Thermal-Hydraulic Analysis of Nuclear Reactors (2nd Ed., Softcover reprint of the original 2nd ed. 2017)

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Language: English

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Thermal-Hydraulic Analysis of Nuclear Reactors
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295.39 €

In Print (Delivery period: 15 days).

Add to cartAdd to cart
Thermal-Hydraulic Analysis of Nuclear Reactors
Publication date:
Support: Print on demand

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.

An Introduction to Thermal Hydraulic Aspects of Nuclear Power Reactors.- Thermodynamics.- Transport Properties.- General Conservation Equations.- Laminar Incompressible Forced Convection.- Turbulent Forced Convection.- Compressible Flow.- Conduction Heat Transfer.- Forced Convection Heat Transfer.- Natural or Free Convection.- Mass Transfer.- Thermal Radiation.- Multi-Phase Flow Dynamics.- Convective Boiling.- Thermal Stress.- Combined Cycle Driven Efficiency in Nuclear Power Plant.- Heat Exchangers.- Analysis of Reactor Accident.- Probabilistic Risk Assessment.- Nuclear Power Plants.- Nuclear Fuel Cycle.- The Economic Future of Nuclear Power.- 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.

Dr. Bahman Zohuri is currently at the Galaxy Advanced Engineering, Inc. a consulting company that he stared himself in 1991 when he left both semiconductor and defense industries after many years working as a chief scientist. After graduating from University of Illinois in field of Physics and Applied Mathematics, he joined Westinghouse Electric Corporation where he performed thermal hydraulic analysis and natural circulation for Inherent Shutdown Heat Removal System (ISHRS) in the core of a Liquid Metal Fast Breeder Reactor (LMFBR) as a secondary fully inherent shut system for secondary loop heat exchange. All these designs were used for Nuclear Safety and Reliability Engineering for Self-Actuated Shutdown System. He designed the Mercury Heat Pipe and Electromagnetic Pumps for Large Pool Concepts of LMFBR for heat rejection purpose for this reactor around 1978 where he received a patent for it. He later on was transferred to defense division of Westinghouse where he was responsible for the dynamic analysis and method of launch and handling of MX missile out of canister. The results are applied to MX launch seal performance and muzzle blast phenomena analysis (i.e. missile vibration and hydrodynamic shock formation). He also was involved in analytical calculation and computation in the study of Nonlinear Ion Wave in Rarefying Plasma. The results are applied to the propagation of "Soliton Wave" and the resulting charge collector traces, in the rarefactions characteristic of the corona of the a laser irradiated target pellet. As part of his graduate research work at Argonne National Laboratory, he performed computation and programming of multi-exchange integral in surface physics and solid state physics. He holds different patent in areas such as diffusion processes and design of diffusion furnace while he was senior process engineer working for different semiconductor industries such as Intel, Varian, and National Semiconductor corporations. Later on he jo

Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, from fundamentals to applications; Reinforces fundamentals of fluid dynamics and heat transfer; thermal and hydraulic analysis of nuclear reactors, two-phase flow and boiling, compressible flow, stress analysis and energy conversion methods; Includes detailed appendices that cover metric and English system units and conversions, detailed steam and gas tables, heat transfer properties and nuclear reactor system descriptions.