Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors
Volume 2: Modelling
- 600 pages
- English
- PDF
- Only available on web
Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors
Volume 2: Modelling
About This Book
Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 2, Modelling includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided.
- Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics
- Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix
- Covers applicable nuclear reactor safety considerations and design technology throughout
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Table of contents
- Front Cover
- Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors
- Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors: Volume 2: Modelling
- Copyright
- Dedication
- Contents
- List of contributors
- Contributors for volumes 1, 2 and 3
- Foreword
- Glossary
- Preface to the first edition of the book
- Preface to the second edition of the book
- Acknowledgments (for the past) and wishes (for the future)
- 10 - Special models for nuclear thermal hydraulics
- 11 - The structure of system thermal-hydraulic code for nuclear reactor applications
- 12 - An overview of computational fluid dynamics and nuclear thermal hydraulics applications
- 13 - Verification and validation of system thermal-hydraulic computer codes and scaling and uncertainty evaluation of calcu ...
- 14 - Best estimate plus uncertainty approach for accident analysis
- 15 - Applications of SYS TH codes to nuclear reactor design and accident analysis
- 16 - Thermal hydraulic aspects of key nuclear accidents
- 17 - Instrumentation in nuclear thermal hydraulics
- Questions and answers from Chapters 10 to 17
- References
- Index
- Back Cover