Stacey Weston M. Nuclear Reactor Physics

Wiley-Interscience, 2001. — 736 p.An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices
Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature.
Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems.
Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.Basic Reactor Physics
Neutron Nuclear Reactions
Neutron-Induced Nuclear Fission
Neutron Capture
Neutron Elastic Scattering
Summary of Cross-Section Data
Evaluated Nuclear Data Files
Elastic Scattering Kinematics
Neutron Chain Fission Reactors
Neutron Chain Fission Reactions
Criticality
Time Dependence of a Neutron Fission
Classification of Nuclear Reactors
Neutron Diffusion Theory
Derivation of One-Speed Diffusion Theory
Solutions of the Neutron Diffusion Equation
Diffusion Kernels and Distributed Sources
Albedo Boundary Condition
Neutron Diffusion and Migration Lengths
Bare Homogeneous Reactor
Reflected Reactor
Homogenization of a Heterogeneous
Control Rods
Numerical Solution of Diffusion Equation
Nodal Approximation
Neutron Energy Distribution
Analytical Solutions in an Infinite Medium
Multigroup Calculation of Neutron Energy
Resonance Absorption
Multigroup Diffusion Theory
Nuclear Reactor Dynamics
Delayed Fission Neutrons
Point Kinetics Equations
Period-Reactivity Relations
Approximate Solutions of the Point Neutron
Delayed Neutron Kernel and Zero-Power
Experimental Determination of Neutron
Reactivity Feedback
Perturbation Theory Evaluation of Reactivity
Reactor Stability
Measurement of Reactor Transfer Functions
Reactor Transients with Feedback
Reactor Fast Excursions
Numerical Methods
Fuel Burnup
Changes in Fuel Composition
Nuclear Power Reactors
Pressurized Water Reactors
Boiling Water Reactors
Pressure Tube Heavy Water-Moderated Reactors
Pressure Tube Graphite-Moderated Reactors
Graphite Moderated Gas-Coolcd Reactors
Liquid-Metal Fast Breeder Reactors
Other Power Reactors
Characteristics of Power Reactors
Advanced Reactors
Nuclear Reactor Analysis
Interaction of Reactor Physics and Reactor
Reactor Safety
Elements of Reactor Safety
Reactor Safety Analysis
Quantitative Risk Assessment
Reactor Accidents
Passive Safety
Advanced Reactor Physics
Neutron Transport Theory
Neutron Transport Equation
Integral Transport Theory
Isotropic Point Source
Collision Probability Methods
Interface Current Methods in Slab Geometry
Multidimensional Interface Current Methods
Spherical Harmonics (PL) Methods
Multidimensional Spherical Harmonics (PL)
Discrete Ordinates Methods in One-Dimensional Slab Geometry
Discrete Ordinates Methods in One-Dimensional Spherical Geometry
Multidimensional Discrete Ordinates Methods
Even-Parity Transport Formulation
Monte Carlo Methods
Neutron Slowing Down
Elastic Scattering Transfer Function
PI and B Slowing-Down Equations
Diffusion Theory
Continuous Slowing-Down Theory
Multigroup Discrete Ordinates Transport Theory
Resonance Absorption
Resonance Cross Sections
Widely Spaced Single-Level Resonances in a Heterogeneous Fuel-Moderator Lattice
Calculation of First-Flight Escape Probabilities
Unresolved Resonances
Multiband Treatment of Spatially Dependent Self-Shielding
Resonance Cross-Section Representations
Neutron Thermalization
Double Differential Scattering Cross Section for Thermal Neutrons
Neutron Scattering from a Monatomic Maxwellian Gas
Thermal Neutron Scattering from Bound Nuclei
Calculation of the Thermal Neutron Spectra in Homogeneous Media
Calculation of Thermal Neutron Energy Spectra in Heterogeneous Lattices
Pulsed Neutron Thermalization
Perturbation and Variational Methods
Perturbation Theory Reactivity Estimate
Adjoint Operators and Importance Function
Variational/Generalized Perturbation Reactivity Estimate
VariationallGeneralized Perturbation Theory Estimates of Reaction Rate Ratios in Critical Reactors
VariationaltGeneralized Perturbation Theory Estimates of Reaction Rates
Variational Theory
Variational Estimate of Intermediate Resonance Integral
Heterogeneity Reactivity Effects
Variational Derivation of Approximate Equations
Variational Even-Parity Transport Approximations
Boundary Perturbation Theory
Homogenization
Equivalent Homogenized Cross Sections
ABH Collision Probability Method
Blackness Theory
Fuel Assembly Transport Calculations
Homogenization Theory
Equivalence Homogenization Theory
Multiscale Expansion Homogenization Theory
Flux Detail Reconstruction
Nodal and Synthesis Methods
General Nodal Formalism
Conventional Nodal Mcthods
Transverse Integralcd Nodal Diffusion Theory Methods
SpaceTime Neutron Kinetics
Flux Tilts and Delayed Neutron Holdback
Spatially Dependent Point Kinetics
Time Integration of the Spatial Neutron Flux Distribution
Stability
Control
Xenon Spatial Oscillations
Stochastic Kinetics
Appendices
Some Useful Nuclear Data
Some Useful Mathematical Formulas
Step Functions, Delta Functions, and Other Exotic Beasts
Some Properties of Special Functions
Introduction to Matrices and Matrix Algebra
Introduction to Laplace TransformsErrata