Robert E Masterson

Nuclear Reactor Thermal Hydraulics

An Introduction to Nuclear Heat Transfer and Fluid Flow

• Gebundenes Buch

Produktbeschreibung

Nuclear Thermal Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal hydraulics, reflecting the latest technologies, reactor designs, and safety considerations.

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Produktdetails

• Verlag: CRC Press
• Seitenzahl: 1392
• Erscheinungstermin: 18. September 2019
• Englisch
• Abmessung: 261mm x 213mm x 60mm
• Gewicht: 2644g
• ISBN-13: 9781138035379
• ISBN-10: 1138035378
• Artikelnr.: 55982921

Autorenporträt

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.

Inhaltsangabe

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