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Bahman Zohuri

Thermal-Hydraulic Analysis of Nuclear Reactors


2. Aufl. 2018. xxviii, 835 S. 280 SW-Abb., 173 Farbabb., 340 Farbtabellen. 235 mm
Verlag/Jahr: SPRINGER, BERLIN; SPRINGER INTERNATIONAL PUBLISHING 2018
ISBN: 3-319-85251-5 (3319852515)
Neue ISBN: 978-3-319-85251-5 (9783319852515)

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This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors.

Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.
1. An Introduction to Thermal Hydraulic Aspects of Nuclear Power Reactors 2. Thermodynamics 3. Transport Properties 4. General Conservation Equations 5. Laminar Incompressible Forced Convection 6. Turbulent Forced Convection 7. Compressible Flow 8. Conduction Heat Transfer 9. Forced Convection Heat Transfer 10. Natural or Free Convection 11. Mass Transfer 12. Thermal Radiation 13. Multi-Phase Flow Dynamics 14. Convective Boiling 15. Thermal Stress 16. Combined Cycle Driven Efficiency in Nuclear Power Plant 17. Heat Exchangers 18. Analysis of Reactor Accident 19. Probabilistic Risk Assessment 20. Nuclear Power Plants 21. Nuclear Fuel Cycle 22. The Economic Future of Nuclear Power 23. Safety, Waste Disposal, Containment, and Accidentss Appendix A: Table and Graphs Compilations Appendix B: Physical Property Tables Appendix C: Units, Dimensions and Conversion Factors Appendix D: Physical Properties Appendix E: Fluid Property Data Appendix F: Basic Equations Index