Fundamentals of Nuclear Reactor Physics

Klappentext Offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation. This book includes a discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution. Zusammenfassung Offers a one-semester treatment of the essentials of how the fission nuclear reactor works! the various approaches to the design of reactors! and their safe and efficient operation. This book includes a discussion of neutron reactions! including neutron kinetics and the neutron energy spectrum! as well as neutron spatial distribution.

Autorentext
By Elmer E Lewis, Ph.D., Northwestern University Dept. Of Mechanical Engineering Robert R. McCormick School of Eng. & Applied Science Evanston, IL

Inhalt

1. Nuclear Reactions 1.1 Introduction 1.2 Nuclear Reaction Fundamentals 1.3 The Curve of Binding Energy 1.4 Fusion Reactions 1.5 Fission Reactions 1.6 Fissile and Fertile Materials 1.7 Radioactive Decay 2. Neutron Interactions 2.1 Introduction 2.2 Neutron Cross Sections 2.3 Neutron Energy Range 2.4 Cross Section Energy Dependence 2.5 Neutron Scattering 3. Neutron Distributions in Energy 3.1 Introduction 3.2 Nuclear Fuel Properties 3.3 Neutron Moderators 3.4 Neutron Energy Spectra 3.5 Energy-Averaged Reaction Rates 3.6 Infinite Medium Multiplication: 4. The Power Reactor Core 4.1 Introduction 4.2 Core Composition 4.3 Fast Reactor Lattices 4.4 Thermal Reactor Lattices 5. Reactor Kinetics 5.1 Introduction 5.2 Neutron Balance Equations 5.3 Multiplying Systems Behavior 5.4 Delayed Neutron Kinetics 5.5 Step Reactivity Changes 5.6 Prolog to Reactor Dynamics 6. Spatial Diffusion of Neutrons 6.1 Introduction 6.2 The Neutron Diffusion Equation 6.3 Non-multiplying Systems- Plane Geometry 6.4 Boundary Conditions 6.5 Non-multiplying Systems- Spherical Geometry 6.6 Diffusion Approximation Validity 6.7 Multiplying Systems 7. Neutron Distributions in Reactors 7.1 Introduction 7.2 The Time-Independent Diffusion Equation 7.3 Uniform Reactors 7.4 Neutron Leakage 7.5 Reflected Reactors 7.6 Control Poisons 8. Energy Transport 8.1 Introduction 8.2 Core Power Distribution 8.3 Heat Transport 8.4 Thermal Transients 9. Reactivity Feedback 9.1 Introduction 9.2 Reactivity Coefficients 9.3 Composite Coefficients 9.4 Excess Reactivity and Shutdown Margin 9.5 Reactor Transients 10. Long Term Core Behavior 10.1 Introduction 10.2 Reactivity Control 10.3 Fission Product Buildup and Decay 10.4 Fuel Depletion 10.5 Fission Product and Actinides Inventories Appendices A. Useful Mathematics B. Bessel's Equation and Functions C. Derivation of Neutron Diffusion Properties D. Fuel Element Heat Transfer E. Nuclear Data