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Fundamentals of Nuclear Reactor Physics
 
 

Fundamentals of Nuclear Reactor Physics, 1st Edition

 
Fundamentals of Nuclear Reactor Physics, 1st Edition,Elmer Lewis,ISBN9780123706317
 
 
 

  

Academic Press

9780123706317

9780080560434

280

260 X 184

A first of its kind text on the essential nuclear physics employed in the design and operation of nuclear reactors.

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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

Description

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.

Readership

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

Elmer Lewis

Ph.D.

Affiliations and Expertise

Northwestern University, Department Of Mechanical Engineering, Robert R. McCormick School of Eng. & Applied Science, Evanston, IL, USA

Fundamentals of Nuclear Reactor Physics, 1st Edition

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
 
 
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