Thermal-Hydraulic Analysis of Nuclear Reactors [electronic resource] /
Zohuri, Bahman.author.
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. • Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, from fundamentals to applications; • 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.
Includes bibliographical references at the end of each chapters and index.
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 -- Combined Cycle Driven Efficiency in Nuclear Power Plant -- 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 Accidentss -- 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 -- Index.
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. • Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, from fundamentals to applications; • 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.
Nuclear energy.
Thermodynamics.
Heat engineering.
Heat transfer.
Mass transfer.
Applied mathematics.
Engineering mathematics.
Fluid mechanics.
Nuclear Energy.
Engineering Thermodynamics, Heat and Mass Transfer.
Mathematical and Computational Engineering.
Engineering Fluid Dynamics.