Henryk Anglart
Thermal Safety Margins in Nuclear Reactors
Henryk Anglart
Thermal Safety Margins in Nuclear Reactors
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This book presents an overview of state-of-the art approaches to determine thermal safety margins in nuclear reactors.
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This book presents an overview of state-of-the art approaches to determine thermal safety margins in nuclear reactors.
Produktdetails
- Produktdetails
- Verlag: Taylor & Francis Ltd
- Seitenzahl: 370
- Erscheinungstermin: 11. Juni 2024
- Englisch
- Abmessung: 234mm x 156mm
- Gewicht: 870g
- ISBN-13: 9781032171050
- ISBN-10: 1032171057
- Artikelnr.: 70243088
- Verlag: Taylor & Francis Ltd
- Seitenzahl: 370
- Erscheinungstermin: 11. Juni 2024
- Englisch
- Abmessung: 234mm x 156mm
- Gewicht: 870g
- ISBN-13: 9781032171050
- ISBN-10: 1032171057
- Artikelnr.: 70243088
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.
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.
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.
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.
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.