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This full-color textbook provides an up to date introduction to nuclear physics, reactor design, thermal-hydraulic systems, fuel cycles, safety, and computational methods for students taking a first course in Nuclear Engineering. Following a structured learning approach, the text offers consistent topic development, supported by color images, key equations, worked examples, historical and biographical features, web links for research, short answer questions, and numerous chapter problems. Nuclear reactor designs, including the most recent examples, are analyzed and compared, and the role of internet tools in analysis and design is explored. Extensive tables are included for reference.
Sommario
Preface
Acknowledgments
Author
Chapter 1 Understanding the Atom and the Nucleus
Chapter 2 Neutrons and Other Important Nuclear Particles
Chapter 3 Fundamental Nuclear Processes: Scattering, Fission, and Absorption
Chapter 4 Nuclear Cross Sections and Reaction Probabilities
Chapter 5 Cross Section Libraries and Sources of Nuclear Data
Chapter 6 Radioactive Materials and Radioactive Decay
Chapter 7 Nuclear Fission and the Nuclear Chain Reaction
Chapter 8 Neutron Moderators and Reactor Coolants
Chapter 9 Elements, Isotopes, and Their Properties
Chapter 10 Uranium Enrichment, Nuclear Fuels, and Fuel Cycles
Chapter 11 Fuel Pins, Fuel Rods, Fuel Assemblies, and Reactor Cores
Chapter 12 Types of Reactors and Their Design Parameters
Chapter 13 Pressurized Water Reactors
Chapter 14 Boiling Water Reactors
Chapter 15 Fast Reactors, Gas Reactors, and Military Reactors
Chapter 16 Containment Buildings and the Nuclear Steam Supply System
Chapter 17 The Interaction of Radiation with Matter
Chapter 18 Shielding Systems and Radiation Shields
Chapter 19 Protecting Humans from the Harmful Effects of Radiation
Appendix A: Important Nuclear and Physical Constants
Appendix B: Unit Systems and Conversion Factors
Appendix C: Nuclear Cross Sections and Reaction Rates
Appendix D: Physical Properties of Important Nuclear Materials
Appendix E: Atomic Mass Tables, Half-Lives, and Natural Abundances
Appendix F: Delayed Neutron Emitters and Their Nuclear Properties
Appendix G: Attenuation Coefficients for Radiation Shields
Index
Info autore
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.
