Thermal-hydraulic analysis of nuclear reactors
著者
書誌事項
Thermal-hydraulic analysis of nuclear reactors
Springer, 2017
2nd ed
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注記
Includes bibliographical references and index
内容説明・目次
内容説明
This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors.
Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.
目次
1. An Introduction to Thermal Hydraulic Aspects of Nuclear Power Reactors2. Thermodynamics3. Transport Properties4. General Conservation Equations5. Laminar Incompressible Forced Convection6. Turbulent Forced Convection7. Compressible Flow8. Conduction Heat Transfer9. Forced Convection Heat Transfer10. Natural or Free Convection11. Mass Transfer12. Thermal Radiation13. Multi-Phase Flow Dynamics14. Convective Boiling15. Thermal Stress16. Combined Cycle Driven Efficiency in Nuclear Power Plant17. Heat Exchangers18. Analysis of Reactor Accident19. Probabilistic Risk Assessment20. Nuclear Power Plants21. Nuclear Fuel Cycle22. The Economic Future of Nuclear Power23. Safety, Waste Disposal, Containment, and AccidentssAppendix A: Table and Graphs CompilationsAppendix B: Physical Property TablesAppendix C: Units, Dimensions and Conversion FactorsAppendix D: Physical PropertiesAppendix E: Fluid Property DataAppendix F: Basic EquationsIndex
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