
    Sensors for Robotics and Automation
    Summary
    References
    Operator Training Simulators for Fast Breeder Reactors
    Introduction
    Types of Simulators
    Operator Training Simulator
    Basic Simulator Model
    Design and Development of Training Simulator
    Integration and Performance Testing
    Verification and Validation of Training Simulator
    Implementation
    Configuration Management of Training Simulator
    Reference Standards
    ECONOMICS OF SFRS WITH A CLOSED FUEL CYCLE
    Economics of SFRs with a Closed Fuel Cycle
    Introduction
    Overall Perception on the Economy of SFRs
    Economic Assessment of International SFRs
    Future Directions: Technological Challenges
    Approach to Economics of SFR in India: A Case Study
    References

    Biography

    Baldev Raj, BE, Ph.D, served the Department of Atomic Energy, India over a 42-year period until 2011. As distinguished scientist and director, Indira Gandhi Centre of Atomic Research, Kalpakkam, India (IGCAR), he has advanced several challenging technologies, especially those related to the fast breeder test reactor and the prototype fast breeder reactor. Dr. Raj pioneered the application of nondestructive examination (NDE) for basic research using acoustic and electromagnetic techniques in a variety of materials and components. He is also responsible for realizing societal applications of NDE in areas related to cultural heritage and medical diagnosis. He is the author of more than 970 refereed publications, 70 books, and special journal volumes, and more than 20 contributions to encyclopedias and handbooks, as well as the owner of 29 patents. He is immediate past president, International Institute of Welding and President, Indian National Academy of Engineering. He assumed responsibilities as the director of the National Institute of Advanced Studies, Bangalore, India in September 2014. He is a fellow of all science and engineering academies in India; member of the German Academy of Sciences; honorary member of the International Medical Sciences Academy; member of the International Nuclear Energy Academy; vice president, nondestructive testing, Academia International; and president-elect of the International Council of Academies of Engineering and Technological Sciences.

    P. Chellapandi, BE (Hons.), M.Tech., Ph.D, is currently a distinguished scientist and director of the Reactor Design Group at the IGCAR. He specializes in reactor design, thermal hydraulics, structural mechanics, safety analysis, and experimental simulations. He is one of the key persons involved in the design and development activities of the 500 MWe prototype fast breeder reactor (PFBR) since its inception. He has contributed significantly for the PFBR over a wide spectrum of design, analysis, qualification, and research activities, also involving academic and R&D institutions in the country. His current responsibilities include design of advanced oxide and metallic fast breeder reactors planned by the department. He is a senior professor at Homi Bhabha National Institute and has published about 130 journal papers. He is a fellow at the Indian National Academy of Engineering. He is the recipient of the Homi Bhabha Science and Technology Award; the Indian Nuclear Society Award; the Vasvik Award; the National Design Award in Mechanical Engineering from Institute of Electrical and Electronics Engineers; the Agni Award for Excellence in Self-Reliance from Defence Research and Development Organization; the Department of Atomic Energy (DAE) Group Achievement Award for the design, manufacture, and erection of PFBR reactor assembly components; and the Distinguished Alumnus Award from the Indian Institute of Technology, Chennai.

    P.R. Vasudeva Rao, B.Sc., Ph.D, is the director of the IGCAR and the General Services Organization at Kalpakkam, India. After graduating from Vivekananda College, Chennai, India, he joined the DAE in the 16th batch of Bhabha Atomic Research Centre training school. He was instrumental in the setting up of the Radiochemistry Laboratory at the IGCAR. He is an expert in the area of fast reactor fuel cycle, especially the back-end fuel cycle. He is a recipient of the Indian Nuclear Society Award (2007) for his contributions to the area of nuclear fuel cycle technologies. He was selected for the Material Research Society of India (MRSI) medal lecture in 1998 and MRSI-ICSC Superconductivity and Materials Science Senior Award in 2011. He was also selected for the award of the Silver Medal by the Chemical Research Society of India in 2011. He is a senior professor at the Homi Bhabha National Institute. He has nearly 250 publications in peer-reviewed international journals. His areas of interest include the development of technologies for fast reactors and associated fuel cycles, actinide separations, and education in the field of chemical sciences.

    "…I think this book will be useful for students and post-graduate students having specializations in various areas of SFR technology. …Chapters include a lot of world experience related to SFR designing and construction and are well illustrated… I will be glad to have this book on my table."
    —Yury Ashurko, State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering (SSC RF-IPPE)

    "A comprehensive source book providing information about various aspects of fast reactors and their associated fuel cycles would be of significant value for experts, as well as for younger-generation professionals aspiring to take up challenging R&D programs in designing and building fast reactor systems. I am delighted that such a book on fast reactors has been made a reality by my colleagues, Dr. Baldev Raj, Dr. P. Chellapandi, and Dr. P.R. Vasudeva Rao. I congratulate them for their fine efforts in preparing this comprehensive treatise on this important subject."
    —R.K. Sinha, Secretary, Department of Atomic Energy and Chairman, Atomic Energy Commission, Mumbai, India

    "… provides authoritative information from a team that has recently built a fast reactor. … covers the full fuel cycle for sodium-cooled fast reactors and includes valuable construction experience. … a very important topic and the inclusion of the entire fuel cycle (including recycling) should make this book very valuable to the fast reactor professional community."
    —Dr. Alan E. Waltar, Director, Nuclear Energy, Pacific Northwest National Lab, Richland, Washington, USA (Retired) and Professor and Head, Nuclear Engineering, Texas A&M University, College Station, USA (Retired)