A Monte Carlo Primer
A Practical Approach to Radiation Transport


Stephen A. Dupree
Distinguished Member of Technical Staff, Sandia National Laboratories, Albuquerque, NM, USA
Stanley K. Fraley
Senior Scientist, Sandia National Laboratories, Albuquerque, NM, USA


Kluwer Academic/Plenum Publishers
Hardbound, ISBN 0-306-46748-8
December 2001,  356 pp.


Preface. 1. Introduction. 2. Monte Carlo Sampling Techniques. 3. Monte Carlo Modeling of Neutron Transport. 4. Energy-Dependent Neutron Transport. 5. A Probabilistic Framework Code. 6. Variance Reduction Techniques. 7. Monte Carlo Detectors. 8. Nuclear Criticality Calculations with Monte Carlo. 9. Advanced Applications of Monte Carlo. Appendix: Random Number Generators. Bibliography. Index.


This book introduces the reader to the use of Monte Carlo methods for solving practical problems in radiation transport, and will also serve as a reference work for practitioners in the field. It assumes the reader has a general knowledge of calculus and radiation physics, and a knowledge of Fortran programming, but assumes no prior knowledge of stochastic methods or statistical physics. The subject is presented by a combination of theoretical development and practical calculations. Because Monte Carlo methods are closely linked to the use of computers, from the beginning the reader is taught to convert the theoretical constructs developed in the text into functional software for use on a personal computer. Example problems provide the reader with an in-depth understanding of the concepts presented and lead to the production of a unique learning tool, a probabilistic framework code that models in a simple manner the features of production of Monte Carlo transport codes. This framework code is developed in stages such that every function is understood, tested, and demonstrated – random sampling, generating random numbers, implementing geometric models, using variance reduction, tracking particles in a random walk, testing the thoroughness with which the problem phase space is sampled, scoring detectors, and obtaining estimates of uncertainty in results. Advanced topics covered include criticality, correlated sampling, adjoint transport, and neutron thermalization.

Monte Carlo codes can produce highly precise wrong answers. The probability of this occurring is increased if production codes are run as opaque, `black boxes' of software. This text attempts to make Monte Carlo into a comprehensible, usable tool for solving practical transport problems. It is suitable for advanced undergraduate and graduate students and researchers who wish to expand their knowledge of the Monte Carlo technique.


A simple example of the types of problems that can be solved using the Monte Carlo techniques described in the text can be found at “Example Calculation Using PFC.”


A discussion of the values used in this volume for the criticality calculation of the Godiva fast-pulse reactor can be found at “Isotope Abundances in Godiva Criticality Calculations.”




Editorial Reviews
From Book News, Inc.
Attempting to steer a course between exclusive concentration on the mathematical basis or the application in computer codes, this work seeks to adequately cover both facets of Monte Carlo methods as applied to the transport of sub-atomic particles. Dupree and Fraley (both of Sandia National Laboratories, US) cover sampling techniques, modeling of neutron transport, energy-dependent neutron transport, variance reduction techniques, Monte Carlo detectors, nuclear criticality calculations, and advanced applications. The book assumes knowledge of integral calculus, neutron transport theory, and Fortran programming, as well as access to a PC with a Fortran compiler for solving the exercises. Book News, Inc.®, Portland, OR



For further information, contact the authors at MCP@fraleys.com


Return to Home Page