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
Author(s): Elmer E. Lewis Ph.D.
Edition: 1
Publisher: Academic Press
Year: 2008
Language: English
Commentary: Complete with TOC and appendices.
Pages: 312
Front Cover
Dedication
TOC
Preface
1. Nuclear Reactions
Introduction
Nuclear Reaction Fundamentals
Reaction Equations
Notation
Energetics
The Curve of Binding Energy
Fusion Reactions
Fission Reactions
Energy Release and Dissipation
Neutron Multiplication
Fission Products
Fissile and Fertile Materials
Radioactive Decay
Saturation Activity
Decay Chains
Bibliography
Problems
2. Neutron Interactions
Introduction
Neutron Cross Sections
Microscopic and Macroscopic Cross Sections
Uncollided Flux
Nuclide Densities
Enriched Uranium
Reaction Types
Neutron Energy Range
Cross Section Energy Dependence
Compound Nucleus Formation
Resonance Cross Sections
Threshold Cross Sections
Fissionable Materials
Neutron Scattering
Elastic Scattering
Slowing Down Decrement
Inelastic Scattering
Bibliography
Problems
3. Neutron Distributions in Energy
Introduction
Nuclear Fuel Properties
Neutron Moderators
Neutron Energy Spectra
Fast Neutrons
Neutron Slowing Down
The Slowing Down Density
Energy Self-Shielding
Thermal Neutrons
Fast and Thermal Reactor Spectra
Energy-Averaged Reaction Rates
Fast Cross Section Averages
Resonance Cross Section Averages
Thermal Cross Section Averages
Infinite Medium Multiplication
Bibliography
Problems
4. The Power Reactor Core
Introduction
Core Composition
Light Water Reactors
Heavy Water Reactors
Graphite-Moderated Reactors
RBMK Reactors
Fast Reactors
Fast Reactor Lattices
Thermal Reactor Lattices
The Four Factor Formula
Fast Fission Factor
Resonance Escape Probability
Thermal Utilization and eta_Tau
k_infinity Reconsidered
Pressurized Water Reactor Example
Bibliography
5. Reactor Kinetics
Introduction
Neutron Balance Equations
Infinite Medium Nonmultiplying Systems
Infinite Medium Multiplying Systems
Finite Multiplying Systems
Multiplying Systems Behavior
Delayed Neutron Kinetics
Kinetics Equations
Reactivity Formulation
Step Reactivity Changes
Reactor Period
Prompt Jump Approximation
Rod Drop
Source Jerk
Rod Oscillator
Prologue to Reactor Dynamics
Bibliography
Problems
6. Spatial Diffusion of Neutrons
Introduction
The Neutron Diffusion Equation
Spatial Neutron Balance
Diffusion Approximation
Nonmultiplying Systems-Plane Geometry
Source Free Example
Uniform Source Example
Boundary Conditions
Vacuum Boundaries
Reflected Boundaries
Surface Sources and Albedos
Interface Conditions
Boundary Conditions in Other Geometries
Nonmultiplying Systems-Spherical Geometry
Point Source Example
Two Region Example
Diffusion Approximation Validity
Diffusion Length
Uncollided Flux Revisited
Multiplying Systems
Subcritical Assemblies
The Critical Reactor
Bibliography
Problems
7. Neutron Distributions in Reactors
Introduction
The Time-Independent Diffusion Equation
Uniform Reactors
Finite Cylindrical Core
Reactor Power
Neutron Leakage
Two Group Approximation
Migration Length
Leakage and Design
Reflected Reactors
Axial Reflector Example
Reflector Savings and Flux Flattening
Control Poisons
Reactivity Worth
Partially Inserted Control Rod
Control Rod Bank Insertion
Bibliography
Problems
8. Energy Transport
Introduction
Core Power Distribution
Finite Cylindrical Core
Uniform Cylindrical Core Example
Heat Transport
Heat Source Characterization
Steady State Temperatures
Pressurized Water Reactor Example
Thermal Transients
Fuel Temperature Transient Examples
Coolant Temperature Transients
Bibliography
Problems
9. Reactivity Feedback
Introduction
Reactivity Coefficients
Fuel Temperature Coefficient
Moderator Temperature Coefficient
Fast Reactor Temperature Coefficients
Composite Coefficients
Prompt Coefficient
Isothermal Temperature Coefficient
Power Coefficient
Temperature and Power Defects
Excess Reactivity and Shutdown Margin
Reactor Transients
Reactor Dynamics Model
Transient Analysis
Bibliography
Problems
10. Long-Term Core Behavior
Introduction
Reactivity Control
Fission Product Buildup and Decay
Xenon Poisoning
Samarium Poisoning
Fuel Depletion
Fissionable Nuclide Concentrations
Burnable Poisons
Fission Product and Actinide Inventories
Bibliography
Problems
APPENDIX
A. Useful Mathematical Relationships
Derivatives and Integrals
Definite Integrals
Hyperbolic Functions
Expansions
Integration by Parts
Derivative of an Integral
First-Order Differential Equations
Second-Order Differential Equations
V2 and dV in Various Coordinate Systems
B. Bessel’s Equation and Functions
C. Derivation of Neutron Diffusion Properties
The Transport Equation
The Diffusion Approximation
Partial Currents
D. Fuel Element Heat Transfer
E. Nuclear Data
Index
