Introduction to Nuclear Engineering

Pearson New International Edition

AvJohn Lamarsh,Anthony Baratta

Häftad, Engelska, 2013

1 183 kr

Beställningsvara. Skickas inom 7-10 vardagar. Fri frakt över 249 kr.

Fler format och utgåvor

Inbunden

4 767 kr

Beskrivning

The text is designed for junior and senior level Nuclear Engineering students. The third edition of this highly respected text offers the most current and complete introduction to nuclear engineering available. Introduction to Nuclear Engineering has been thoroughly updated with new information on French, Russian, and Japanese nuclear reactors. All units have been revised to reflect current standards. In addition to the numerous end-of-chapter problems, computer exercises have been added.

Produktinformation

Utgivningsdatum:2013-07-24
Mått:216 x 279 x 33 mm
Vikt:1 613 g
Format:Häftad
Språk:Engelska
Antal sidor:744
Upplaga:3
Förlag:Pearson Education
ISBN:9781292025810

Utforska kategorier

Energiteknik inom Naturvetenskap och teknik

Innehållsförteckning

(Most chapters end with References and Problems). 1. Nuclear Engineering. 2. Atomic and Nuclear Physics. Fundamental Particles. Atomic and Nuclear Structure. Atomic and Molecular Weight. Atomic and Nuclear Radii. Mass and Energy. Particle Wavelengths. Excited States and Radiation. Nuclear Stability and Radioactive Decay. Radioactivity Calculations. Nuclear Reactions. Binding Energy. Nuclear Models. Gases, Liquids, and Solids. Atom Density. 3. Interaction of Radiation with Matter. Neutron Interactions. Cross-Sections. Neutron Attenuation. Neutron Flux. Neutron Cross-Section Data. Energy Loss in Scattering Collisions. Fission. y-Ray Interactions with Matter. Charged Particles. 4. Nuclear Reactors and Nuclear Power. The Fission Chain Reaction. Nuclear Reactor Fuels. Non-Nuclear Components of Nuclear Power Plants. Components of Nuclear Reactors. Power Reactors and Nuclear Steam Supply Systems. Nuclear Cycles. Isotope Separation. Fuel Reprocessing. Radioactive Waste Disposal. 5. Neutron Diffusion and Moderation. Neutron Flux. Fick's Law. The Equation of Continuity. The Diffusion Equation. Boundary Conditions. Solutions of the Diffusion Equation. The Diffusion Length. The Group-Diffusion Method. Thermal Neutron Diffusion. Two-Group Calculation of Neutron Moderation. 6. Nuclear Reactor Theory. One-Group Reactor Equation. The Slab Reactor. Other Reactor Shapes. The One-Group Critical Equation. Thermal Reactors. Reflected Reactors. Multigroup Calculations. Heterogeneous Reactors. 7. The Time-Dependent Reactor. Classification of Time Problems. Reactor Kinetics. Control Rods and Chemical Shim. Temperature Effects on Reactivity. Fission Product Poisoning. Core Properties during Lifetime. 8. Heat Removal from Nuclear Reactors. General Thermodynamic Considerations. Heat Generation in Reactors. Heat Flow by Conduction. Heat Transfer to Coolants. Boiling Heat Transfer. Thermal Design of a Reactor. 9. Radiation Protection. History of Radiation Effects. Radiation Units. Some Elementary Biology. The Biological Effects of Radiation. Quantitative Effects of Radiation on the Human Species. Calculations of Radiation Effects. Natural and Man-Made Radiation Sources. Standards of Radiation Protection. Computations of Exposure and Dose. Standards for Intake of Radionuclides. Exposure from y-Ray Sources. Glossary. 10. Radiation Shielding. Gamma-Ray Shielding: Buildup Factors. Infinite Planar and Disc Sources. The Line Source. Internal Sources. Multilayered Shields. Nuclear Reactor Shielding: Principles of Reactor Shielding. Removal Cross-Sections. The Reactor Shield Design: Removal-Attenuation Calculatons. The Removal-Diffusion Method. Exact Methods. Shielding y-Rays. Coolant Activation. Ducts in Shields. 11. Reactor Licensing, Safety, and the Environment. Governmental Authority and Responsibility. Reactor Licensing. Principles of Nuclear Power Plant Safety. Dispersion of Effluents from Nuclear Facilities. Radiation Doses from Nuclear Plants. Reactor Siting. Reactor Accidents. Accident Risk Analysis. Environmental Radiation Doses. Index.