Nuclear Reactor Thermal Hydraulics: An Introduction to Nuclear Heat Transfer and Fluid Flow

Nuclear

Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students.

Robert E. Masterson (1950-2020) held MS and PhD degrees in nuclear engineering from the Massachusetts Institute of Technology, and he worked for Westinghouse Nuclear Energy Systems. He was an Affiliate Professor of Nuclear Science and Engineering at Virginia Tech University in Blacksburg, Virginia. Dr. Masterson published extensively in the journals of the ANS and had over 20 years of experience in the field of nuclear science and engineering. He had an extensive background in the fields of reactor safety, reactor design and analysis, reactor thermal hydraulics, numerical analysis, reactor physics, reactor dynamics, nuclear medicine, and nuclear particle transport. He was a member of the American Nuclear Society. His first textbook with CRC Press, Nuclear Engineering Fundamentals: A Practical Perspective, was published in 2017.