Monte Carlo Methods and Codes for Nuclear Engineering Analysis provides a comprehensive survey of the state-of-the-art in radiation transport methods used by Monte Carlo (MC) codes. It explores the real-world implementation of these methods in codes used by nuclear scientists and engineers, considering the advantages and disadvantages of the various techniques, design philosophies and algorithm implementations. After a foreword and introduction giving a brief history of Monte Carlo methods, code systems, and their applications in nuclear science and engineering, subsequent chapters describe the fundamentals of Monte Carlo radiation transport methods by dividing the field into a number of topics or focus areas.
Subjects selected include potential geometry and particle tracking, nuclear data, variance reduction, time-dependent analysis and parallel computing. Each chapter presents a comprehensive survey of the state-of-the-art implementations, algorithms, and methodologies used by production-level Monte Carlo codes for the area. A concluding chapter provides a handy summary by briefly listing the methods used by key Monte Carlo codes for each focus area in several tables.
This book is an essential guide to Monte Carlo methods and codes for nuclear scientists, engineers and code developers in academia and industry and students studying this topic.
- Discusses and compares the radiation transport methods in real-life Monte Carlo (MC) codes used by nuclear scientists and engineers
- Presents, in one convenient volume, information previously scattered between conference papers, journal articles and code manuals, thus allowing MC code users to compare features and make an educated selection of codes
- Presents content at a level that is appropriate for readers who are unfamiliar with the field, but then goes on to address the state-of-the-art
1. Introduction to Monte Carlo Methods 2. Fundamentals of the Monte Carlo Method 3. Potential Geometry and Particle Tracking 4. Nuclear Data Processing, Data Structures, Handling of Temperature-dependence 5. Eigenvalue Source Convergence and Acceleration for Criticality Codes 6. Importance-based Variance Reduction for Fixed Source Codes 7. Tally Estimators, Tally Data Structures, and Reactor Physics Applications 8. Time-Dependent Analysis Part 1: Depletion Calculations 9. Time-Dependent Analysis
Part 2: Transient/Multiphysics Simulations 10. Sensitivity and Uncertainty Analysis Methods (Adjoint-based and Stochastic Methods) 11. Approach to Parallel/High-Performance Computing 12. Approaches for Validation and Verification 13. Conclusions
Dr. Christopher (Chris) Perfetti studied nuclear engineering at the University of Florida, where he obtained his Bachelors and Masters of Science degrees in Nuclear and Radiological Engineering. Chris then moved to the University of Michigan to pursue his PhD in Nuclear Engineering under the guidance of Professor Bill Martin. After obtaining his PhD in 2012, Chris began a postdoc appointment at ORNL under the mentorship of Dr. Brad Rearden, where he was converted to R&D staff in 2014. Chris is the Sensitivity and Uncertainty Analysis team lead for the SCALE Code System, and is involved with teaching several SCALE training courses. Chris is currently the Past Chair of the Oak Ridge/Knoxville Local Chapter of the American Nuclear Society. He is a member of ANS and a reviewer for Annals of Nuclear Energy, Nuclear Technology and Nuclear Science and Engineering.