Monte Carlo Methods and Codes for Nuclear Engineering Analysis
Monte Carlo Methods and Codes for Nuclear Engineering Analysis

Author: Christopher Perfetti

Publisher: Woodhead Publishing

Published: 2019-06-15

Total Pages: 390

ISBN-13: 9780128154007

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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 then goes on to explore the real-world implementation of these methods in codes used by nuclear and scientists 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. The 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 the features and make and educated selections of the codes best meeting their needs chapters begin at a level that is appropriate for readers who are unfamiliar with the field, then go on to address the state-of-the-art

Exploring Monte Carlo Methods
Exploring Monte Carlo Methods

Author: William L. Dunn

Publisher: Elsevier

Published: 2022-06-07

Total Pages: 594

ISBN-13: 0128197455

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Exploring Monte Carlo Methods, Second Edition provides a valuable introduction to the numerical methods that have come to be known as "Monte Carlo." This unique and trusted resource for course use, as well as researcher reference, offers accessible coverage, clear explanations and helpful examples throughout. Building from the basics, the text also includes applications in a variety of fields, such as physics, nuclear engineering, finance and investment, medical modeling and prediction, archaeology, geology and transportation planning. - Provides a comprehensive yet concise treatment of Monte Carlo methods - Uses the famous "Buffon's needle problem" as a unifying theme to illustrate the many aspects of Monte Carlo methods - Includes numerous exercises and useful appendices on: Certain mathematical functions, Bose Einstein functions, Fermi Dirac functions and Watson functions

Nuclear Engineering
Nuclear Engineering

Author: Zafar Ullah Koreshi

Publisher: Academic Press

Published: 2022-03-23

Total Pages: 549

ISBN-13: 0323908314

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Nuclear Engineering Mathematical Modeling and Simulation presents the mathematical modeling of neutron diffusion and transport. Aimed at students and early career engineers, this highly practical and visual resource guides the reader through computer simulations using the Monte Carlo Method which can be applied to a variety of applications, including power generation, criticality assemblies, nuclear detection systems, and nuclear medicine to name a few. The book covers optimization in both the traditional deterministic framework of variational methods and the stochastic framework of Monte Carlo methods. Specific sections cover the fundamentals of nuclear physics, computer codes used for neutron and photon radiation transport simulations, applications of analyses and simulations, optimization techniques for both fixed-source and multiplying systems, and various simulations in the medical area where radioisotopes are used in cancer treatment. - Provides a highly visual and practical reference that includes mathematical modeling, formulations, models and methods throughout - Includes all current major computer codes, such as ANISN, MCNP and MATLAB for user coding and analysis - Guides the reader through simulations for the design optimization of both present-day and future nuclear systems

Nuclear Power Plant Design and Analysis Codes
Nuclear Power Plant Design and Analysis Codes

Author: Jun Wang

Publisher: Woodhead Publishing

Published: 2020-11-10

Total Pages: 612

ISBN-13: 0128181915

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Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. - Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors - Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes - Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting

Handbook of Nuclear Engineering
Handbook of Nuclear Engineering

Author: Dan Gabriel Cacuci

Publisher: Springer Science & Business Media

Published: 2010-09-14

Total Pages: 3701

ISBN-13: 0387981306

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This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Fast Spectrum Reactors
Fast Spectrum Reactors

Author: Alan E. Waltar

Publisher: Springer Science & Business Media

Published: 2011-09-28

Total Pages: 717

ISBN-13: 1441995722

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This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which , along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology (including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included. Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India) , John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation) ,James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency).

The Monte Carlo Simulation Method for System Reliability and Risk Analysis
The Monte Carlo Simulation Method for System Reliability and Risk Analysis

Author: Enrico Zio

Publisher: Springer Science & Business Media

Published: 2012-11-02

Total Pages: 204

ISBN-13: 1447145887

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Monte Carlo simulation is one of the best tools for performing realistic analysis of complex systems as it allows most of the limiting assumptions on system behavior to be relaxed. The Monte Carlo Simulation Method for System Reliability and Risk Analysis comprehensively illustrates the Monte Carlo simulation method and its application to reliability and system engineering. Readers are given a sound understanding of the fundamentals of Monte Carlo sampling and simulation and its application for realistic system modeling. Whilst many of the topics rely on a high-level understanding of calculus, probability and statistics, simple academic examples will be provided in support to the explanation of the theoretical foundations to facilitate comprehension of the subject matter. Case studies will be introduced to provide the practical value of the most advanced techniques. This detailed approach makes The Monte Carlo Simulation Method for System Reliability and Risk Analysis a key reference for senior undergraduate and graduate students as well as researchers and practitioners. It provides a powerful tool for all those involved in system analysis for reliability, maintenance and risk evaluations.

Risk-informed Methods and Applications in Nuclear and Energy Engineering
Risk-informed Methods and Applications in Nuclear and Energy Engineering

Author: Curtis Smith

Publisher: Academic Press

Published: 2023-11-16

Total Pages: 388

ISBN-13: 0323998186

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Risk-informed Methods and Applications in Nuclear and Energy Engineering: Modelling, Experimentation, and Validation presents a comprehensive view of the latest technical approaches and experimental capabilities in nuclear energy engineering. Based on Idaho National Laboratory's popular summer school series, this book compiles a collection of entries on the cutting-edge research and knowledge presented by proponents and developers of current and future nuclear systems, focusing on the connection between modelling and experimental approaches. Included in this book are key topics such as probabilistic concepts for risk analysis, the survey of legacy reliability and risk analysis tools, and newly developed tools supporting dynamic probabilistic risk-assessment. This book is an insightful and inspiring compilation of work from top nuclear experts from INL. Industry professionals, researchers and academics working in nuclear engineering, safety, operations and training will gain a board picture of the current state-of-practice and be able to apply that to their own risk-assessment studies. - Based on Idaho National Laboratory's summer school series, this book is a collection of entries from proponents and developers of current and future nuclear systems - Provides an up-to-date view of current technical approaches and experimental capabilities in nuclear energy engineering, covering modeling and validation, and focusing on risk-informed methods and applications - Equips the reader with an understanding of various case studies and experimental validations to enable them to carry out a risk-assessment study

Monte Carlo Methods for Particle Transport
Monte Carlo Methods for Particle Transport

Author: Alireza Haghighat

Publisher: CRC Press

Published: 2020-08-09

Total Pages: 279

ISBN-13: 042958220X

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Fully updated with the latest developments in the eigenvalue Monte Carlo calculations and automatic variance reduction techniques and containing an entirely new chapter on fission matrix and alternative hybrid techniques. This second edition explores the uses of the Monte Carlo method for real-world applications, explaining its concepts and limitations. Featuring illustrative examples, mathematical derivations, computer algorithms, and homework problems, it is an ideal textbook and practical guide for nuclear engineers and scientists looking into the applications of the Monte Carlo method, in addition to students in physics and engineering, and those engaged in the advancement of the Monte Carlo methods. Describes general and particle-transport-specific automated variance reduction techniques Presents Monte Carlo particle transport eigenvalue issues and methodologies to address these issues Presents detailed derivation of existing and advanced formulations and algorithms with real-world examples from the author’s research activities

Foundations In Applied Nuclear Engineering Analysis (2nd Edition)
Foundations In Applied Nuclear Engineering Analysis (2nd Edition)

Author: Glenn E Sjoden

Publisher: World Scientific Publishing Company

Published: 2015-01-13

Total Pages: 403

ISBN-13: 9814630950

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Foundations in Applied Nuclear Engineering Analysis (2nd Edition) covers a fast-paced one semester course to address concepts of modeling in mathematics, engineering analysis, and computational problem solving needed in subjects such as radiation interactions, heat transfer, reactor physics, radiation transport, numerical modeling, etc., for success in a nuclear engineering/medical physics curriculum. While certain topics are covered tangentially, others are covered in depth to target on the appropriate amalgam of topics for success in navigating nuclear-related disciplines. Software examples and programming are used throughout the book, since computational capabilities are essential for new engineers.The book contains a array of topics that cover the essential subjects expected for students to successfully navigate into nuclear-related disciplines. The text assumes that students have familiarity with undergraduate mathematics and physics, and are ready to apply those skills to problems in nuclear engineering. Applications and problem sets are directed toward problems in nuclear science. Software examples using Mathematica software are used in the text.This text was developed as part of a very applied course in mathematical physics methods for nuclear engineers. The course in Nuclear Engineering Analysis that follows this text began at the University of Florida; the 2nd edition was released while at the Georgia Institute of Technology.