Thermal-hydraulic analysis of nuclear reactors
著者
書誌事項
Thermal-hydraulic analysis of nuclear reactors
Springer, c2015
大学図書館所蔵 全2件
内容説明・目次
内容説明
This 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. 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. 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.
This book also:
Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, beginning 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
Reinforces fundamentals of fluid dynamics and heat transfer; thermal and hydraulic analysis of nuclear reactors, two-phase flow and boiling, compressible flow, stress analysis, and energy conversion methods
Includes detailed appendices that cover metric and English system units and conversions, detailed steam and gas tables, heat transfer properties, and nuclear reactor system descriptions
目次
An Introduction to Thermal Hydraulic Aspects of Nuclear Power Reactors.- Thermodynamics.- Transport Properties.- General Conservation Equations.- Laminar Incompressible Forced Convection.- Turbulent Forced Convection.- Compressible Flow.- Conduction Heat Transfer.- Forced Convection Heat Transfer.- Natural or Free Convection.- Mass Transfer.- Thermal Radiation.- Multi-Phase Flow Dynamics.- Convective Boiling.- Thermal Stress.- Heat Exchangers.- Analysis of Reactor Accident.- Probabilistic Risk Assessment.- Nuclear Power Plants.- Nuclear Fuel Cycle.- The Economic Future of Nuclear Power.- Safety, Waste Disposal, Containment, and Accidents.- Appendix A: Table and Graphs Compilations.- Appendix B: Physical Property Tables.- Appendix C: Units, Dimensions and Conversion Factors.- Appendix D: Physical Properties.- Appendix E: Fluid Property Data.- Appendix F: Basic Equations.
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