
Introduction to Nuclear Engineering
By: John R. Lamarsh, Anthony J. Baratta
eText | 1 June 2017 | Edition Number 4
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For junior- and senior-level courses in Nuclear Engineering.
Introduction to Nuclear Engineering, 4th Edition reflects changes in the industry since the 2001 publication of its predecessor. With recent data and information, including expanded discussions about the worldwide nuclear renaissance and the development and construction of advanced plant designs, the text aims to provide students with a modern, high-level introduction to nuclear engineering. The nuclear industry is constantly in flux, and the 4th Edition helps students understand real-world applications of nuclear technology–in the United States and across the globe.
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on
- 1. Nuclear Engineering
- 2. Atomic and Nuclear Physics
- 2.1 Fundamental Particles
- 2.2 Atomic and Nuclear Structures
- 2.3 Atomic and Molecular Weights
- 2.4 Atomic and Nuclear Radii
- 2.5 Mass and Energy
- 2.6 Particle Wavelengths
- 2.7 Excited States and Radiation
- 2.8 Nuclear Stability and Radioactive Decay
- 2.9 Radioactivity Calculations
- 2.10 Nuclear Reactions
- 2.11 Binding Energy
- 2.12 Nuclear Models
- 2.13 Gases, Liquids, and Solids
- 2.14 Atom Density
- 3. Interaction of Radiation with Matter
- 3.1 Neutron Interactions
- 3.2 Cross Sections
- 3.3 Neutron Attenuation
- 3.4 Neutron Flux
- 3.5 Neutron Cross Section Data
- 3.6 Energy Loss in Scattering Collisions
- 3.7 Fission
- 3.8 y-Ray Interactions with Matter
- 3.9 Charged Particles
- 4. Nuclear Reactors and Nuclear Power
- 4.1 The Fission Chain Reaction
- 4.2 Nuclear Reactor Fuels
- 4.3 Non-Nuclear Components of Nuclear Power Plants
- 4.4 Components of Nuclear Reactors
- 4.5 Power Reactors and Nuclear Steam Supply Systems
- 4.6 Nuclear Cycles
- 4.7 Isotope Separation
- 4.8 Fuel Reprocessing
- 4.9 Radioactive Waste Disposal
- 5. Neutron Diffusion and Moderation
- 5.1 Neutron Flux
- 5.2 Fick’s Law
- 5.3 The Equation of Continuity
- 5.4 The Diffusion Equation
- 5.5 Boundary Conditions
- 5.6 Solutions of the Diffusion Equation
- 5.7 The Diffusion Length
- 5.8 The Group-Diffusion Method
- 5.9 Thermal Neutron Diffusion
- 5.10 Two-Group Calculation of Neutron Moderation
- 6. Nuclear Reactor Theory
- 6.1 One-Group Reactor Equation
- 6.2 The Slab Reactor
- 6.3 Other Reactor Shapes
- 6.4 The One-Group Critical Equation
- 6.5 Thermal Reactors
- 6.6 Reflected Reactors
- 6.7 Multigroup Calculations
- 6.8 Heterogeneous Reactors
- 7. The Time-Dependent Reactor
- 7.1 Classification of Time Problems
- 7.2 Reactor Kinetics
- 7.3 Control Rods and Chemical Shim
- 7.4 Temperature Effects on Reactivity
- 7.5 Fission Product Poisoning
- 7.6 Core Properties During Lifetime
- 8. Heat Removal from Nuclear Reactors
- 8.1 General Thermodynamic Considerations
- 8.2 Heat Generation in Reactors
- 8.3 Heat Flow by Conduction
- 8.4 Heat Transfer to Coolants
- 8.5 Boiling Heat Transfer
- 8.6 Thermal Design of a Reactors
- 9. Radiation Protection
- 9.1 History of Radiation Effects
- 9.2 Radiation Units
- 9.3 Some Elementary Biology
- 9.4 The Biological Effects of Radiation
- 9.5 Quantitative Effects of Radiation on the Human Species
- 9.6 Calculations of Radiation Effects
- 9.7 Natural and Man-Made Radiation Sources
- 9.8 Standards of Radiation Protection
- 9.9 Computations of Exposure and Dose
- 9.10 Standards for Intake of Radionuclides
- 9.11 Exposure from y-Ray Sources
- 10. Radiation Shielding
- 10.1 Gamma-Ray Shielding: Buildup Factors
- 10.2 Infinite Planar and Disc Sources
- 10.3 The Line Source
- 10.4 Internal Sources
- 10.5 Multilayered Shields
- 10.6 Nuclear Reactor Shielding: Principles of Reactor Shielding
- 10.7 Removal Cross Sections
- 10.8 Reactor Shield Design: Removal—Attenuation Calculations
- 10.9 The Removal—Diffusion Method
- 10.10 Exact Methods
- 10.11 Shielding y-Rays
- 10.12 Coolant Activation
- 10.13 Ducts in Shields
- 11. Reactor Licensing, Safety, and the Environment
- 11.1 Governmental Authority and Responsibility
- 11.2 Reactor Licensing
- 11.3 Principles of Nuclear Power Plant Safety
- 11.4 Dispersion of Effluents from Nuclear Facilities
- 11.5 Radiation Doses from Nuclear Plants
- 11.6 Reactor Siting
- 11.7 Reactor Accidents
- 11.8 Accident Risk Analysis
- 11.9 Environmental Radiation Doses
- Appendixes
- I. Units and Conversion Factors 743
- II. Fundamental Constants and Data 749
- III. Vector Operations in Orthogonal Curvilinear Coordinates 759
- IV. Thermodynamic and Physical Properties 765
- V. Bessel Functions
- Index
ISBN: 9780134570341
ISBN-10: 0134570340
Published: 1st June 2017
Format: ePUB
Language: English
Audience: College, Tertiary and University
Publisher: Pearson Education (US)
Country of Publication: US
Edition Number: 4
























