<p>This text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intende
Thermal-Hydraulic Analysis of Nuclear Reactors
β Scribed by Bahman Zohuri (auth.)
- Publisher
- Springer International Publishing
- Year
- 2017
- Tongue
- English
- Leaves
- 845
- Edition
- 2
- Category
- Library
No coin nor oath required. For personal study only.
β¦ Synopsis
This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors.
Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.
β¦ Table of Contents
Front Matter....Pages i-xxviii
An Introduction to Thermal-Hydraulic Aspects of Nuclear Power Reactors....Pages 1-28
Thermodynamics....Pages 29-76
Transport Properties....Pages 77-114
General Conservation Equations....Pages 115-146
Laminar Incompressible Forced Convection....Pages 147-221
Turbulent Forced Convection....Pages 223-277
Compressible Flow....Pages 279-305
Conduction Heat Transfer....Pages 307-321
Forced Convection Heat Transfer....Pages 323-345
Natural or Free Convection....Pages 347-375
Mass Transfer....Pages 377-393
Thermal Radiation....Pages 395-421
Multiphase Flow Dynamics....Pages 423-454
Convective Boiling....Pages 455-499
Thermal Stress....Pages 501-522
Combined Cycle-Driven Efficiency in Nuclear Power Plant....Pages 523-552
Heat Exchangers....Pages 553-589
Analysis of Reactor Accident....Pages 591-606
Probabilistic Risk Assessment....Pages 607-648
Nuclear Power Plants....Pages 649-689
Nuclear Fuel Cycle....Pages 691-712
The Economic Future of Nuclear Power....Pages 713-738
Safety, Waste Disposal, Containment, and Accidents....Pages 739-746
Back Matter....Pages 747-835
β¦ Subjects
Nuclear Energy;Engineering Thermodynamics, Heat and Mass Transfer;Appl.Mathematics/Computational Methods of Engineering;Engineering Fluid Dynamics
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