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Numerical methods of reactor analysis /
Numerical Methods of Reactor Analysis.
| Clasificación: | Libro Electrónico |
|---|---|
| Autores principales: | , |
| Formato: | Electrónico eBook |
| Idioma: | Inglés |
| Publicado: |
New York :
Academic Press,
�1964.
|
| Colección: | Nuclear science and technology ;
3. |
| Temas: | |
| Acceso en línea: | Texto completo |
Tabla de Contenidos:
- Front Cover; Numerical Methods of Reactor Analysis; Copyright Page; Preface; Table of Contents; CHAPTER I. LINEAR EQUATIONS AND MATRIX ALGEBRA; 1.1 Linear Equations and Matrix Notation; 1.2 Matrix Operations; 1.3 Determinants; 1.4 Solution of Simultaneous Equations; 1.5 Special Matrices and Their Properties; 1.6 Vector Interpretation; 1.7 Matrix Functions and Similarity Transformations; 1.8 Linear Independence of Vectors and Orthogonalization of Vectors; 1.9 Eigenvalues and Eigenvectors; 1.10 Nonsymmetric Matrices; 1.11 Geometric Interpretation; 1.12 Biorthogonal Vectors.
- 1.13 Nonnegative Matrices1.14 Special Forms and Matrix Factorization; References; Problems; CHAPTER II. DIFFERENCE EQUATIONS; 2.1 A Simple Example; 2.2 Difference and Summation Operators; 2.3 Formation of Difference Equations and Truncation Error; 2.4 Analytic Solution of Difference Equations; 2.5 Partial Difference Equations; 2.6 Convergence of Difference Solutions; 2.7 Matrix Form of Difference Equations; References; Problems; CHAPTER III. NUMERICAL SOLUTIONS OF EQUATIONS; 3.1 Numerical Integration; 3.2 Ordinary Differential Equations; 3.3 Partial Differential Equations.
- 3.4 Hyperbolic Equations3.5 Parabolic Equations; 3.6 Elliptic Equations and Iterative Methods; References; Problems; CHAPTER IV. MULTIGROUP DIFFUSION METHODS; 4.1 Age-Diffusion Approximation; 4.2 Adjoint Equations; 4.3 Formation of Multigroup Equations; 4.4 Adjoint Multigroup Equations; 4.5 Multigroup Difference Equations; 4.6 Matrix Form of Multigroup Equations; 4.7 Numerical Solution of the Multigroup Equations; References; Problems; CHAPTER V. TRANSPORT METHODS; 5.1 The PN Approximation; 5.2 Double PN Approximation; 5.3 Multigroup Transport Methods; 5.4 Discrete Ordinate Methods.
- 5.5 The Method5.6 Time Dependent Transport Methods; 5.7 Moments Method; References; Problems; CHAPTER VI. THE MONTE CARLO METHOD; 6.1 Introduction; 6.2 Random Numbers; 6.3 Distribution Functions; 6.4 Statistical Estimation; 6.5 Analogs of Two Simple Problems; 6.6 Monte Carlo Calculation of the Fast Fission Factor; 6.7 Variance Reduction Methods; 6.8 Concluding Remarks; References; Problems; Appendix A: THE BOLTZMANN TRANSPORT EQUATION; References; Problems; Appendix B: VELOCITY RELATIONS FOR NUCLEAR EVENTS; B.1 Kinematical Relations; B.2 Conservation of Momentum; B.3 Conservation of Energy.
- B.4 Relation between the Initial and Final Speeds and the Angle of ScatteringB. 5 Relation between the Scattering Angles in the Laboratory and the Center-of-Mass System; B.6 Relations among the Scattering Angles and the Initial and Final Energies; B.7 Relations between the Direction Cosines of the Velocity of a Scattered Neutron in the Laboratory System and in a Center-of-Mass System; B.8 Relations between the Direction Cosines of a Scattered Neutron in Two Center-of-Mass Systems; B.9 Transfer Probabilities for Elastic, Isotropic Scattering and Fission; References; Problems.