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Thermal-Hydraulics of Water Cooled Nuclear Reactors

Book Description

Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors.

Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes.

The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis.

This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability.

  • Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors
  • Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis)
  • Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes
  • Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants

Table of Contents

  1. Cover image
  2. Title page
  3. Table of Contents
  4. Copyright
  5. List of authors
  6. About the authors
  7. Preface
  8. Acknowledgments
    1. Dedication
  9. Part One: The background to nuclear thermal-hydraulics
    1. 1: Introduction
      1. Abstract
      2. Acknowledgments
      3. Chapter foreword
      4. Glossary
    2. 2: A historical perspective of nuclear thermal-hydraulics
      1. Abstract
      2. Chapter foreword
    3. 3: Parameters and concepts
      1. Abstract
      2. Chapter foreword
    4. 4: Role of thermal-hydraulics in nuclear power plants: Design and safety
      1. Abstract
      2. Chapter foreword
  10. Part Two: Thermal-hydraulics connections: The principles of thermodynamics and nuclear systems
    1. 5: Balance equations
      1. Abstract
      2. Chapter foreword
      3. 5.4 The time-averaged single-phase equations
      4. 5.5 The space-time-averaged 1-D equations for single-phase flows
      5. 5.6 The various approaches to two-phase flow modeling
      6. 5.7 Time-averaged two-fluid equations
      7. 5.8 The space averaged 1-D equations for two-phase flow
      8. 5.9 The time-space averaged 1-D equations for two-phase flow
      9. 5.10 The 1-D two-fluid equations as used in system codes
      10. 5.11 Some simplified two-phase models: HEM drift-flux model
      11. 5.12 Characteristic velocities and hyperbolicity
      12. 5.13 Transport of interfacial area and polydispersion models
      13. 5.14 3-Field models in system codes
      14. 5.15 Summary remarks
    2. 6: Target phenomena in nuclear thermal-hydraulics
      1. Abstract
      2. Acknowledgments
      3. Chapter foreword
      4. 6.5 Thermal-hydraulic phenomena related to advanced water-cooled reactors
      5. 6.6 Thermal-hydraulic phenomena for SCWRs
      6. 6.7 Conclusions
  11. Part Three: Nuclear thermal hydraulics modeling
    1. 7: Heat transfer in nuclear thermal hydraulics
      1. Abstract
      2. Acknowledgments
      3. Chapter foreword
      4. Part 1: Principles and modeling
      5. Part 2: Boiling Heat Transfer
    2. 8: Pressure drops in nuclear thermal-hydraulics: Principles, experiments, and modeling
      1. Abstract
      2. List of symbols
      3. Chapter foreword
    3. 9: Constitutive equations
      1. Abstract
      2. Chapter foreword
    4. 10: Special models for nuclear thermal hydraulics
      1. Abstract
      2. Chapter foreword
    5. 11: The structure of system thermal-hydraulic (SYS-TH) code for nuclear energy applications
      1. Abstract
      2. Chapter foreword
    6. 12: An overview of computational fluid dynamics and nuclear applications
      1. Abstract
      2. Chapter foreword
      3. Part 1. Computational fluid dynamics for nuclear thermal hydraulics: The current overview
      4. Part 2. Insights into computational fluid dynamics for nuclear power plant applications
  12. Part Four: Applications of thermal-hydraulics in nuclear technology
    1. 13: Verification and validation of system thermal-hydraulic computer codes, scaling and uncertainty evaluation of calculated code results
      1. Abstract
      2. Chapter foreword
    2. 14: Best-Estimate Plus Uncertainty (BEPU) approach for accident analysis
      1. Abstract
      2. Acknowledgments
      3. Chapter foreword
    3. 15: Applications of SYS TH codes to nuclear reactor design and accident analysis
      1. Abstract
      2. Acknowledgments
      3. Chapter foreword
    4. 16: Thermal-hydraulics aspects of key nuclear accidents
      1. Abstract
      2. Acknowledgments
      3. Chapter foreword
  13. Subject Index
  14. Author Index