Fundamentals of Nuclear Reactor Physics

Elmer E. Lewis Ph.D.0123706319, 9780123706317, 9780080560434

This new streamlined text offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation. The book includes numerous worked-out examples and end-of-chapter questions to help reinforce the knowledge presented. This textbook offers an engineering-oriented introduction to nuclear physics, with a particular focus on how those physics are put to work in the service of generating nuclear-based power, particularly the importance of neutron reactions and neutron behavior. Engineering students will find this applications-oriented approach, with many worked-out examples, more accessible and more meaningful as they aspire to become future nuclear engineers. · A clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release · In-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution · Ample worked-out examples and over 100 end-of-chapter problems

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Table of contents :
cover.jpg……Page 1
Dedication……Page 2
Preface……Page 3
Introduction……Page 6
Nuclear Reaction Fundamentals……Page 7
Reaction Equations……Page 8
Energetics……Page 10
The Curve of Binding Energy……Page 12
Fusion Reactions……Page 13
Fission Reactions……Page 14
Energy Release and Dissipation……Page 15
Neutron Multiplication……Page 17
Fission Products……Page 18
Fissile and Fertile Materials……Page 21
Radioactive Decay……Page 23
Saturation Activity……Page 25
Decay Chains……Page 26
Bibliography……Page 28
Problems……Page 29
Neutron Cross Sections……Page 33
Microscopic and Macroscopic Cross Sections……Page 34
Uncollided Flux……Page 36
Nuclide Densities……Page 37
Enriched Uranium……Page 39
Reaction Types……Page 40
Neutron Energy Range……Page 42
Cross Section Energy Dependence……Page 44
Compound Nucleus Formation……Page 45
Resonance Cross Sections……Page 46
Threshold Cross Sections……Page 50
Fissionable Materials……Page 51
Neutron Scattering……Page 52
Elastic Scattering……Page 53
Slowing Down Decrement……Page 54
Inelastic Scattering……Page 56
Problems……Page 57
Introduction……Page 61
Nuclear Fuel Properties……Page 62
Neutron Moderators……Page 65
Neutron Energy Spectra……Page 67
Fast Neutrons……Page 69
The Slowing Down Density……Page 70
Energy Self-Shielding……Page 72
Thermal Neutrons……Page 74
Fast and Thermal Reactor Spectra……Page 76
Energy-Averaged Reaction Rates……Page 77
Fast Cross Section Averages……Page 79
Resonance Cross Section Averages……Page 82
Thermal Cross Section Averages……Page 83
Infinite Medium Multiplication……Page 85
Problems……Page 86
Core Composition……Page 89
Light Water Reactors……Page 92
Heavy Water Reactors……Page 95
Graphite-Moderated Reactors……Page 96
RBMK Reactors……Page 97
Fast Reactor Lattices……Page 98
Thermal Reactor Lattices……Page 102
The Four Factor Formula……Page 103
Fast Fission Factor……Page 105
Resonance Escape Probability……Page 106
Thermal Utilization and eta_Tau……Page 110
k_infinity Reconsidered……Page 111
Pressurized Water Reactor Example……Page 112
Bibliography……Page 114
Introduction……Page 118
Infinite Medium Nonmultiplying Systems……Page 119
Infinite Medium Multiplying Systems……Page 120
Finite Multiplying Systems……Page 122
Multiplying Systems Behavior……Page 123
Delayed Neutron Kinetics……Page 126
Kinetics Equations……Page 127
Step Reactivity Changes……Page 129
Reactor Period……Page 130
Prompt Jump Approximation……Page 134
Rod Drop……Page 135
Prologue to Reactor Dynamics……Page 136
Problems……Page 138
Introduction……Page 142
Spatial Neutron Balance……Page 143
Diffusion Approximation……Page 145
Source Free Example……Page 146
Uniform Source Example……Page 147
Boundary Conditions……Page 148
Vacuum Boundaries……Page 149
Surface Sources and Albedos……Page 150
Interface Conditions……Page 151
Nonmultiplying Systems-Spherical Geometry……Page 152
Point Source Example……Page 153
Two Region Example……Page 154
Diffusion Approximation Validity……Page 156
Diffusion Length……Page 157
Uncollided Flux Revisited……Page 158
Subcritical Assemblies……Page 160
The Critical Reactor……Page 163
Bibliography……Page 165
Problems……Page 166
The Time-Independent Diffusion Equation……Page 169
Uniform Reactors……Page 171
Finite Cylindrical Core……Page 172
Reactor Power……Page 174
Two Group Approximation……Page 176
Migration Length……Page 180
Leakage and Design……Page 181
Reflected Reactors……Page 182
Axial Reflector Example……Page 183
Reflector Savings and Flux Flattening……Page 186
Reactivity Worth……Page 188
Partially Inserted Control Rod……Page 190
Control Rod Bank Insertion……Page 192
Problems……Page 197
Core Power Distribution……Page 201
Finite Cylindrical Core……Page 202
Uniform Cylindrical Core Example……Page 205
Heat Source Characterization……Page 206
Steady State Temperatures……Page 207
Pressurized Water Reactor Example……Page 211
Thermal Transients……Page 213
Fuel Temperature Transient Examples……Page 214
Coolant Temperature Transients……Page 215
Problems……Page 217
Reactivity Coefficients……Page 222
Fuel Temperature Coefficient……Page 224
Moderator Temperature Coefficient……Page 226
Composite Coefficients……Page 228
Isothermal Temperature Coefficient……Page 229
Power Coefficient……Page 230
Excess Reactivity and Shutdown Margin……Page 231
Reactor Transients……Page 233
Reactor Dynamics Model……Page 234
Transient Analysis……Page 235
Problems……Page 239
Reactivity Control……Page 243
Fission Product Buildup and Decay……Page 245
Xenon Poisoning……Page 247
Samarium Poisoning……Page 250
Fissionable Nuclide Concentrations……Page 252
Burnable Poisons……Page 255
Fission Product and Actinide Inventories……Page 257
Problems……Page 259
Index……Page 263