(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.
Appendixes.
I. Units and Conversion Factors. II. Fundamental Constants and
Data. III. Vector Operations in Orthogonal Curvilinear Coordinates.
IV. Thermodynamic and Physical Properties. V. Bessel Functions.
Index.
Anthony Baratta is currently a Professor of Nuclear Engineering at The Pennsylvania State University and Director of the Nuclear Safety Center. He received the B.A/B.S. degrees in physics/applied physics from Columbia University in 1968 and the M.S. and Ph.D. degrees in physics from Brown University in 1970 and 1978, respectively. His research interests and contributions include reactor safety, reactor kinetics and physics, and the effects of radiation on materials. He has authored many scientific publications and made numerous presentations. He is an active member of the American Nuclear Society and has appeared on many network television and radio broadcasts as an authority on reactor accidents, including the accident at Three Mile Island.
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