- 费米的物理(核反应堆的中子物理)(英文版)(精)
- - 作者：编者:(意)萨尔瓦托雷·埃斯波西托//奥费利娅·皮桑蒂|责编:王艺霖
  - 出版社：世图出版公司
  - ISBN：9787523234983
  - 出版日期：2026/07/01
  - 页数：665
- 售价：91.6

内容大纲
这本书汇集了恩里科·费米关于核反应堆中子物理的核心教学遗产与工程实践记录。书中收录了费米于1945年在洛斯阿拉莫斯讲授的中子物理课程笔记，系统阐述了中子慢化、扩散、共振吸收、链式反应理论及反应堆临界尺寸计算等基础物理原理。整理了费米参与或主导的15项相关专利，详细描述了从天然铀－石墨堆的指数实验、冷却系统设计、控制棒操作到材料纯度测试等工程实现方案。这些文献此前未收入费米的《论文集》，为理解核反应堆从物理理论走向实际建造提供了珍贵的一手资料。
作者介绍
萨尔瓦托雷·埃斯波西托（SALVATORE ESPOSITO），意大利国家核物理研究所的物理史教授兼理论物理副教授，被公认为马约拉纳研究的权威。
目录
Introduction
Some Background to my Notes on Fermi's Neutron Physics Lectures (Los Alamos, 1945), by Anthony P. French
Neutron Physics
  Neutron Physics - A Course of Lectures by E. Fermi
  1. Sources of Neutrons
    1.1  Natural Sources
      1.1.1  Alpha Particle Sources
      1.1.2  Photo-Neutron Sources
    1.2  Artificial Sources
  2. The Isotopic Chart: Nuclear Masses and Energies
    2.1  The Isotopic Chart
    2.2  Energy Balance of Reactions
    2.3  The Binding Energies of Nuclei
    2.4  The Packing Fraction Curve
  3. The Scattering of Neutrons (Part 1)
    3.1  General Considerations
    3.2  Elementary Theoretical Treatment
      3.2.1  Elastic Scattering
      3.2.2  Inelastic (n,n) Scattering
      3.2.3  Inelastic (n,m) Scattering
      3.2.4  Inelastic (n,γ) Scattering
  4. Resonance: Models of the Nucleus
    4.1  Resonance in Nuclear Reactions
    4.2  Two Models of the Nucleus
  5. The Scattering of Neutrons (Part 2)
    5.1  The Solution of Schrdinger's Equation
    5.2  The Scattering Cross Section
    5.3  Neutron-Proton scattering
    5.4  The Breit-Wigner Formula
    5.5  The Effect of Chemical Binding on Scattering
    5.6  Scattering Cross Section for Other Elements
  6. Slow Neutrons as Waves
    6.1  Introduction
    6.2  Isotopic Effects
    6.3  Penetration by Thermal Neutrons
    6.4  The Production of Very Slow Neutrons
    6.5  Reflection and Refraction
  7. The Slowing Down of Neutrons
    7.1  Introduction
    7.2  The Energy Loss in One Collision
    7.3  Many Collisions
    7.4  The Spatial Distribution of Slowed Neutrons
    7.5  Theory of the Spatial Distribution
  8. The Age Equation
    8.1  Derivation of the Age Equation
      8.1.1  Diffusion
      8.1.2  Energy Drift
    8.2  The Problem of a Point Source
  9. Thermal Neutron Distributions
    9.1  The Basic Equation

    9.2  Point Source of Slow Neutrons
    9.3  Point Source of Fast Neutrons
    9.4  Bounded Media
    9.5  The Measurement of Diffusion Length
    9.6  Diffusion in Graphite
    9.7  Some Useful Quantities and Relationships
  10. The Reflection of Neutrons
    10.1  Introduction
    10.2  Approximate Solution of the Escape Problem
    10.3  Exact Solution by Integral Equation Method
    10.4  The Albedo
    10.5  Measurement of the Albedo
  11. The Stability of Nuclei
    11.1  The Binding Energy of a Nucleus
      11.1.1  The Liquid Drop Model
      11.1.2  Nuclear Composition
      11.1.3  Coulomb Forces
      11.1.4  The Odd-Even Effect
    11.2  Determination of Coefficients
    11.3  The Binding of Neutrons to Nuclei
  12. Nuclear Fission
    12.1  The Possibility of Fission
    12.2  Limitations on the Occurrence of Fission
    12.3  The Liquid Drop Model in Fission
    12.4  The Particles of Fission
    12.5  Cross Sections for Fission and Other Processes
  13. The Possibility of a Chain Reaction
    13.1  The Properties of Natural Uranium
      13.1.1  The High Energy Region
      13.1.2  The Thermal Region
    13.2  Moderators
    13.3  Homogeneous and Lumped Graphite Piles
    13.4  The Possibility of a Homogeneous Pile
  14. The Heterogeneous Pile
    14.1  The Design of a Lumped Pile
    14.2  The Determination of Pile Constants
      14.2.1  The Magnitude of
      14.2.2  (1  fR)
      14.2.3  Calculation of fT
    14.3  Reproduction Factor and Critical Size
  15. The Time Dependence of a Pile
    15.1  The Time-Dependent Equations
    15.2  Evaluation of the Period
  16. Practical Aspects of Pile Physics
    16.1  The Determination of k
    16.2  The Study of Pile Materials
    16.3  Energy and Radiation Production
    16.4  Shielding
    16.5  Other Types of Piles
  17. Fast Reactors

    17.1  Elementary Considerations
    17.2  The Integral Equation to the Neutron Distribution
    17.3  The Critical Size for a Fast Reactor
    17.4  Supercritical Reactors
  Problems and Exercises
Nuclear Reactors
  1. Process for the Production of Radioactive Substances  by E. Fermi, E. Amaldi, B. Pontecorvo, F. Rasetti and E. Segré
  2. Test Exponential Pile  by E. Fermi
  3. Method of Operating a Neutronic Reactor  by E. Fermi and L. Szilard
    3.1  The Chain Fission Reaction
      3.1.1  Neutron Loss by Absorption in Uranium
      3.1.2  Neutron Loss by Absorption in the Moderator
      3.1.3  Neutron Loss by Absorption by Impurities in the System
      3.1.4  Exterior Neutron Loss in a Neutronic Reactor of Practical Size
    3.2  Measurement of Neutron Losses
    3.3  An Illustrative Neutronic Reactor having a Solid Moderator
    3.4  Graphite in the Reactor
    3.5  An Illustrative Neutronic Reactor having a Liquid Moderator
    3.6  Neutronic Reactors with Other Moderators
    3.7  Reduction of Losses Due to Resonance Capture
    3.8  Reduction of Neutron Losses Due to Impurities in the Material
    3.9  Effect of a Cooling System in a Neutronic Reactor
    3.10  An Illustrative Gas-Cooled Neutronic Reactor
    3.11  An Illustrative Liquid-Cooled Neutronic Reactor
    3.12  Use of Different Lattices in the Same Neutronic Reactor
    3.13  Critical and Operating Sizes of Neutronic Reactors
    3.14  Control of the Neutronic Reaction by Variation of Neutron Losses in or from the Neutronic Reactor
    3.15  Uses of Neutronic Reactors
  4. Chain Reacting System  by E. Fermi and M.C. Leverett
  5. Neutronic Reactor I  by E. Fermi
  6. Air Cooled Neutronic Reactor  by E. Fermi and L. Szilard
  7. Testing Material in a Neutronic Reactor  by E. Fermi and H.L. Anderson
  8. Neutron Velocity Selector  by E. Fermi
  9. Neutronic Reactor II  by E. Fermi and L. Szilard
  10. Neutronic Reactor III  by E. Fermi, W.H. Zinn and H.L. Anderson
  11. Neutronic Reactor IV  by E. Fermi and W.H. Zinn
  12. Method of Testing Thermal Neutron Fissionable Material for Purity  by E. Fermi and H.L. Anderson
  13. Method of Sustaining a Neutronic Chain Reacting System  by E. Fermi and M.C. Leverett
  14. Neutronic Reactor Shield  by E. Fermi and W.H. Zinn
Appendix A: Other Documents not Reported in this Volume
Appendix B: The Complete List of Fermi's Papers
Bibliography
Index

内容大纲

作者介绍

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