**A Monte Carlo Primer**

**A Practical Approach to
Radiation Transport**

by

**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*

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Kluwer
Academic/Plenum Publishers

Hardbound, ISBN 0-306-46748-8

December 2001, 356 pp.

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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.

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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.”

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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.”

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**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*

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

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