Nuclear Fission Reactors

1.Basic Physics of the Atom and the Nucleus.- 1.1. The Nuclear Atom.- 1.2. The Structure of the Atom.- 1.3. Radioactivity.- 1.3.1. ?, ?, and ? Emission.- 1.3.2. The Systematics of Radioactive Decay.- 1.4. Mass Defect and Binding Energy.- 1.5. Interactions of Neutrons with the Nucleus.- 1.6. Cross Sections for Neutron Reactions.- 1.7. Cross Sections of Particular Importance in Reactor Physics.- 1.8. Experimental Techniques.- 1.8.1. Neutron Sources.- 1.8.2. Detection of Charged Particles and ? Rays.- 1.8.3. Neutron Detectors.- 2. Nuclear Fission and the Nuclear Chain Reaction.- 2.1. Nature of the Fission Process.- 2.2. The Products of Fission.- 2.3. Energy Release in Fission.- 2.4. The Nuclear Chain Reaction.- 2.5. The Role of Plutonium in Nuclear Reactors.- 2.6. Nuclear Cross Sections of the Fissile Isotopes.- 3. Elements of Nuclear Reactor Theory.- 3.1. The Neutron Energy Spectrum in a Nuclear Reactor.- 3.2. The Spatial Dependence of the Neutron Flux in a Reactor.- 3.2.1. One-Group Method.- 3.2.2. Two-Group Method.- 3.3. The Heterogeneous Reactor.- 3.4. Reactor Kinetics and Control.- 3.4.1. Kinetics of the Reactor without Feedback.- 3.4.2. Reactivity Effects Arising from Power Operation.- 3.4.3. Fission Product Poisoning.- 4. Nuclear Fuels and Their Characteristics.- 4.1.Nuclear Properties of Fissile Materials.- 4.2.Buildup of Plutonium in a Natural Uranium Reactor.- 4.3.The Th232-U233 Fuel Cycle.- 4.4.Aspects of Fuel Management in Thermal Reactors.- 5. Materials Problems for Nuclear Reactors.- 5.1. Effects of Irradiation on Reactor Materials.- 5.2. Uranium-Production and Enrichment.- 5.3. Properties of Uranium Metal.- 5.4. Ceramic Uranium Fuel.- 5.5. Dispersion-Type Fuel Elements.- 5.6. Graphite.- 5.7. Stainless Steel.- 5.8. Zirconium.- 5.9. Light and Heavy Water.- 6.Heat Generation and Removal in Nuclear Reactors.- 6.1. Introduction.- 6.2. Maximum Heat Generation Rate in Fuel.- 6.3. Heat Conduction in Fuel Elements.- 6.3.1. The Poisson Equation.- 6.3.2. Solutions of the Poisson Equation.- 6.4. Temperature Distributions along a Coolant Channel.- 6.4.1. Heat Transfer by Convection.- 6.4.2. Axial Variation of Fuel, Clad, and Coolant Temperatures.- 6.5. Heat Transfer by Boiling Coolant.- 6.6. Nuclear Power Reactor Cooling Systems.- 6.6.1. Choice of Coolant.- 6.6.2. Water-Cooled Reactors.- 6.6.3. Gas-Cooled Reactors.- 6.6.4. Liquid Metal Cooling.- 6.6.5. Superheat and Reheat.- 7.General Survey of Reactor Types.- 7.1.Introduction.- 7.2.Classification of Thermal Reactors.- 8. The Gas-Cooled Graphite-Moderated Reactor.- 8.1. General Characteristics of the Gas-Cooled Graphite-Moderated Reactor.- 8.2. The Magnox Natural Uranium Graphite-Moderated Reactor.- 8.3. The Advanced Gas-Cooled Reactor.- 8.4. The High-Temperature Gas-Cooled Reactor.- 9. The Light-Water-Moderated Reactor.- 9.1. General Characteristics of the Light-Water-Moderated Reactor.- 9.2. Development of the Light Water Reactor.- 9.3. The Pressurized Water Reactor.- 9.4. The Boiling Water Reactor.- 10. The Heavy-Water-Moderated Reactor.- 10.1. General Characteristics of the Heavy Water Reactor.- 10.2. The CANDU Pressure Tube Heavy Water Reactor.- 11. The Fast Reactor.- 11.1. Introduction.- 11.2. The Physics and Technology of Fast Reactors.- 11.3. Dynamic Behavior and Safety Aspects of the Fast Reactor.- 11.4. The Dounreay Prototype Fast Reactor.- 12. Safety and Environmental Aspects of Nuclear Reactors.- 12.1.The Biological Effects of Radiation.- 12.2. Effects of Routine Release of Radioactivity from the Nuclear Industry.- 12.2.1. Dose Limits for Radiation Exposure.- 12.2.2. Release of Radioactive Isotopes from Nuclear Power Plants.- 12.2.3. Estimated Radiation Doses Due to the Nuclear Fuel Cycle.- 12.3. Reactor Accidents: Safety Studies on Light Water Reactors.- 12.3.1. Analysis of LWR Safety.- 12.3.2. Accident Experience with Light Water Reactors.- 12.4. Reactor Accidents: Thermal Reactors Other than LWRs.- 12.4.1. The Gas-Cooled Graphite-Moderated Reactor.- 12.4.2. The Heavy Water Reactor.- 12.5. The Safety of the Fast Breeder Reactor.- 12.6. Long-term Storage and Disposal of Radioactive Wastes.- 12.7. The Thermal Effects of Nuclear Power Stations.