Introduction to nuclear engineering

著者

書誌事項

Introduction to nuclear engineering

John R. Lamarsh, Anthony J. Baratta

Pearson Education, c2018

4th ed

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内容説明・目次

内容説明

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.

目次

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 References Problems 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 References Problems 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 References Problems 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 References Problems 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 References Problems 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 References Problems 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 Reactor References Problems 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 Glossary References Problems 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 References Problems 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 References Problems 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

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詳細情報

  • NII書誌ID(NCID)
    BB25181697
  • ISBN
    • 9780134570051
  • 出版国コード
    us
  • タイトル言語コード
    eng
  • 本文言語コード
    eng
  • 出版地
    Hoboken, N.J.
  • ページ数/冊数
    xiii, 802 p.
  • 大きさ
    24 cm
  • 分類
  • 件名
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