Nuclear Reactor Analysis
1. Edition January 1976
672 Pages, Softcover
Wiley & Sons Ltd
A classic textbook for an introductory course in nuclear reactor
analysis that introduces the nuclear engineering student to the
basic scientific principles of nuclear fission chain reactions and
lays a foundation for the subsequent application of these
principles to the nuclear design and analysis of reactor
cores. This text introduces the student to the fundamental
principles governing nuclear fission chain reactions in a manner
that renders the transition to practical nuclear reactor design
methods most natural. The authors stress throughout the very
close interplay between the nuclear analysis of a reactor core and
those nonnuclear aspects of core analysis, such as thermalhydrolics
or materials studies, which play a major role in determining a
reactor design.
Chapter 1: An Introduction to Nuclear Power Generation 3
Chapter 2: The Nuclear Physics of Fission Chain Reactions 10
Chapter 3: Fission Chain Reactions and Nuclear Reactor--An Introduction 74
Part 2: The One-Speed Diffusion Model Of A Nuclear Reactor
Chapter 4: Neutron Transport 103
Chapter 5: The One-Speed Diffusion-Theory Model 149
Chapter 6: Nuclear Reactor Kinetics 233
Part 3: The Multigroup Diffusion Method
Chapter 7: Multigroup Diffusion Theory 285
Chapter 8: Fast-Spectrum Calculations and Fast-Group Constants 315
Chapter 9: Thermal Spectrum Calculations and Thermal Group Constants 375
Chapter 10: Cell Calculations for Heterogeneous Core Lattices 398
Part 4: An Introduction To Nuclear Reactor-Core Design
Chapter 11: General Aspects of Nuclear Reactor Core Design 447
Chapter 12: Thermo-Hydraulic Analysis of Nuclear Reactor Cores 467
Chapter 13: The Calculation of Core Power Distributions 515
Chapter 14: Reactivity Control 537
Chapter 15: Analysis of Core-Composition Changes 566
Appendices
A. Some useful Nuclear Data 605
B. Some useful Mathematical Formulas 611
C. Step Functions, Delta Functions, and Other Exotic Beasts 613
D. Some Properties of Special Functions 616
E. Some Assorted Facts on Linear Operators 621
F. An Introduction to Matrices and Matrix Algebra 626
G. An Introduction to Laplace Transforms 629
H. Typical Nuclear Power Reactor Data 634
I. Units Utilized in Text 636
Index 639
