Cargando…
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 |
MARC
| LEADER | 00000cam a2200000Ia 4500 | ||
|---|---|---|---|
| 001 | SCIDIR_ocn654293527 | ||
| 003 | OCoLC | ||
| 005 | 20231117044433.0 | ||
| 006 | m o d | ||
| 007 | cr cnu---unuuu | ||
| 008 | 100809s1964 nyua ob 000 0 eng d | ||
| 040 | |a OCLCE |b eng |e pn |c OCLCE |d OCLCQ |d OPELS |d N$T |d IDEBK |d E7B |d OCLCO |d OCLCF |d OCLCQ |d YDXCP |d EBLCP |d UKDOC |d DEBSZ |d OCLCQ |d MERUC |d OCLCQ |d OCLCO |d OCLCQ |d LEAUB |d LUN |d EYM |d OCLCO |d OCLCQ |d OCLCO |d COM |d OCLCO |d OCL |d OCLCQ |d OCLCO | ||
| 019 | |a 297277319 |a 602241552 |a 850146133 |a 987748794 |a 1086514951 | ||
| 020 | |a 9780323154673 |q (electronic bk.) | ||
| 020 | |a 0323154670 |q (electronic bk.) | ||
| 020 | |a 9780123956538 |q (electronic bk.) | ||
| 020 | |a 0123956536 |q (electronic bk.) | ||
| 020 | |z 0121753506 | ||
| 020 | |z 9780121753504 | ||
| 035 | |a (OCoLC)654293527 |z (OCoLC)297277319 |z (OCoLC)602241552 |z (OCoLC)850146133 |z (OCoLC)987748794 |z (OCoLC)1086514951 | ||
| 042 | |a dlr | ||
| 050 | 4 | |a TK9202 |b .C49 1964eb | |
| 072 | 7 | |a TEC |x 028000 |2 bisacsh | |
| 082 | 0 | 4 | |a 621.48/3 |2 23 |
| 084 | |a SK 950 |2 rvk | ||
| 084 | |a UN 5100 |2 rvk | ||
| 084 | |a NUC 205f |2 stub | ||
| 100 | 1 | |a Clark, Melville, |c Jr. | |
| 245 | 1 | 0 | |a Numerical methods of reactor analysis / |c Melville Clark, Jr. [and] Kent F. Hansen. |
| 260 | |a New York : |b Academic Press, |c �1964. | ||
| 300 | |a 1 online resource (xi, 340 pages) : |b illustrations | ||
| 336 | |a text |b txt |2 rdacontent | ||
| 337 | |a computer |b c |2 rdamedia | ||
| 338 | |a online resource |b cr |2 rdacarrier | ||
| 490 | 1 | |a Nuclear science and technology, a series of monographs and textbooks ; |v 3 | |
| 504 | |a Includes bibliographical references. | ||
| 506 | |3 Use copy |f Restrictions unspecified |2 star |5 MiAaHDL | ||
| 533 | |a Electronic reproduction. |b [Place of publication not identified] : |c HathiTrust Digital Library, |d 2010. |5 MiAaHDL | ||
| 538 | |a Master and use copy. Digital master created according to Benchmark for Faithful Digital Reproductions of Monographs and Serials, Version 1. Digital Library Federation, December 2002. |u http://purl.oclc.org/DLF/benchrepro0212 |5 MiAaHDL | ||
| 583 | 1 | |a digitized |c 2010 |h HathiTrust Digital Library |l committed to preserve |2 pda |5 MiAaHDL | |
| 588 | 0 | |a Print version record. | |
| 505 | 0 | |a 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. | |
| 505 | 8 | |a 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. | |
| 505 | 8 | |a 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. | |
| 505 | 8 | |a 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. | |
| 505 | 8 | |a 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. | |
| 520 | |a Numerical Methods of Reactor Analysis. | ||
| 650 | 0 | |a Nuclear reactors |v Tables. | |
| 650 | 7 | |a TECHNOLOGY & ENGINEERING |x Power Resources |x Nuclear. |2 bisacsh | |
| 650 | 7 | |a Nuclear reactors |2 fast |0 (OCoLC)fst01040734 | |
| 650 | 7 | |a Kernreaktorphysik |2 gnd |0 (DE-588)4123503-4 | |
| 650 | 7 | |a Numerisches Verfahren |2 gnd |0 (DE-588)4128130-5 | |
| 655 | 2 | |a Tables |0 (DNLM)D020501 | |
| 655 | 7 | |a tables (documents) |2 aat |0 (CStmoGRI)aatgf300027364 | |
| 655 | 7 | |a Tables (Data) |2 fast |0 (OCoLC)fst01919974 | |
| 655 | 7 | |a Tables |2 fast |0 (OCoLC)fst01423914 | |
| 655 | 7 | |a Tables (Data) |2 lcgft | |
| 655 | 7 | |a Tables (Donn�ees) |2 rvmgf |0 (CaQQLa)RVMGF-000001171 | |
| 700 | 1 | |a Hansen, Kent F., |e author. | |
| 776 | 0 | 8 | |i Print version: |a Clark, Melville, Jr. |t Numerical methods of reactor analysis. |d New York : Academic Press, 1964 |w (DLC) 64020318 |w (OCoLC)1361169 |
| 830 | 0 | |a Nuclear science and technology ; |v 3. | |
| 856 | 4 | 0 | |u https://sciencedirect.uam.elogim.com/science/book/9780123956538 |z Texto completo |