Nuclear Reactor Physics 3rd edition by Weston Stacey – Ebook PDF Instant Download/Delivery: 3527413669 , 978-3527413669
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Product details:
ISBN 10: 3527413669
ISBN 13: 978-3527413669
Author: Weston Stacey
Nuclear Reactor Physics 3rd Table of contents:
Part 1: Basic Reactor Physics
Chapter 1: Neutron–Nuclear Reactions
1.1 Neutron-Induced Nuclear Fission
1.2 Neutron Capture
1.3 Neutron Elastic Scattering
1.4 Summary of Cross Section Data
1.5 Evaluated Nuclear Data Files
1.6 Elastic Scattering Kinematics
References
Further Readings
Problems
Chapter 2: Neutron Chain Fission Reactors
2.1 Neutron Chain Fission Reactions
2.2 Criticality
2.3 Time Dependence of a Neutron Fission Chain Assembly
2.4 Classification of Nuclear Reactors
References
Further Readings
Problems
Chapter 3: Neutron Diffusion and Transport Theory
3.1 Derivation of One-Speed Diffusion Theory
3.2 Solutions of the Neutron Diffusion Equation in Nonmultiplying Media
3.3 Diffusion Kernels and Distributed Sources in a Homogeneous Medium
3.4 Albedo Boundary Condition
3.5 Neutron Diffusion and Migration Lengths
3.6 Bare Homogeneous Reactor
3.7 Reflected Reactor
3.8 Homogenization of a Heterogeneous Fuel–Moderator Assembly
3.9 Control Rods
3.10 Numerical Solution of Diffusion Equation
3.11 Nodal Approximation
3.12 Transport Methods
References
Further Readings
Problems
Chapter 4: Neutron Energy Distribution
4.1 Analytical Solutions in an Infinite Medium
4.2 Multigroup Calculation of Neutron Energy Distribution in an Infinite Medium
4.3 Resonance Absorption
4.4 Multigroup Diffusion Theory
References
Further Reading
Problems
Chapter 5: Nuclear Reactor Dynamics
5.1 Delayed Fission Neutrons
5.2 Point Kinetics Equations
5.3 Period–Reactivity Relations
5.4 Approximate Solutions of the Point Neutron Kinetics Equations
5.5 Delayed Neutron Kernel and Zero-Power Transfer Function
5.6 Experimental Determination of Neutron Kinetics Parameters
5.7 Reactivity Feedback
5.8 Perturbation Theory Evaluation of Reactivity Temperature Coefficients
5.9 Reactor Stability
5.10 Measurement of Reactor Transfer Functions
5.11 Reactor Transients with Feedback
5.12 Reactor Fast Excursions
5.13 Numerical Methods
References
Further Reading
Problems
Chapter 6: Fuel Burnup
6.1 Changes in Fuel Composition
6.2 Samarium and Xenon
6.3 Fertile-to-Fissile Conversion and Breeding
6.4 Simple Model of Fuel Depletion
6.5 Fuel Reprocessing and Recycling
6.6 Radioactive Waste
6.7 Burning Surplus Weapons-Grade Uranium and Plutonium
6.8 Utilization of Uranium Energy Content
6.9 Transmutation of Spent Nuclear Fuel
6.10 Closing the Nuclear Fuel Cycle
References
Further Reading
Problems
Chapter 7: Nuclear Power Reactors
7.1 Pressurized Water Reactors
7.2 Boiling Water Reactors
7.3 Pressure Tube Heavy Water–Moderated Reactors
7.4 Pressure Tube Graphite-Moderated Reactors
7.5 Graphite-Moderated Gas-Cooled Reactors
7.6 Liquid Metal Fast Reactors
7.7 Other Power Reactors
7.8 Characteristics of Power Reactors
7.9 Advanced Generation-III Reactors
7.10 Advanced Generation-IV Reactors
7.11 Advanced Subcritical Reactors
7.12 Nuclear Reactor Analysis
7.13 Interaction of Reactor Physics and Reactor Thermal Hydraulics
References
Further Readings
Problems
Chapter 8: Reactor Safety
8.1 Elements of Reactor Safety
8.2 Reactor Safety Analysis
8.3 Quantitative Risk Assessment
8.4 Reactor Accidents
8.5 Passive Safety
References
Further Readings
Problems
Part 2: Advanced Reactor Physics
Chapter 9: Neutron Transport Theory
9.1 Neutron Transport Equation
9.2 Integral Transport Theory
9.3 Collision Probability Methods
9.4 Interface Current Methods in Slab Geometry
9.5 Multidimensional Interface Current Methods
9.6 Spherical Harmonics (PL) Methods in One-Dimensional Geometries
9.7 Multidimensional Spherical Harmonics (PL) Transport Theory
9.8 Discrete Ordinates Methods in One-Dimensional Slab Geometry
9.9 Discrete Ordinates Methods in One-Dimensional Spherical Geometry
9.10 Multidimensional Discrete Ordinates Methods
9.11 Even-Parity Transport Formulation
9.12 Monte Carlo Methods
References
Further Readings
Problems
Chapter 10: Neutron Slowing Down
10.1 Elastic Scattering Transfer Function
10.2 P1 and B1 Slowing-Down Equations
10.3 Diffusion Theory
10.4 Continuous Slowing-Down Theory
10.5 Multigroup Discrete Ordinates Transport Theory
References
Further Reading
Problems
Chapter 11: Resonance Absorption
11.1 Resonance Cross Sections
11.2 Widely Spaced Single-Level Resonances in a Heterogeneous Fuel–Moderator Lattice
11.3 Calculation of First-Flight Escape Probabilities
11.4 Unresolved Resonances
11.5 Multiband Treatment of Spatially Dependent Self-Shielding
11.6 Resonance Cross Section Representations *
References
Further Reading
Problems
Chapter 12: Neutron Thermalization
12.1 Double Differential Scattering Cross Section for Thermal Neutrons
12.2 Neutron Scattering from a Monatomic Maxwellian Gas
12.3 Thermal Neutron Scattering from Bound Nuclei
12.4 Calculation of the Thermal Neutron Spectra in Homogeneous Media
12.5 Calculation of Thermal Neutron Energy Spectra in Heterogeneous Lattices
12.6 Pulsed Neutron Thermalization
References
Further Readings
Problems
Chapter 13: Perturbation and Variational Methods
13.1 Perturbation Theory Reactivity Estimate
13.2 Adjoint Operators and Importance Function
13.3 Variational/Generalized Perturbation Reactivity Estimate
13.4 Variational/Generalized Perturbation Theory Estimates of Reaction Rate Ratios in Critical Reactors
13.5 Variational/Generalized Perturbation Theory Estimates of Reaction Rates
13.6 Variational Theory
13.7 Variational Estimate of Intermediate Resonance Integral
13.8 Heterogeneity Reactivity Effects
13.9 Variational Derivation of Approximate Equations
13.10 Variational Even-Parity Transport Approximations
13.11 Boundary Perturbation Theory
References
Further Reading
Problems
Chapter 14: Homogenization
14.1 Equivalent Homogenized Cross Sections
14.2 ABH Collision Probability Method
14.3 Blackness Theory
14.4 Fuel Assembly Transport Calculations
14.5 Homogenization Theory
14.6 Equivalence Homogenization Theory
14.7 Multiscale Expansion Homogenization Theory
14.8 Flux Detail Reconstruction
References
Further Readings
Problems
Chapter 15: Nodal and Synthesis Methods
15.1 General Nodal Formalism
15.2 Conventional Nodal Methods
15.3 Transverse Integrated Nodal Diffusion Theory Methods
15.4 Transverse Integrated Nodal Integral Transport Theory Models
15.5 Transverse Integrated Nodal Discrete Ordinates Method
15.6 Finite-Element Coarse-Mesh Methods
15.7 Variational Discrete Ordinates Nodal Method
15.8 Variational Principle for Multigroup Diffusion Theory
15.9 Single-Channel Spatial Synthesis
15.10 Multichannel Spatial Synthesis
15.11 Spectral Synthesis
References
Further Readings
Problems
Chapter 16: Space–Time Neutron Kinetics
16.1 Flux Tilts and Delayed Neutron Holdback
16.2 Spatially Dependent Point Kinetics
16.3 Time Integration of the Spatial Neutron Flux Distribution
16.4 Stability
16.5 Xenon Spatial Oscillations
16.6 Stochastic Kinetics
References
Further Readings
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