Fundamentals of Nuclear Reactor Physics,
Edition 1
By Elmer E. Lewis, Ph.D.
Publication Date:
18 Jan 2008
Description
Fundamentals of Nuclear Reactor Physics 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 . It provides 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.
It provides in-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution. It includes ample worked-out examples and over 100 end-of-chapter problems.
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.
Key Features
- 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
- Full Solutions Manual
About the author
By Elmer E. Lewis, Ph.D., Northwestern University,
Department Of Mechanical Engineering, Robert R. McCormick School of Eng. & Applied Science,
Evanston, IL, USA
Table of Contents
1. Nuclear Reactions
1.1 Introduction
1.2 Nuclear Reaction Fundamentals
1.3 The Curve of Binding Energy
1.4 Fusion Reactions
1.5 Fission Reactions
1.6 Fissile and Fertile Materials
1.7 Radioactive Decay
2. Neutron Interactions
2.1 Introduction
2.2 Neutron Cross Sections
2.3 Neutron Energy Range
2.4 Cross Section Energy Dependence
2.5 Neutron Scattering
3. Neutron Distributions in Energy
3.1 Introduction
3.2 Nuclear Fuel Properties
3.3 Neutron Moderators
3.4 Neutron Energy Spectra
3.5 Energy-Averaged Reaction Rates
3.6 Infinite Medium Multiplication:
4. The Power Reactor Core
4.1 Introduction
4.2 Core Composition
4.3 Fast Reactor Lattices
4.4 Thermal Reactor Lattices
5. Reactor Kinetics
5.1 Introduction
5.2 Neutron Balance Equations
5.3 Multiplying Systems Behavior
5.4 Delayed Neutron Kinetics
5.5 Step Reactivity Changes
5.6 Prolog to Reactor Dynamics
6. Spatial Diffusion of Neutrons
6.1 Introduction
6.2 The Neutron Diffusion Equation
6.3 Non-multiplying Systems- Plane Geometry
6.4 Boundary Conditions
6.5 Non-multiplying Systems- Spherical Geometry
6.6 Diffusion Approximation Validity
6.7 Multiplying Systems
7. Neutron Distributions in Reactors
7.1 Introduction
7.2 The Time-Independent Diffusion Equation
7.3 Uniform Reactors
7.4 Neutron Leakage
7.5 Reflected Reactors
7.6 Control Poisons
8. Energy Transport
8.1 Introduction
8.2 Core Power Distribution
8.3 Heat Transport
8.4 Thermal Transients
9. Reactivity Feedback
9.1 Introduction
9.2 Reactivity Coefficients
9.3 Composite Coefficients
9.4 Excess Reactivity and Shutdown Margin
9.5 Reactor Transients
10. Long Term Core Behavior
10.1 Introduction
10.2 Reactivity Control
10.3 Fission Product Buildup and Decay
10.4 Fuel Depletion
10.5 Fission Product and Actinides Inventories
Appendices
A. Useful Mathematics
B. Bessel’s Equation and Functions
C. Derivation of Neutron Diffusion Properties
D. Fuel Element Heat Transfer
E. Nuclear Data
1.1 Introduction
1.2 Nuclear Reaction Fundamentals
1.3 The Curve of Binding Energy
1.4 Fusion Reactions
1.5 Fission Reactions
1.6 Fissile and Fertile Materials
1.7 Radioactive Decay
2. Neutron Interactions
2.1 Introduction
2.2 Neutron Cross Sections
2.3 Neutron Energy Range
2.4 Cross Section Energy Dependence
2.5 Neutron Scattering
3. Neutron Distributions in Energy
3.1 Introduction
3.2 Nuclear Fuel Properties
3.3 Neutron Moderators
3.4 Neutron Energy Spectra
3.5 Energy-Averaged Reaction Rates
3.6 Infinite Medium Multiplication:
4. The Power Reactor Core
4.1 Introduction
4.2 Core Composition
4.3 Fast Reactor Lattices
4.4 Thermal Reactor Lattices
5. Reactor Kinetics
5.1 Introduction
5.2 Neutron Balance Equations
5.3 Multiplying Systems Behavior
5.4 Delayed Neutron Kinetics
5.5 Step Reactivity Changes
5.6 Prolog to Reactor Dynamics
6. Spatial Diffusion of Neutrons
6.1 Introduction
6.2 The Neutron Diffusion Equation
6.3 Non-multiplying Systems- Plane Geometry
6.4 Boundary Conditions
6.5 Non-multiplying Systems- Spherical Geometry
6.6 Diffusion Approximation Validity
6.7 Multiplying Systems
7. Neutron Distributions in Reactors
7.1 Introduction
7.2 The Time-Independent Diffusion Equation
7.3 Uniform Reactors
7.4 Neutron Leakage
7.5 Reflected Reactors
7.6 Control Poisons
8. Energy Transport
8.1 Introduction
8.2 Core Power Distribution
8.3 Heat Transport
8.4 Thermal Transients
9. Reactivity Feedback
9.1 Introduction
9.2 Reactivity Coefficients
9.3 Composite Coefficients
9.4 Excess Reactivity and Shutdown Margin
9.5 Reactor Transients
10. Long Term Core Behavior
10.1 Introduction
10.2 Reactivity Control
10.3 Fission Product Buildup and Decay
10.4 Fuel Depletion
10.5 Fission Product and Actinides Inventories
Appendices
A. Useful Mathematics
B. Bessel’s Equation and Functions
C. Derivation of Neutron Diffusion Properties
D. Fuel Element Heat Transfer
E. Nuclear Data
Book details
ISBN:
9780123706317
Page Count: 312
Retail Price
:
£81.99
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Instructor Resources
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Audience
Junior and Senior Undergraduate engineering students in mechanical, nuclear, and materials engineering , Junior and Senior Undergraduate students in physics, Graduate Students in other engineering disciplines in need of an introductory text, including those in Electrical engineering and Environmental and Health and Safety engineering, Professional Engineers in Mechanical, Nuclear and Materials Engineering, Managers and Technicians in the power-generation industries, Administrators charged with regulatory and safety issues affecting the nuclear power industry
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