Nuclear Systems Volume II
eBook - ePub

Nuclear Systems Volume II

Elements of Thermal Hydraulic Design

  1. 666 pages
  2. English
  3. ePUB (mobile friendly)
  4. Available on iOS & Android
eBook - ePub

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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Yes, you can access Nuclear Systems Volume II by Neil E. Todreas,Mujid S. Kazimi,Mahmoud Massoud in PDF and/or ePUB format, as well as other popular books in Physical Sciences & Energy. We have over one million books available in our catalogue for you to explore.

Information

Publisher
CRC Press
Year
2021
Print ISBN
9781482239584

Table of contents

  1. Cover
  2. Half Title Page
  3. Title Page
  4. Copyright Page
  5. Dedication
  6. Table of Contents
  7. Preface
  8. Acknowledgments
  9. Authors
  10. Chapter 1 Formulation of the Reactor Thermal Hydraulic Design Problem
  11. Chapter 2 Scaling of Two-Phase Flows in Complex Nuclear Reactor Systems
  12. Chapter 3 Single, Heated Channel Transient Analysis
  13. Chapter 4 Multiple Heated Channels Connected Only at Plena
  14. Chapter 5 Analysis of Interacting Channels by the Porous Media Approach
  15. Chapter 6 Analysis of Interacting Channels by the Subchannel Approach
  16. Chapter 7 Flow Loops
  17. Chapter 8 Steady State and Transient Analysis of Centrifugal Pumps
  18. Chapter 9 Thermal Analysis of Pressurizers
  19. Chapter 10 Thermal Analysis of Containments
  20. Chapter 11 Thermal Analysis of Steam Generators and Condensers
  21. Chapter 12 Fundamentals of Reactor Transient Simulation
  22. Chapter 13 Treatment of Uncertainties in Reactor Thermal Analysis
  23. Appendix A: Selected Nomenclature
  24. Appendix B: Physical and Mathematical Constants
  25. Appendix C: Unit Systems
  26. Appendix D: Mathematical Tables
  27. Appendix E: Thermodynamic Properties
  28. Appendix F: Thermophysical Properties of Some Substances
  29. Appendix G: Dimensionless Groups of Fluid Mechanics and Heat Transfer
  30. Appendix H: Multiplying Prefixes
  31. Appendix I: List of Elements
  32. Appendix J: Square and Hexagonal Rod Array Dimensions
  33. Appendix K: Parameters for Typical BWR-5 and PWR Reactors
  34. Appendix L: Discretization of Lumped Parameter Conservation Equations
  35. Appendix M: Proof of Local Volume-Averaging Theorems of Chapter 5
  36. Index