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The Theory of Neutron Slowing Down in Nuclear Reactors focuses on one facet of nuclear reactor design: the slowing down (or moderation) of neutrons from the high energies with which they are born in fission to the energies at which they are ultimately absorbed. In conjunction with the study of neutron moderation, calculations of reactor criticality are presented. A mathematical description of the slowing-down process is given, with particular emphasis on the problems encountered in the design of thermal reactors. This volume is comprised of four chapters and begins by considering the problems of neutron moderation and their importance in all types of reactors. An asymptotic reactor model is described, and the calculation of the elastic scattering frequency is explained. Subsequent chapters focus on the process of slowing down in finite and infinite medium by analyzing capture by individual resonances; resonance integrals in heterogeneous systems; the slowing-down kernels; the spherical harmonics method; statistical methods; and small source theory. The final chapter presents numerical solutions of the Boltzmann equation and covers topics such as the multigroup approach, group constants, and solution of the multigroup equations. This book will be a useful resource for nuclear physicists and engineers.
I. Slowing Down and Reactor Criticality
A. The Role of Slowing Down
B. The Mathematical Description of the Neutron Density in a Reactor
C. Asymptotic Reactor Theory
D. Calculation of the Elastic Scattering Frequency
E. Evaluation and Significance of the Transformation Matrices
II. Slowing Down in an Infinite Medium
A. Introductory Remarks
B. Slowing Down in Hydrogeneous Media
C. Slowing Down in Media Containing Heavy Elements:
I. Non-absorbing Media
D. Slowing Down in Media Containing Heavy Elements:
II. Absorbing Media
E. Capture by Individual Resonances
F. Calculation of Resonance Integrals
G. Resonance Integrals in Heterogeneous Systems
III. Slowing Down in Finite Media
A. The Slowing-down Kernels
B. The Spherical Harmonics Method
C. The Pi Approximation
D. Methods Related to the PL Approximations
E. Other Approximations to the Boltzmann Equation
F. Statistical Methods
G. Small Source Theory
H. Comparison of Results with Experiment
IV. Numerical Solutions of the Boltzmann Equation
A. The Multigroup Approach
Β. Simple Applications of the Method
C. Group Constants
D. Solution of the Multigroup Equations
Appendix A—Time Dependent Asymptotic Reactor Theory
Appendix B—Vector Identities
Appendix C—The Validity of Asymptotic Reactor Theory
Appendix D—Extensions of Asymptotic Reactor Theory
Appendix E—Improvements in Criticality Calculations
Appendix F—Equivalence of the BL and PL Approximations
Other Titles in the Series
- No. of pages:
- © Pergamon 1966
- 1st January 1966
- eBook ISBN:
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