
- English
- ePUB (mobile friendly)
- Available on iOS & Android
About this book
An introductory text for broad areas of nuclear reactor physics
Nuclear Reactor Physics and Engineering offers information on analysis, design, control, and operation of nuclear reactors. The authorâa noted expert on the topicâexplores the fundamentals and presents the mathematical formulations that are grounded in differential equations and linear algebra.
The book puts the focus on the use of neutron diffusion theory for the development of techniques for lattice physics and global reactor system analysis. The author also includes recent developments in numerical algorithms, including the Krylov subspace method, and the MATLAB software, including the Simulink toolbox, for efficient studies of steady-state and transient reactor configurations. In addition, nuclear fuel cycle and associated economics analysis are presented, together with the application of modern control theory to reactor operation. This important book:
- Provides a comprehensive introduction to the fundamental concepts of nuclear reactor physics and engineering
- Contains information on nuclear reactor kinetics and reactor design analysis
- Presents illustrative examples to enhance understanding
- Offers self-contained derivation of fluid conservation equations
Written for undergraduate and graduate students in nuclear engineering and practicing engineers, Nuclear Reactor Physics and Engineering covers the fundamental concepts and tools of nuclear reactor physics and analysis.
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Information
Table of contents
- Cover
- Table of Contents
- Preface
- Permissions and Copyrights
- List of Tables
- List of Figures
- Chapter 1: Nuclear Power Plants
- Chapter 2: Neutronânucleus Reaction and Neutron Cross Section
- Chapter 3: Neutron Flux, Reaction Rate, and Effective Cross Section
- Chapter 4: Derivation of the Neutron Diffusion Equation
- Chapter 5: Applications of the OneâGroup Neutron Diffusion Equation
- Chapter 6: Numerical Solution of the Neutron Diffusion Equation
- Chapter 7: Applications of the TwoâGroup Neutron Diffusion Equation
- Chapter 8: Nuclear Reactor Kinetics
- Chapter 9: Fast Neutron Spectrum Calculation
- Chapter 10: Perturbation Theory and Adjoint Flux
- Chapter 11: Lattice Physics Analysis of Heterogeneous Cores
- Chapter 12: Nuclear Fuel Cycle Analysis and Management
- Chapter 13: ThermalâHydraulic Analysis of Reactor Systems
- Chapter 14: Power Coefficients of Reactivity
- Chapter 15: Nuclear Energy Economics
- Chapter 16: SpaceâTime Kinetics and Reactor Control
- Chapter 17: Elements of Neutron Transport Theory
- Appendix A: Key Physical Constants
- Appendix B: Comparison of Major Reactor Types
- Appendix C: Special Mathematical Functions
- Appendix D: Integral Transforms
- Appendix E: Calculus of Variation for Optimal Control Formulation
- Appendix F: Kalman Filter Algorithm
- Answers to Selected Problems
- Index
- End User License Agreement