Introduction to Nuclear Engineering, 4th edition

Published by Pearson (July 1, 2022) © 2023

  • John R. Lamarsh Late Professor with the New York Polytechnic Institute
  • Anthony J. Baratta Pennsylvania State University
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For junior- and senior-level courses in Nuclear Engineering.

Applying nuclear engineering essentials to the modern world

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.

  • 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 Diffus

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