Massachusetts Institute of Technology, Taylor &Francis, 1993,
720 pp. - ISBN 1-56032-051-6.
(Thermal hydraulic fundamentals, Nuclear reactors, Fluid dynamics, Heat Transmission, Nuclear power plants)
This book can serve as a textbook for two to three courses at the advanced undergraduate and the graduate student level. It is also suitable as a basis for continuing education of engineers in the nuclear power industry, who wish to expand their knowledge of the principles of thermal analysis of nuclear systems. The book, in fact, was an outgrowth of the course notes used for teaching several classes at MIT over a period of nearly fifteen years.
The book is meant to cover more than thermal hydraulic design and analysis of the core of a nuclear reactor. Thus, in several parts and examples, other components of the nuclear power plant, such as the pressurizer, the containment and the entire primary coolant system are addressed. In this respect the book reflects the importance of such considerations in thermal engineering of a modem nuclear power plant. The traditional concentration on the fuel element in earlier textbooks was appropriate when the fuel performance had a higher share of the cost of electricity than in mode plants. The cost and performance of nuclear power plants has proven to be more influenced by the steam supply system and the containment building than previously anticipated.
Contents.
Thermal Hydraulic Characteristics of Power Reactors.
Plant Characteristics Influenced by Thermal Hydraulic.
Reactor Heat Generation.
Transport Equations for Single-Phase Flow.
Transport Equations for Two-Phase Flow.
Thermodynamics of Nuclear Energy Conversion Systems: Nonflow and Steady Flow: First and Second Law Applications.
Thermodynamics of Nuclear Energy Conversion Systems: Nonsteady Flow First Law Analysis.
Thermal Analysis of Fuel Elements.
Single-Phase Fluid Mechanics.
Single-Phase Heat Transfer.
Two-Phase Flow Dynamics.
Two-Phase Heat Transfe.
Single Heated Channel: Steady-State Analysis.
Appendices. Index.
(Thermal hydraulic fundamentals, Nuclear reactors, Fluid dynamics, Heat Transmission, Nuclear power plants)
This book can serve as a textbook for two to three courses at the advanced undergraduate and the graduate student level. It is also suitable as a basis for continuing education of engineers in the nuclear power industry, who wish to expand their knowledge of the principles of thermal analysis of nuclear systems. The book, in fact, was an outgrowth of the course notes used for teaching several classes at MIT over a period of nearly fifteen years.
The book is meant to cover more than thermal hydraulic design and analysis of the core of a nuclear reactor. Thus, in several parts and examples, other components of the nuclear power plant, such as the pressurizer, the containment and the entire primary coolant system are addressed. In this respect the book reflects the importance of such considerations in thermal engineering of a modem nuclear power plant. The traditional concentration on the fuel element in earlier textbooks was appropriate when the fuel performance had a higher share of the cost of electricity than in mode plants. The cost and performance of nuclear power plants has proven to be more influenced by the steam supply system and the containment building than previously anticipated.
Contents.
Thermal Hydraulic Characteristics of Power Reactors.
Plant Characteristics Influenced by Thermal Hydraulic.
Reactor Heat Generation.
Transport Equations for Single-Phase Flow.
Transport Equations for Two-Phase Flow.
Thermodynamics of Nuclear Energy Conversion Systems: Nonflow and Steady Flow: First and Second Law Applications.
Thermodynamics of Nuclear Energy Conversion Systems: Nonsteady Flow First Law Analysis.
Thermal Analysis of Fuel Elements.
Single-Phase Fluid Mechanics.
Single-Phase Heat Transfer.
Two-Phase Flow Dynamics.
Two-Phase Heat Transfe.
Single Heated Channel: Steady-State Analysis.
Appendices. Index.