Thermal Safety Margins in Nuclear Reactors

This book presents an overview of state-of-the art approaches to determine thermal safety margins in nuclear reactors. It presents both the deterministic and probabilistic aspects of thermal safety margins of nuclear reactors to facilitate the understanding of these two difficult topics at various academic levels, from undergraduates to researchers in nuclear engineering.

It first sets out the theoretical background before exploring how to determine thermal safety margins in nuclear reactors, through examples, problems and advanced state-of-the-art approaches. This will help undergraduate students better understand the most fundamental aspects of nuclear reactor safety. For researchers and practitioners, this book provides a comprehensive overview of most recent achievements in the field, offering an excellent starting point to develop new methods for the assessment of the thermal safety margins.

This book is written to bridge the gap between deterministic and appropriate treatment of uncertainties to assess safety margins in nuclear reactors, presenting these approaches as complementary to each other. Even though these two approaches are frequently used in parallel in real-world applications, there has been a lack of a consistent teaching approach in this area.

This book is suitable for readers with a background in calculus, thermodynamics, fluid mechanics, and heat transfer. It is assumed that readers have previous exposure to such concepts as laws of thermodynamics, enthalpy, entropy, and conservation equations used in fluid mechanics and heat transfer.

Key Features:

• Covers the theory, principles, and assessment methods of thermal safety margins in nuclear reactors whilst presenting the state-of-the-art technology in the field
• Combines the deterministic thermal safety considerations with a comprehensive treatment of uncertainties, offering a framework that is applicable to all current and future commercial nuclear reactor types
• Provides numerous examples and problems to be solved

Chapter 1: Overview of Nuclear Reactor Safety and Design. Chapter 2: Nuclear Power Reactors. Chapter 3: Thermophysical Properties of Reactor Core Materials. Chapter 4: Conservation Equations for Single-Phase Flow. Chapter 5: Single-Phase Flow in Coolant Channels. Chapter 6: Multiphase Flows in Channels. Chapter 7: Convection Heat Transfer. Chapter 8: Boiling Heat Transfer. Chapter 9: Boiling Crisis. Chapter 10: Thermal Performance of Fuel Elements. Chapter 11: Uncertainty Treatment. Chapter 12: Thermal Safety Margins. Appendix A: Notation. Appendix B: Mathematical Tools. Appendix C: Correlations. Appendix D: Data Tables. References. Index.

Henryk Anglart is Professor Emeritus of Nuclear Engineering at the KTH Royal Institute of Technology, Stockholm, Sweden, and at the Warsaw University of Technology (WUT), Warsaw, Poland. He received his MSc from WUT and his PhD from the Rensselaer Polytechnic Institute, Troy, NY. After his eighteen year career as a research and development engineer at Westinghouse in Sweden, he accepted a tenure position at KTH, where he has supervised many PhD students and post-doctoral fellows, and has taught several courses in nuclear engineering. In addition to research and teaching, Prof. Henryk Anglart was serving for a long time as head of Reactor Technology Division, Deputy Director of the Physics Department, and Director of Nuclear Technology Center at KTH. Prof. Henryk Anglart authored and coauthored over 200 journal, conference and other scientific publications. He is also an author of three textbooks used in teaching of nuclear engineering courses at WUT and KTH, and two CRC Press books: Multilingual Dictionary of Nuclear Reactor Physics and Engineering, and Introduction to Sustainable Energy Transformation.