Sodium Fast Reactors with Closed Fuel Cycle
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Opis: Sodium Fast Reactors with Closed Fuel Cycle - P. R. Vasudeva Rao, P R Vasudeva Rao, P Chellapandi

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. "...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)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-a-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 Phneix 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


Szczegóły: Sodium Fast Reactors with Closed Fuel Cycle - P. R. Vasudeva Rao, P R Vasudeva Rao, P Chellapandi

Tytuł: Sodium Fast Reactors with Closed Fuel Cycle
Autor: P. R. Vasudeva Rao, P R Vasudeva Rao, P Chellapandi
Producent: CRC Press Inc.
ISBN: 9781466587670
Rok produkcji: 2015
Ilość stron: 901
Oprawa: Twarda
Waga: 1.77 kg


Recenzje: Sodium Fast Reactors with Closed Fuel Cycle - P. R. Vasudeva Rao, P R Vasudeva Rao, P Chellapandi
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Sodium Fast Reactors with Closed Fuel Cycle

, ,

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. "...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)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-a-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 Phneix 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

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Cena 773,00 PLN
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Szczegóły: Sodium Fast Reactors with Closed Fuel Cycle - P. R. Vasudeva Rao, P R Vasudeva Rao, P Chellapandi

Tytuł: Sodium Fast Reactors with Closed Fuel Cycle
Autor: P. R. Vasudeva Rao, P R Vasudeva Rao, P Chellapandi
Producent: CRC Press Inc.
ISBN: 9781466587670
Rok produkcji: 2015
Ilość stron: 901
Oprawa: Twarda
Waga: 1.77 kg


Recenzje: Sodium Fast Reactors with Closed Fuel Cycle - P. R. Vasudeva Rao, P R Vasudeva Rao, P Chellapandi

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