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Nuclear Reactor Thermal Hydraulics : An Introduction to Nuclear Heat Transfer and Fluid Flow

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

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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.

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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

Index

 

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