Neutronic analysis for nuclear reactor systems

This book covers the entire spectrum of the science and technology of nuclear reactor systems, from underlying physics, to next generation system applications and beyond. Beginning with neutron physics background and modeling of transport and diffusion, this self-contained learning tool progresses step-by-step to discussions of reactor kinetics, dynamics, and stability that will be invaluable to anyone with a college-level mathematics background wishing to develop an understanding of nuclear power. From fuels and reactions to full systems and plants, the author provides a clear picture of how nuclear energy works, how it can be optimized for safety and efficiency, and why it is important to the future.

Preface; About This Document; Acknowledgments; Contents; About the Author; Chapter 1: Neutron Physics Background; 1.1 Nuclei: Sizes, Composition, and Binding Energies; Pion; Atom Density; 1.2 Decay of a Nucleus; 1.3 Distribution of Nuclides and Nuclear Fission/Nuclear Fusion; Gamma Decay; 1.4 Neutron-Nucleus Interaction; 1.4.1 Nuclear Reaction Rates and Neutron Cross Sections; 1.4.2 Effects of Temperature on Cross Section; 1.4.3 Nuclear Cross-Sectional Processing Codes; 1.4.4 Energy Dependence of Neutron Cross Sections; 1.4.5 Types of Interactions; 1.5 Mean Free Path.

1.6 Nuclear Cross Section and Neutron Flux Summary1.7 Fission; 1.8 Fission Spectra; 1.9 The Nuclear Fuel; 1.9.1 Fertile Material; 1.10 Liquid Drop Model of a Nucleus; 1.11 Summary of Fission Process; 1.12 Reactor Power Calculation; 1.13 Relationship Between Neutron Flux and Reactor Power; Problems; References; Chapter 2: Modeling Neutron Transport and Interactions; 2.1 Transport Equations; 2.2 Reaction Rates; 2.3 Reactor Power Calculation; 2.4 Relationship Between Neutron Flux and Reactor Power; 2.5 Neutron Slowing Down and Thermalization; 2.6 Macroscopic Slowing Down Power.

2.7 Moderate Ratio2.8 Integrodifferentia…