Sodium fast reactors with closed fuel cycle. (2014)

• Record Type: Book
• Further Information: Note: Baldev Raj, P. Chellapandi, P.R. Vasudeva Rao.
• Authors: Raj, Baldev, 1947-2018; Chellapandi, P; Vasudeva Rao, P. R
• Contents: 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
• Edition: 1st
• Publisher Details: Boca Raton : CRC Press
• Publication Date: 2014
• Extent: 1 online resource, illustrations (black and white)
• Subjects: 621.4834; Sodium cooled reactors; Fast reactors
• Languages: English
• ISBNs: 9781466587694
• Related ISBNs: 9781466587670
• Notes: Note: Description based on CIP data; item not viewed.
• Access Rights: Legal Deposit; Only available on premises controlled by the deposit library and to one user at any one time; The Legal Deposit Libraries (Non-Print Works) Regulations (UK).
• Access Usage: Restricted: Printing from this resource is governed by The Legal Deposit Libraries (Non-Print Works) Regulations (UK) and UK copyright law currently in force.