1st Edition
Nuclear Reactor Thermal Hydraulics An Introduction to Nuclear Heat Transfer and Fluid Flow
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.
1. Nuclear Power in the World Today
2. The Pressurized Water Reactor
3. The Boiling Water Reactor
4. Fast Reactors, Gas Reactors, and Military Reactors
5. Thermal Energy Production in Nuclear Power Plants
6. The Laws of Thermodynamics
7. Thermodynamic Properties and Equations of State
8. The Nuclear Steam Supply System and Reactor Heat Exchangers
9. Reactor Thermal Cycles
10. The Laws of Nuclear Heat Transfer
11. Heat Removal from Nuclear Fuel Rods
12. Time-Dependent Nuclear Heat Transfer
13. Nuclear Reactor Fluid Mechanics
14. Fluid Statics and Fluid Dynamics
15. The Conservation Equations of Fluid Mechanics
16. Single-Phase Flow in Nuclear Power Plants
17. Laminar and Turbulent Flows with Friction
18. Core and Fuel Assembly Fluid Flow
19. Reactor Coolants, Coolant Pumps, and Power Turbines
20. Fundamentals of Single-Phase Heat Transfer in Nuclear Power Plants
21. Correlations for Single-Phase Nuclear Heat Transfer
22. Natural Convection in Nuclear Power Plants
23. Fundamentals of Two-Phase Flow in Nuclear Power Plants
24. Two-Phase Nuclear Heat Transfer
25. Heat Transfer Correlations for Advanced Two-Phase Nuclear Heat Transfer
26. Core Temperature Fields
27. Nuclear Hot Channel Factors, the Critical Heat Flux, and the DNBR
28. Particle Transport and Entrainment during Reactor Accidents
29. Equilibrium and Non-Equilibrium Flows, Compressible Flows, and Choke Flows
30. Reactor Accidents, DBAs, and LOCAs
31. Flow Oscillations, Density Waves, and Hydrodynamic Instabilities
32. Containment Buildings and Their Function
33. Thermal Design Limits, Operating Limits, and Safety Limits
34. Response of a Containment Building to a Reactor LOCA
Biography
Robert E. Masterson (1950-2020) held MS and PhD degrees in nuclear engineering from the Massachusetts Institute of Technology, and he worked for Westinghouse Nuclear Energy Systems. He was an Affiliate Professor of Nuclear Science and Engineering at Virginia Tech University in Blacksburg, Virginia. Dr. Masterson published extensively in the journals of the ANS and had over 20 years of experience in the field of nuclear science and engineering. He had an extensive background in the fields of reactor safety, reactor design and analysis, reactor thermal hydraulics, numerical analysis, reactor physics, reactor dynamics, nuclear medicine, and nuclear particle transport. He was a member of the American Nuclear Society. His first textbook with CRC Press, Nuclear Engineering Fundamentals: A Practical Perspective, was published in 2017.
