Stephen A. Dupree, Stanley K. Fraley

A Monte Carlo Primer

A Practical Approach to Radiation Transport

• Broschiertes Buch

Produktbeschreibung

The mathematical technique of Monte Carlo, as applied to the transport of sub-atomic particles, has been described in numerous reports and books since its formal development in the 1940s. Most of these instructional efforts have been directed either at the mathematical basis of the technique or at its practical application as embodied in the several large, formal computer codes available for performing Monte Carlo transport calculations. This book attempts to fill what appears to be a gap in this Monte Carlo literature between the mathematics and the software. Thus, while the mathematical basis for Monte Carlo transport is covered in some detail, emphasis is placed on the application of the technique to the solution of practical radiation transport problems. This is done by using the PC as the basic teaching tool. This book assumes the reader has a knowledge of integral calculus, neutron transport theory, and Fortran programming. It also assumes the reader has available a PC witha Fortran compiler. Any PC of reasonable size should be adequate to reproduce the examples or solve the exercises contained herein. The authors believe it is important for the reader to execute these examples and exercises, and by doing so to become accomplished at preparing appropriate software for solving radiation transport problems using Monte Carlo. The step from the software described in this book to the use of production Monte Carlo codes should be straightforward.

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Produktdetails

• Verlag: Springer, Berlin
• Softcover reprint of the original 1st ed. 2002
• Seitenzahl: 360
• Erscheinungstermin: 5. September 2012
• Englisch
• Abmessung: 244mm x 170mm x 20mm
• Gewicht: 620g
• ISBN-13: 9781461346289
• ISBN-10: 1461346282
• Artikelnr.: 36938316

Inhaltsangabe

1. Introduction.- 1.1 The Monte Carlo Method.- 1.2 The Evaluation of Random Processes>.- 1.3 Monte Carlo Evaluation of Definite Integrals.- Exercises.- 2. Monte Carlo Sampling Techniques.- 2.1 Probability Theory and Statistics.- 2.2 Sampling.- 2.3 Means and Variances.- 2.4 Estimations of Means and Variances.- 2.5 Introduction to Variance Reduction Techniques.- Exercises.- 3. Monte Carlo Modeling of Neutron Transport.- 3.1 Introduction.- 3.2 Neutron Interactions and Mean Free Path.- 3.3 Neutron Transport.- 3.4 A Mathematical Basis for Monte Carlo Neutron Transport.- 3.5 Monte Carlo Modeling of Neutron Motion.- 3.6 Particle Flight Path in Complex Geometries.- 3.7 Multi-Region Problems.- Exercises.- 4. Energy-Dependent Neutron Transport.- 4.1 Elastic Scattering of Neutrons.- 4.2 Transformation of Post-Collision Direction to Laboratory System.- 4.3 Energy-Dependent Cross Sections.- Exercises.- 5. A Probabilistic Framework Code.- 5.1 Introduction to PFC.- 5.2 Problem Definition in PFC.- 5.3 The Random Walk in PFC.- 5.4 Computing the Response.- Exercises.- 6. Variance Reduction Techniques.- 6.1 Introduction.- 6.2 Source Biasing.- 6.3 Survival Biasing.- 5.4 Russian Roulette.- 6.5 Splitting.- 6.6 Exponential Transform.- Exercises.- 7. Monte Carlo Detectors.- 7.1 Introduction.- 7.2 The Next-Event Estimator.- 7.3 Volumetric Flux Detectors.- 7.3 Surface-Crossing Flux Estimator.- 7.5 Expectation Surface-Crossing Flux Estimator.- Time-Dependent Detectors.- Exercises.- 8. Nuclear Criticality Calculations with Monte Carlo.- 8.1 Multiplying Assemblies.- 8.2 The Generation Method.- 8.3 The Matrix Method.- 8.4 Combination of Generation and Matrix Methods.- 8.5 Criticality Calculations Using Multigroup Cross Sections.- Exercises.- 9. Advanced Applications of Monte Carlo.- 9.1 Correlated Sampling.- 9.2 Adjoint Monte Carlo.- 9.3 Neutron Thermalization.- Exercises.- Appendix Random Number Generators.