Title: Nuclear Reactor Thermal Hydraulics : An Introduction to Nuclear Heat Transfer and Fluid Flow Author: Robert E. Masterson ISBN: 1138035378 / 9781138035379 Format: Hard Cover Pages: 1354 Publisher: CRC Press Year: 2019 Availability: 2 to 3 weeks
Description
Contents
Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students. A complete Solutions Manual is available for professors adopting the text.
Preface
Chapter 1 : Nuclear Power in the World Today Chapter 2 : The Pressurized Water Reactor Chapter 3 : The Boiling Water Reactor Chapter 4 : Fast Reactors, Gas Reactors, and Military Reactors Chapter 5 : Thermal Energy Production in Nuclear Power Plants Chapter 6 : The Laws of Thermodynamics Chapter 7 : Thermodynamic Properties and Equations of State Chapter 8 : The Nuclear Steam Supply System and Reactor Heat Exchangers Chapter 9 : Reactor Thermal Cycles Chapter 10 : The Laws of Nuclear Heat Transfer Chapter 11 : Heat Removal from Nuclear Fuel Rods Chapter 12 : Time-Dependent Nuclear Heat Transfer Chapter 13 : Nuclear Reactor Fluid Mechanics Chapter 14 : Fluid Statics and Fluid Dynamics Chapter 15 : The Conservation Equations of Fluid Mechanics Chapter 16 : Single-Phase Flow in Nuclear Power Plants Chapter 17 : Laminar and Turbulent Flows with Friction Chapter 18 : Core and Fuel Assembly Fluid Flow Chapter 19 : Reactor Coolants, Coolant Pumps, and Power Turbines Chapter 20 : Fundamentals of Single-Phase Heat Transfer in Nuclear Power Plants Chapter 21 : Correlations for Single-Phase Nuclear Heat Transfer Chapter 22 : Natural Convection in Nuclear Power Plants Chapter 23 : Fundamentals of Two-Phase Flow in Nuclear Power Plants Chapter 24 : Two-Phase Nuclear Heat Transfer Chapter 25 : Heat Transfer Correlations for Advanced Two-Phase Nuclear Heat Transfer Chapter 26 : Core Temperature Fields Chapter 27 : Nuclear Hot Channel Factors, the Critical Heat Flux, and the DNBR Chapter 28 : Particle Transport and Entrainment during Reactor Accidents Chapter 29 : Equilibrium and Non-Equilibrium Flows, Compressible Flows, and Choke Flows Chapter 30 : Reactor Accidents, DBAs, and LOCAs Chapter 31 : Flow Oscillations, Density Waves, and Hydrodynamic Instabilities Chapter 32 : Containment Buildings and Their Function Chapter 33 : Thermal Design Limits, Operating Limits, and Safety Limits Chapter 34 : Response of a Containment Building to a Reactor LOCA