Overview

The Monte Carlo method has become the de facto standard in radiation transport. Although powerful, if not understood and used appropriately, the method can give misleading results. Monte Carlo Methods for Particle Transport teaches appropriate use of the Monte Carlo method, explaining the method s fundamental concepts as well as its limitations. Concise yet comprehensive, this well-organized text:

• Introduces the particle importance equation and its use for variance reduction
• Describes general and particle-transport-specific variance reduction techniques
• Presents particle transport eigenvalue issues and methodologies to address these issues
• Explores advanced formulations based on the author s research activities
• Discusses parallel processing concepts and factors affecting parallel performance

Full Product Details

9781322636320

Table of Contents

Reviews

This is an outstanding reference and textbook on applied stochastic methods. It is a must-have for scientists, students, and practitioners interested in Monte Carlo methods for solving particle transport problems. This book provides an excellent description of the fundamentals through numerous example problems and a rich discussion of advantages and pitfalls of the Monte Carlo method. The chapter on solving eigenvalue problems is long overdue, where diagnosing convergence of the fission source in reactor physics problems with high dominance ratio is challenging and as a result has been a subject of much research. Farzad Rahnema, Georgia Power Company Distinguished Professor and Chair of Nuclear and Radiological Engineering and Medical Physics, Georgia Institute of Technology, Atlanta, USA This is a very solid book for graduate students in nuclear engineering to learn how the Monte Carlo method can be used to solve reactor physics problems. It covers the fundamentals of Monte Carlo simulations before discussing how the technique can be used to solve fixed and fission sources neutron transport problems. Excellent examples are provided in the main text, in addition to a complete set of homework problems at the end of each chapter. This makes it an ideal textbook for those teaching a course on simulation methods in reactor physics. G. Marleau, Professor of Nuclear Engineering and Engineering Physics, Director of the Institute of Nuclear Engineering, Ecole Polytechnique de Montreal, Quebec, Canada Professor Haghighat, based on his many years of experience in teaching the subject, has written a long-awaited book on Monte Carlo methods. The subject of the book based on particle transport has an old history in concept, but is becoming lately more important and enjoying heavy use with the advent of high-performance computers. Professor Haghighat has succeeded in writing a book that is concise, but also includes all ingredients in the Monte Carlo method. [This book is] an excellent addition to the bookshelf of teachers, students, researchers, and practitioners in the field of nuclear reactor design and radiation shielding applications. Nam Zin Cho, Professor of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon, South Korea

Author Information

Alireza Haghighat is a professor at Virginia Tech. He has served as the director of the Nuclear Science and Engineering Lab in Arlington, Virginia, and led the Virginia Tech Theory Transport Group. He previously worked at Penn State and the University of Florida. He holds a Ph.D from the University of Washington. He has published numerous papers, received several best paper awards, and presented many invited workshops, seminars, and papers nationally and internationally. He is a recipient of the 2011 Radiation Protection Shielding Division s Professional Excellence Award, and a recognition award from the Office of Global Threat Reduction. An ANS fellow, he has served in various ANS leadership positions.

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