Fundamentals of Nuclear Reactor Physics 1st Edition by Elmer Lewis ISBN 9780080560434 0080560431

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Product details:
ISBN 10: 0080560431
ISBN 13: 9780080560434
Author: Elmer Lewis

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.

Fundamentals of Nuclear Reactor Physics 1st Edition Table of contents:

Chapter 1 Nuclear Reactions

1.1 Introduction

1.2 Nuclear Reaction Fundamentals

Reaction Equations

Notation

Energetics

1.3 The Curve of Binding Energy

1.4 Fusion Reactions

1.5 Fission Reactions

Energy Release and Dissipation

Neutron Multiplication

Fission Products

1.6 Fissile and Fertile Materials

1.7 Radioactive Decay

Saturation Activity

Decay Chains

Chapter 2 Neutron Interactions

2.1 Introduction

2.2 Neutron Cross Sections

Microscopic and Macroscopic Cross Sections

Uncollided Flux

Nuclide Densities

Enriched Uranium

Cross Section Calculation Example

Reaction Types

2.3 Neutron Energy Range

2.4 Cross Section Energy Dependence

Compound Nucleus Formation

Resonance Cross Sections

Threshold Cross Sections

Fissionable Materials

2.5 Neutron Scattering

Elastic Scattering

Slowing Down Decrement

Inelastic Scattering

Chapter 3 Neutron Distributions in Energy

3.1 Introduction

3.2 Nuclear Fuel Properties

3.3 Neutron Moderators

3.4 Neutron Energy Spectra

Fast Neutrons

Neutron Slowing Down

Thermal Neutrons

Fast and Thermal Reactor Spectra

3.5 Energy-Averaged Reaction Rates

Fast Cross Section Averages

Resonance Cross Section Averages

Thermal Cross Section Averages

3.6 Infinite Medium Multiplication

Chapter 4 The Power Reactor Core

4.1 Introduction

4.2 Core Composition

Light Water Reactors

Heavy Water Reactors

Graphite-Moderated Reactors

RBMK Reactors

Fast Reactors

4.3 Fast Reactor Lattices

4.4 Thermal Reactor Lattices

The Four Factor Formula

Pressurized Water Reactor Example

Chapter 5 Reactor Kinetics

5.1 Introduction

5.2 Neutron Balance Equations

Infinite Medium Nonmultiplying Systems

Infinite Medium Multiplying Systems

Finite Multiplying Systems

5.3 Multiplying Systems Behavior

5.4 Delayed Neutron Kinetics

Kinetics Equations

Reactivity Formulation

5.5 Step Reactivity Changes

Reactor Period

Prompt Jump Approximation

5.6 Prologue to Reactor Dynamics

Chapter 6 Spatial Diffusion of Neutrons

6.1 Introduction

6.2 The Neutron Diffusion Equation

Spatial Neutron Balance

Diffusion Approximation

6.3 Nonmultiplying Systems—Plane Geometry

Source Free Example

Uniform Source Example

6.4 Boundary Conditions

Vacuum Boundaries

Reflected Boundaries

Surface Sources and Albedos

Interface Conditions

Boundary Conditions in Other Geometries

6.5 Nonmultiplying Systems—Spherical Geometry

Point Source Example

Two Region Example

6.6 Diffusion Approximation Validity

Diffusion Length

Uncollided Flux Revisited

6.7 Multiplying Systems

Subcritical Assemblies

The Critical Reactor

Chapter 7 Neutron Distributions in Reactors

7.1 Introduction

7.2 The Time-Independent Diffusion Equation

7.3 Uniform Reactors

Finite Cylindrical Core

Reactor Power

7.4 Neutron Leakage

Two Group Approximation

Migration Length

Leakage and Design

7.5 Reflected Reactors

Axial Reflector Example

Reflector Savings and Flux Flattening

7.6 Control Poisons

Reactivity Worth

Partially Inserted Control Rod

Control Rod Bank Insertion

Chapter 8 Energy Transport

8.1 Introduction

8.2 Core Power Distribution

Finite Cylindrical Core

Uniform Cylindrical Core Example

8.3 Heat Transport

Heat Source Characterization

Steady State Temperatures

Pressurized Water Reactor Example

8.4 Thermal Transients

Fuel Temperature Transient Examples

Coolant Temperature Transients

Chapter 9 Reactivity Feedback

9.1 Introduction

9.2 Reactivity Coefficients

Fuel Temperature Coefficient

Moderator Temperature Coefficient

Fast Reactor Temperature Coefficients

9.3 Composite Coefficients

Prompt Coefficient

Isothermal Temperature Coefficient

Power Coefficient

Temperature and Power Defects

9.4 Excess Reactivity and Shutdown Margin

9.5 Reactor Transients

Reactor Dynamics Model

Transient Analysis

Chapter 10 Long-Term Core Behavior

10.1 Introduction

10.2 Reactivity Control

10.3 Fission Product Buildup and Decay

Xenon Poisoning

Samarium Poisoning

10.4 Fuel Depletion

Fissionable Nuclide Concentrations

Burnable Poisons

10.5 Fission Product and Actinide Inventories

Appendices

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

▿2 and dV in Various Coordinate Systems

Appendix B Bessel’s Equation and Functions

Appendix C Derivation of Neutron Diffusion Properties

Appendix D Fuel Element Heat Transfer

Appendix E Nuclear Data

Index

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