Masterson R.E. Nuclear Reactor Thermal Hydraulics: An Introduction to Nuclear Heat Transfer and Fluid Flow

CRC Press, Taylor & Francis Group, 2020. — 1390 p. — ISBN13: 978-1-138-03537-9.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.Nuclear Power in the World Today
The Pressurized Water Reactor
The Boiling Water Reactor
Fast Reactors, Gas Reactors, and Military Reactors
Thermal Energy Production in Nuclear Power Plants
The Laws of Thermodynamics
Thermodynamic Properties and Equations of State
The Nuclear Steam Supply System and Reactor Heat Exchangers
Reactor Thermal Cycles
The Laws of Nuclear Heat Transfer
Heat Removal from Nuclear Fuel Rods
Time-Dependent Nuclear Heat Transfer
Nuclear Reactor Fluid Mechanics
Fluid Statics and Fluid Dynamics
The Conservation Equations of Fluid Mechanics
Single-Phase Flow in Nuclear Power Plants
Laminar and Turbulent Flows with Friction
Core and Fuel Assembly Fluid Flow
Reactor Coolants, Coolant Pumps, and Power Turbines
Fundamentals of Single-Phase Heat Transfer in Nuclear Power Plants
Correlations for Single-Phase Nuclear Heat Transfer
Natural Convection in Nuclear Power Plants
Fundamentals of Two-Phase Flow in Nuclear Power Plants
Two-Phase Nuclear Heat Transfer
Heat Transfer Correlations for Advanced Two-Phase Nuclear Heat Transfer
Core Temperature Fields
Nuclear Hot Channel Factors, the Critical Heat Flux, and the DNBR
Particle Transport and Entrainment during Reactor Accidents
Equilibrium and Non-Equilibrium Flows, Compressible Flows, and Choke Flows
Reactor Accidents, DBAs, and LOCAs
Flow Oscillations, Density Waves, and Hydrodynamic Instabilities
Containment Buildings and Their Function
Thermal Design Limits, Operating Limits, and Safety Limits
Response of a Containment Building to a Reactor LOCA
Appendixes
Unit Systems and Conversion Factors
Operating Conditions for Common Reactor Types
Reactor Coolants and Their Properties
Dimensionless Numbers Used in Nuclear Heat Transfer and Fluid Flow
Properties of Nuclear Fuel Assemblies
Properties of Subcooled Water
Properties of Saturated Water and Steam
Properties of Superheated Steam
Modern Thermal-Hydraulic Design Correlations
AP-1000 Design Parameters