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Full Description
This book provides advanced coverage of a wide variety of thermal fluid systems and technologies in nuclear power plants, including discussions of the latest reactor designs and their thermal/fluid technologies. Beyond the thermal hydraulic design and analysis of the core of a nuclear reactor, the book covers other components of nuclear power plants, such as the pressurizer, containment, and the entire primary coolant system.
Placing more emphasis on the appropriate models for small-scale resolution of the velocity and temperature fields through computational fluid mechanics, the book shows how this enhances the accuracy of predicted operating conditions in nuclear plants. It introduces considerations of the laws of scaling and uncertainty analysis, along with a wider coverage of the phenomena encountered during accidents.
FEATURES
Discusses fundamental ideas for various modeling approaches for the macro- and microscale flow conditions in reactors
Covers specific design considerations, such as natural convection and core reliability
Enables readers to better understand the importance of safety considerations in thermal engineering and analysis of modern nuclear plants
Features end-of-chapter problems
Includes a solutions manual for adopting instructors
This book serves as a textbook for advanced undergraduate and graduate students taking courses in nuclear engineering and studying thermal/hydraulic systems in nuclear power plants.
Contents
1. Formulation of the Reactor Thermal Hydraulic Design Problem 2. Scaling of Two-Phase Flows in Complex Nuclear Reactor Systems 3. Single, Heated Channel Transient Analysis 4. Multiple Heated Channels Connected Only at Plena 5. Analysis of Interacting Channels by the Porous Media Approach 6. Analysis of Interacting Channels by the Subchannel Approach 7. Flow Loops 8. Steady State and Transient Analysis of Centrifugal Pumps 9. Thermal Analysis of Pressurizers 10. Thermal Analysis of Containments 11. Thermal Analysis of Steam Generators and Condensers 12. Fundamentals of Reactor Transient Simulation 13. Treatment of Uncertainties in Reactor Thermal Analysis
