Neutron Physics for Nuclear Reactors: Unpublished Writings by Enrico Fermi

by Esposito, S.; Pisanti, O.

• ISBN13: 9789814291224
• ISBN10: 9814291226
• Format: Hardcover
• Copyright: 2010-07-30
• Publisher: World Scientific Pub Co Inc

Summary

This unique volume gives an accurate and very detailed description of the functioning and operation of basic nuclear reactors, as emerging from yet unpublished papers by Nobel Laureate Enrico Fermi. In the first part, the entire course of lectures on Neutron Physics delivered by Fermi at Los Alamos is reported, according to the version made by Anthony P French. Here, the fundamental physical phenomena are described very clearly and comprehensively, giving the appropriate physics grounds for the functioning of nuclear piles. In the second part, all the patents issued by Fermi (and coworkers) on the functioning, construction and operation of several different kinds of nuclear reactors are reported. Here, the main engineering problems are encountered and solved by employing simple and practical methods, which are described in detail. This seminal work mainly caters to students, teachers and researchers working in nuclear physics and engineering, but it is of invaluable interest to historians of physics too, since the material presented here is entirely novel.

Table of Contents

Introduction	p. xi
Some Background to my Notes on Fermi's Neutron Physics Lectures (Los Alamos, 1945)	p. xxxi
Neutron Physics	p. 1
Neutron Physics - A Course of Lectures	p. 3
Sources of Neutrons	p. 5
Natural Sources	p. 5
Alpha Particle Sources	p. 5
Photo-Neutron Sources	p. 7
Artificial Sources	p. 7
The Isotopic Chart: Nuclear Masses and Energies	p. 9
The Isotopic Chart	p. 9
Energy Balance of Reactions	p. 10
The Binding Energies of Nuclei	p. 12
The Packing Fraction Curve	p. 12
The Scattering of Neutrons (Part 1)	p. 17
General Considerations	p. 17
Elementary Theoretical Treatment	p. 19
Elastic Scattering	p. 20
Inelastic (n, n) Scattering	p. 21
Inelastic (n, m) Scattering	p. 21
Inelastic (n, y) Scattering	p. 22
Resonance: Models of the Nucleus	p. 25
Resonance in Nuclear Reactions	p. 25
Two Models of the Nucleus	p. 27
The Scattering of Neutrons (Part 2)	p. 31
The Solution of Schrödinger's Equation	p. 31
The Scattering Cross Section	p. 34
Neutron-Proton scattering	p. 35
The Breit-Wigner Formula	p. 36
The Effect of Chemical Binding on Scattering	p. 38
Scattering Cross Section for Other Elements	p. 39
Slow Neutrons as Waves	p. 41
Introduction	p. 41
Isotopic Effects	p. 43
Penetration by Thermal Neutrons	p. 44
The Production of Very Slow Neutrons	p. 46
Reflection and Refraction	p. 47
The Slowing Down of Neutrons	p. 49
Introduction	p. 49
The Energy Loss in One Collision	p. 50
Many Collisions	p. 52
The Spatial Distribution of Slowed Neutrons	p. 54
Theory of the Spatial Distribution	p. 58
The Age Equation	p. 65
Derivation of the Age Equation	p. 65
Diffusion	p. 65
Energy Drift	p. 66
The Problem of a Point Source	p. 68
Thermal Neutron Distributions	p. 71
The Basic Equation	p. 71
Point Source of Slow Neutrons	p. 72
Point Source of Fast Neutrons	p. 72
Bounded Media	p. 73
The Measurement of Diffusion Length	p. 76
Diffusion in Graphite	p. 77
Some Useful Quantities and Relationships	p. 80
The Reflection of Neutrons	p. 81
Introduction	p. 81
Approximate Solution of the Escape Problem	p. 81
Exact Solution by Integral Equation Method	p. 82
The Albedo	p. 85
Measurement of the Albedo	p. 85
The Stability of Nuclei	p. 87
The Binding Energy of a Nucleus	p. 87
The Liquid Drop Model	p. 87
Nuclear Composition	p. 88
Coulomb Forces	p. 89
The Odd-Even Effect	p. 89
Determination of Coefficients	p. 90
The Binding of Neutrons to Nuclei	p. 91
Nuclear Fission	p. 93
The Possibility of Fission	p. 93
Limitations on the Occurrence of Fission	p. 95
The Liquid Drop Model in Fission	p. 97
The Particles of Fission	p. 99
Cross Sections for Fission and Other Processes	p. 102
The Possibility of a Chain Reaction	p. 105
The Properties of Natural Uranium	p. 105
The High Energy Region	p. 106
The Thermal Region	p. 107
Moderators	p. 107
Homogeneous and Lumped Graphite Piles	p. 108
The Possibility of a Homogeneous Pile	p. 112
The Heterogeneous Pile	p. 115
The Design of a Lumped Pile	p. 115
The Determination of Pile Constants	p. 116
The Magnitude of ¿	p. 116
(1 - fR)	p. 116
Calculation of fT	p. 117
Reproduction Factor and Critical Size	p. 119
The Time Dependence of a Pile	p. 123
The Time-Dependent Equations	p. 123
Evaluation of the Period	p. 125
Practical Aspects of Pile Physics	p. 131
The Determination of K	p. 131
The Study of Pile Materials	p. 132
Energy and Radiation Production	p. 133
Shielding	p. 134
Other Types of Piles	p. 136
Fast Reactors	p. 139
Elementary Considerations	p. 139
The Integral Equation to the Neutron Distribution	p. 141
The Critical Size for a Fast Reactor	p. 144
Supercritical Reactors	p. 151
Problems and Exercises	p. 153
Nuclear Reactors	p. 159
Process for the Production of Radioactive Substances	p. 161
Test Exponential Pile	p. 181
Method of Operating a Neutronic Reactor	p. 217
The Chain Fission Reaction	p. 223
Neutron Loss by Absorption in Uranium	p. 226
Neutron Loss by Absorption in the Moderator	p. 228
Neutron Loss by Absorption by Impurities in the System	p. 229
Exterior Neutron Loss in a Neutronic Reactor of Practical Size	p. 233
Measurement of Neutron Losses	p. 234
An Illustrative Neutronic Reactor having a Solid Moderator	p. 244
Graphite in the Reactor	p. 258
An Illustrative Neutronic Reactor having a Liquid Moderator	p. 262
Neutronic Reactors with Other Moderators	p. 269
Reduction of Losses Due to Resonance Capture	p. 271
Reduction of Neutron Losses Due to Impurities in the Material	p. 278
Effect of a Cooling System in a Neutronic Reactor	p. 285
An Illustrative Gas-Cooled Neutronic Reactor	p. 288
An Illustrative Liquid-Cooled Neutronic Reactor	p. 298
Use of Different Lattices in the Same Neutronic Reactor	p. 303
Critical and Operating Sizes of Neutronic Reactors	p. 307
Control of the Neutronic Reaction by Variation of Neutron Losses in or from the Neutronic Reactor	p. 315
Uses of Neutronic Reactors	p. 323
Chain Reacting System	p. 329
Neutronic Reactor I	p. 379
Air Cooled Neutronic Reactor	p. 409
Testing Material in a Neutronic Reactor	p. 447
Neutron Velocity Selector	p. 475
Neutronic Reactor II	p. 493
Neutronic Reactor III	p. 513
Neutronic Reactor IV	p. 523
Method of Testing Thermal Neutron Fissionable Material for Purity	p. 535
Method of Sustaining a Neutronic Chain Reacting System	p. 549
Neutronic Reactor Shield	p. 583
Other Documents not Reported in this Volume	p. 593
The Complete List of Fermi's Papers	p. 621
Bibliography	p. 653
Index	p. 657
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