Sodium fast reactors with closed fuel cycle

<P><STRONG>BASIS AND CONCEPTS<BR>Nuclear Fission and Breeding</STRONG><BR>Introduction<BR>About the Neutron<BR>Nucleus Stability<BR>Energy from Fission<BR>Fission Neutrons and Energy Spectrum<BR>Chain Reaction<BR>Fissile and Fertile Materials<BR>About Breeding<BR>Working of Nuclear Reactors<BR>Reactor Control and Safety: Reactor Physics<BR>References<BR><STRONG>Fast Spectrum Reactor vis-à-vis Pressurized Water Reactors</STRONG><BR>Introduction<BR>Neutronic Characteristics<BR>Safety Characteristics<BR>Geometric Features of Core<BR>References<BR><STRONG>Description of a Fast Spectrum Reactor</STRONG><BR>Introduction<BR>Core and Reactor Assembly<BR>Main Heat Transport System<BR>Component Handling<BR>Steam-Water System<BR>Electrical Power Systems<BR>Instrumentation and Control<BR><STRONG>Unique Worthiness of SFR</STRONG><BR>Introduction<BR>Uranium Utilization in the Open Fuel Cycle Mode<BR>Uranium Utilization in the Closed Fuel Cycle Mode<BR>Fuel Utilization in the Fast Breeder Reactor: A Case Study<BR>High-Level Radioactive Waste Management and Environmental Issues<BR>Minor Actinide Burning Design Concepts<BR>Typical Minor Actinide Burning Scenario in Fast Spectrum Reactors (FSRs)<BR>References<BR><STRONG>Design Objectives for the Efficient Use of Natural Uranium and Plutonium</STRONG><BR>Introduction<BR>Growth<BR>Performance and Fuel Consumption Aspects<BR>References<BR><STRONG>Prospect of Various Types of FSRs</STRONG><BR>Introduction<BR>Sodium-Cooled Fast Reactors<BR>Lead-Cooled Fast Reactors<BR>Molten Salt Reactors<BR>Gas-Cooled Fast Reactors<BR>Comparison of Advanced Fast Reactors with SFRs<BR>Fast Reactors That Evolved Post-Fukushima<BR>References<BR><STRONG>DESIGN OF SODIUM FAST REACTORS</STRONG><BR><STRONG>Choice of Materials and Their Performance</STRONG><BR>Introduction<BR>Fuel<BR>Core Structural Materials<BR>Reactor Structures<BR>Coolant<BR>References<BR><STRONG>System and Components</STRONG><BR>Introduction<BR>Reactor Core<BR>Nuclear Steam Supply System<BR>Reactor Mechanisms<BR>Instrumentation and Control System<BR>Energy Conversion Systems<BR>References<BR><STRONG>Design Basis</STRONG><BR>Introduction<BR>Failure Modes<BR>Codes and Standards<BR>Design Criteria for the Aspects Not Covered in RCC-MR/ASME<BR>Thermal Hydraulic Design Criteria<BR>References<BR><STRONG>Design Validations</STRONG><BR>Introduction<BR>Structural Analysis Codes and Structural Design Methodology<BR>Thermal Hydraulic Codes<BR>Large-Scale Experimental Validations<BR>Experimental Facilities for Qualification of SFR Components in India<BR>Appendix A: 23-Parameter Chaboche Viscoplastic Model<BR>Appendix B: 20-Parameter Viscoplastic Model for 9Cr-1Mo Steel<BR>References<BR><STRONG>Design Analysis and Methods</STRONG><BR>Introduction<BR>Reactor Physics<BR>Thermal Hydraulics<BR>Structural Mechanics Analysis of Special Problems Relevant to SFR<BR>References<BR><STRONG>SAFETY</STRONG><BR><STRONG>Safety Principles and Philosophy</STRONG><BR>Introduction<BR>Inherent and Engineered Safety Features<BR>Operation Simplicity<BR>Radioactivity Release<BR>References<BR><STRONG>Safety Criteria and Basis</STRONG><BR>Introduction<BR>Generic Features of Fast Reactors to Be Addressed in the Safety Criteria<BR>Safety Issues Related to Sodium to Be Addressed in the Safety Criteria<BR>IAEA and Other International Safety Standards<BR>Safety Criteria for SFR: A Few Highlights<BR>Evolving Trends<BR>References<BR><STRONG>Event Analysis</STRONG><BR>Introduction<BR>Categorization of Events: Basis, Definition, and Explanation<BR>Methodology of Analysis<BR>Application of Plant Dynamics Study<BR>Summary<BR>References<BR><STRONG>Severe Accident Analysis</STRONG><BR>Introduction<BR>Initiating Events<BR>Severe Accident Scenarios<BR>Mechanical Energy Release and Consequences<BR>Postaccident Heat Removal<BR>Radiological Consequences<BR>References<BR><STRONG>Sodium Safety</STRONG><BR>Introduction<BR>Sodium Fire<BR>Sodium-Water Interaction<BR>Sodium-Concrete Interaction<BR>Sodium Fire Mitigation<BR>References<BR><STRONG>Computer Codes and Validation</STRONG><BR>Introduction<BR>Computer Codes for Severe Accident Analysis<BR>Computer Codes for the Mechanical Consequences<BR>Radioactive Release<BR>Sodium Fire Codes<BR>References<BR><STRONG>Test Facilities and Programs</STRONG><BR>Introduction<BR>Overview of Test Facilities Related to Core Safety<BR>Overview of Test Facilities Related to Molten Fuel-Coolant Interactions<BR>Test Facilities Related to Postaccident Heat Removal<BR>Test Facilities Related to Sodium Safety<BR>References<BR><STRONG>Safety Experiments in Reactors</STRONG><BR>Introduction<BR>Highlights of Safety Experiments<BR>Conclusion<BR>References<BR><STRONG>Severe Accident Management</STRONG><BR>Introduction<BR>Analysis for the Consequences of Design Extension Conditions: PFBR Case Study<BR>Improved Safety Features for Future SFRs<BR>Summary<BR>References<BR><STRONG>Safety Analysis of PFBR: A Case Study</STRONG><BR>Introduction<BR>Safety Features Incorporate