
Nuclear Systems Volume II
Elements of Thermal Hydraulic Design
- 666 pages
- English
- ePUB (mobile friendly)
- Available on iOS & Android
Nuclear Systems Volume II
Elements of Thermal Hydraulic Design
About this book
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.
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Information
Table of contents
- Cover
- Half Title Page
- Title Page
- Copyright Page
- Dedication
- Table of Contents
- Preface
- Acknowledgments
- Authors
- Chapter 1 Formulation of the Reactor Thermal Hydraulic Design Problem
- Chapter 2 Scaling of Two-Phase Flows in Complex Nuclear Reactor Systems
- Chapter 3 Single, Heated Channel Transient Analysis
- Chapter 4 Multiple Heated Channels Connected Only at Plena
- Chapter 5 Analysis of Interacting Channels by the Porous Media Approach
- Chapter 6 Analysis of Interacting Channels by the Subchannel Approach
- Chapter 7 Flow Loops
- Chapter 8 Steady State and Transient Analysis of Centrifugal Pumps
- Chapter 9 Thermal Analysis of Pressurizers
- Chapter 10 Thermal Analysis of Containments
- Chapter 11 Thermal Analysis of Steam Generators and Condensers
- Chapter 12 Fundamentals of Reactor Transient Simulation
- Chapter 13 Treatment of Uncertainties in Reactor Thermal Analysis
- Appendix A: Selected Nomenclature
- Appendix B: Physical and Mathematical Constants
- Appendix C: Unit Systems
- Appendix D: Mathematical Tables
- Appendix E: Thermodynamic Properties
- Appendix F: Thermophysical Properties of Some Substances
- Appendix G: Dimensionless Groups of Fluid Mechanics and Heat Transfer
- Appendix H: Multiplying Prefixes
- Appendix I: List of Elements
- Appendix J: Square and Hexagonal Rod Array Dimensions
- Appendix K: Parameters for Typical BWR-5 and PWR Reactors
- Appendix L: Discretization of Lumped Parameter Conservation Equations
- Appendix M: Proof of Local Volume-Averaging Theorems of Chapter 5
- Index