Molten salt reactors and integrated molten salt reactors : integrated power conversion /
Clasificación: | Libro Electrónico |
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Autor principal: | |
Formato: | Electrónico eBook |
Idioma: | Inglés |
Publicado: |
London :
Academic Press,
2021.
|
Temas: | |
Acceso en línea: | Texto completo |
Tabla de Contenidos:
- Front cover
- Half title
- Full tiel
- Copyright
- Dedication
- Contents
- About the Author
- Preface
- Acknowledgment
- Chapter 1
- Molten Salt Reactor History, From Past to Present
- 1.1 Introduction
- 1.2 Aircraft Nuclear Power Reactor Experiment
- 1.3 Molten Salt Reactor Experiment (MSRE)
- 1.4 Space-Based Nuclear Reactors
- 1.5 Sustainable Nuclear Energy
- 1.6 Prefiltration and Nonprefiltration nuclear reactors
- 1.7 Nuclear Safeguards
- 1.8 Safety by Physics Versus by Engineering
- 1.9 Criticality Issue of Nuclear Energy Systems Driven by MSRs
- 1.10 Denatured Molten Salt Reactor (DMSR)
- 1.11 MSR Pros and Cons
- 1.12 The Potential of the MSR Concept
- 1.13 Conclusions
- References
- Chapter 2
- Integral Molten Salt Reactor
- 2.1 Introduction
- 2.2 Integral Molten Salt Reactor (IMSR) Descriptions
- 2.3 Integral Molten Salt Reactor (IMSR) Design
- 2.4 Integral Molten Salt Safety Philosophy
- 2.5 Proliferation Defense
- 2.6 Safety and Security (Physical Protection)
- 2.7 Description of Turbine-Generator Systems
- 2.8 Electrical and Integrated and Circuit (I & amp
- C) Systems
- 2.9 Spent Fuel and Waste Management
- 2.10 Plant Layout
- 2.11 Plant Performance
- 2.12 Development Status of Technologies Relevant to the Nuclear Power Plant
- 2.13 Development Status and Planned Schedule
- 2.14 Coupling IMSR Technology with Hybrid Nuclear/Renewable Energy Systems
- 2.14.1 Thermal Storage and Desalination
- 2.14.2 H 2 from High Temperature Steam Electrolysis
- 2.14.3 Synthesized Transport Fuels
- 2.14.4 Ammonia Production Coupled to IMSR
- 2.14.5 Coupling IMSR Technology into Direct Reduction Steel with H 2
- 2.15 Conclusions
- References
- Chapter 3
- New Approach to Energy Conversion Technology
- 3.1 Introduction
- 3.2 Waste Heat Recovery
- 3.3 PCS Components.
- 3.3.1 Heat Exchangers
- 3.3.1.1 Recuperative HXs
- 3.3.1.1.1 Metallic Radiation Recuperator
- 3.3.1.1.2 Convective Recuperator
- 3.3.1.1.3 Hybrid Recuperator
- 3.3.1.1.4 Ceramic Recuperator
- 3.3.1.2 Regenerative HXs
- 3.3.1.3 Evaporative HXs
- 3.3.2 Compact HXs
- 3.4 Development of Gas Turbine
- 3.5 Turbomachinery
- 3.6 Heat Transfer Analysis
- 3.7 Combined-Cycle Gas Power Plant
- 3.8 Advanced Computational Materials Proposed for GEN IV Systems
- 3.9 Material Classes Proposed for GEN IV Systems
- 3.10 GEN IV Materials Challenges
- 3.11 GEN IV Materials Fundamental Issues
- 3.12 Capital Cost of Proposed GEN IV Reactors
- 3.12.1 Economic and Technical of Combined-Cycle Performance
- 3.12.2 Economic Evaluation Technique
- 3.12.3 Output Enhancement
- 3.12.3.1 Gas Turbine Inlet Air Cooling
- 3.12.3.2 Power Augmentation
- 3.13 Combined-Cycle PCS Driven GEN IV Nuclear Plant
- 3.13.1 Modeling the Brayton Cycle
- 3.13.2 Modeling the Rankine Cycle
- 3.13.3 Results
- References
- Chapter 4
- Advanced Power Conversion System Driven by Small Modular Reactors
- 4.1 Introduction
- 4.2 Currently Proposed Power Conversion Systems for SMRs
- 4.3 Advanced Air-Brayton Power Conversion Systems
- 4.4 Design Equations and Design Parameters
- 4.4.1 Reactors
- 4.4.2 Air Compressors and Turbines
- 4.4.3 Heat Exchanger
- 4.4.3.1 Primary Heat Exchangers-Sodium-to-Air, Molten Salt-to-Air
- 4.4.3.2 Economizer-Air to Water
- 4.4.3.3 Superheaters-Air to Steam
- 4.4.3.4 Condenser-Steam to Water
- 4.4.3.5 Recuperator-Air to Air
- 4.4.3.6 Intercooler-Water to Air
- 4.4.4 Pumps and Generators
- 4.4.5 Connections and Uncertainty
- 4.5 Predicted Performance of Small Modular NACC systems
- 4.6 Performance Variation of Small Modular NACC Systems.
- 4.7 Predicted Performance for Small Modular NARC Systems
- 4.8 Performance Variation of Small Modular NARC Systems
- 4.9 Predicted Performance for a Small Modular Intercooled NARC System
- 4.10 Performance Variation of Small Modular Intercooled NARC Systems
- 4.11 Conclusions
- References
- Chapter 5
- Advanced Nuclear Open Air-Brayton Cycles for Highly Efficient Power Conversion
- 5.1 Introduction
- 5.2 Background
- 5.3 Combined Cycle Feature
- 5.4 Typical Cycles
- 5.5 Analysis Methodology
- 5.6 Validation of Methodology
- 5.7 Modeling the Nuclear Combined Cycle
- 5.7.1 Nominal Results for Combined Cycle Model
- 5.7.2 Extension of Results for Peak Turbine Temperatures
- 5.8 Modeling the Nuclear Recuperated Cycle
- 5.8.1 Nominal Results for Recuperated Cycle Models
- 5.8.2 Nominal Results for Recuperated Cycle
- 5.9 Economic Impact
- 5.10 Conclusions
- References
- Chapter 6
- Heat pipe driven heat exchangers to avoid salt freezing and control tritium
- 6.1 Introduction
- 6.2 Heat transfer-the traditional application for heat pipes
- 6.3 Prevention of coolant salt freezing
- 6.4 Tritium capture
- 6.5 Reactor systems and heat pipes design requirements
- 6.5.1 Fluoride-salt-cooled high-temperature reactor
- 6.5.2 Salt-cooled fusion systems
- 6.5.3 Molten salt reactors
- 6.6 Salt reactor heat exchanger requirements
- 6.7 Heat pipe design and startup temperature
- 6.7.1 Choice of fluid
- 6.8 Heat transfer analysis
- 6.8.1 Heat pipe operation limits
- 6.8.1.1 Viscous limit
- 6.8.1.2 Entrainment limit
- 6.8.1.3 Boiling limit
- 6.8.1.4 Sonic limit
- 6.8.1.5 Wicking or capillary limit
- 6.8.2 Sodium heat pipe experience
- 6.9 Tritium control
- 6.10 Status of technology and path forward
- References.
- Chapter 7
- Salt cleanup and waste solidification for fission and fusion reactors
- 7.1 Introduction
- 7.2 Requirements
- 7.2.1 Reactor salt requirements
- 7.2.2 Molten salt separations requirements
- 7.2.3 Final waste form requirements
- 7.3 Separations
- 7.3.1 Distillation
- 7.3.2 Electrochemical separations
- 7.4 Conversion of salt wastes to high-quality waste forms
- 7.4.1 Conversion of halide wastes to iron phosphate gas
- 7.4.2 Conversion of halide wastes to borosilicate glass
- 7.5 Other considerations
- 7.6 Conclusions
- References
- Appendix A
- A combined cycle power conversion system for small modular LMFBR
- References
- APPENDIX B
- Direct reactor auxiliary cooling system (DRACS)
- References
- Appendix C
- Heat pipe general knowledge
- Appendix D
- Variable electricity and steam-cooled based load reactors
- References
- Appendix E
- Variable electricity and steam-cooled based load reactors
- References
- Index
- Back cover.