Thermal-Hydraulic Analysis of Nuclear Reactors, Softcover reprint of the original 1st ed. 2015

This 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. 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. 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.

This book also:

• Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, beginning 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
• 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

Dr. Bahman Zohuri is consulting at Galaxy Advanced Engineering while doing research at Department of Nuclear Engineering, University of New Mexico. Bahman began his career as a Naval Officer as Engineering Duty Officer in the USN, after graduating from University of Illinois with his Bachelor and Master of Science in Physics. After leaving the Navy he worked at Westinghouse in fast reactor safety, integral cross section measurements, as well thermal hydraulic analysis for such reactor. Later on he joined Lockheed Corporation and became chief scientist on star wars program and worked on nuclear weapons vulnerability, space nuclear power, and nuclear propulsion. He also was involved with Laser Radiation hardening and vulnerability different space programs for Strategic Defense Imitative (SDI). He is author of many books and publications. Dr. Zohuri holds a PhD in Nuclear Engineering and his second Master of Science degree in Mechanical Engineering from University of New Mexico.

Nima Fathi has for several semesters been teaching heat transfer at the University of New Mexico. The book is a development of lecture notes used in his classes and incorporation of various industrial and academic research results in thermal hydraulics. He is currently working on his PhD in mechanical engineering and his MSc in Nuclear engineering, after getting his MSc in mechanical engineering focuses on multiphase flow modeling for particle interaction in Stokes flow. Nima Fathi had designed in 2012 a new course, heat exchanger design, for the University of New Mexico. He has several years work experience in the heat exchanger design industry. He has been in involved in the industrial line, from designing, industrial drafting, procurement and fabrication. He has designed more than 86 heat exchanger and pressure vessels. Having a successful collaboration with different large companies, he brings much work experience to his projects. Nima Fathi holds two

Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, beginning 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

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

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