Stochastic Neutron Transport
Stochastic Neutron Transport

Author: Emma Horton

Publisher: Springer Nature

Published: 2023-12-17

Total Pages: 278

ISBN-13: 3031395468

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This monograph highlights the connection between the theory of neutron transport and the theory of non-local branching processes. By detailing this frequently overlooked relationship, the authors provide readers an entry point into several active areas, particularly applications related to general radiation transport. Cutting-edge research published in recent years is collected here for convenient reference. Organized into two parts, the first offers a modern perspective on the relationship between the neutron branching process (NBP) and the neutron transport equation (NTE), as well as some of the core results concerning the growth and spread of mass of the NBP. The second part generalizes some of the theory put forward in the first, offering proofs in a broader context in order to show why NBPs are as malleable as they appear to be. Stochastic Neutron Transport will be a valuable resource for probabilists, and may also be of interest to numerical analysts and engineers in the field of nuclear research.

Mathematical Topics In Neutron Transport Theory: New Aspects
Mathematical Topics In Neutron Transport Theory: New Aspects

Author: Mustapha Mokhtar Kharroubi

Publisher: World Scientific

Published: 1997-12-18

Total Pages: 372

ISBN-13: 981449819X

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This book presents some recent mathematical developments about neutron transport equations. Several different topics are dealt with including regularity of velocity averages, spectral analysis of transport operators, inverse problems, nonlinear problems arising in the stochastic theory of neutron chain fissions, compactness properties of perturbed of c0-semigroups in Banach spaces with applications to transport theory, Miyadera perturbations of c0-semigroups in Banach spaces with applications to singular transport equations, a thorough analysis of the leading eigenelements of transport operators and their approximation, scattering theory. Besides the new problems addressed in this book a unification and extension of the classical spectral analysis of neutron transport equations is given.

Neutron Fluctuations
Neutron Fluctuations

Author: Imre Pazsit

Publisher: Elsevier

Published: 2007-10-05

Total Pages: 359

ISBN-13: 0080550436

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The transport of neutrons in a multiplying system is an area of branching processes with a clear formalism. Neutron Fluctuations presents an account of the mathematical tools used in describing branching processes, which are then used to derive a large number of properties of the neutron distribution in multiplying systems with or without an external source. In the second part of the book, the theory is applied to the description of the neutron fluctuations in nuclear reactor cores as well as in small samples of fissile material. The question of how to extract information about the system under study is discussed. In particular the measurement of the reactivity of subcritical cores, driven with various Poisson and non-Poisson (pulsed) sources, and the identification of fissile material samples, is illustrated. The book gives pragmatic information for those planning and executing and evaluating experiments on such systems. - Gives a complete treatise of the mathematics of branching particle processes, and in particular neutron fluctuations, in a self-contained manner - The first monograph containing the theory and application of neutron fluctuations in low power ADS (spallation and pulsed sources) - Suitable as a tutorial and handbook/reference book for scientists and graduate students - One of the authors is the founder of the mathematical theory of neutron fluctuations in zero power systems

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.

Nuclear Computational Science
Nuclear Computational Science

Author: Yousry Azmy

Publisher: Springer Science & Business Media

Published: 2010-04-15

Total Pages: 476

ISBN-13: 9048134110

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Nuclear engineering has undergone extensive progress over the years. In the past century, colossal developments have been made and with specific reference to the mathematical theory and computational science underlying this discipline, advances in areas such as high-order discretization methods, Krylov Methods and Iteration Acceleration have steadily grown. Nuclear Computational Science: A Century in Review addresses these topics and many more; topics which hold special ties to the first half of the century, and topics focused around the unique combination of nuclear engineering, computational science and mathematical theory. Comprising eight chapters, Nuclear Computational Science: A Century in Review incorporates a number of carefully selected issues representing a variety of problems, providing the reader with a wealth of information in both a clear and concise manner. The comprehensive nature of the coverage and the stature of the contributing authors combine to make this a unique landmark publication. Targeting the medium to advanced level academic, this book will appeal to researchers and students with an interest in the progression of mathematical theory and its application to nuclear computational science.

Monte Carlo Principles and Neutron Transport Problems
Monte Carlo Principles and Neutron Transport Problems

Author: Jerome Spanier

Publisher: Courier Corporation

Published: 2008-01-01

Total Pages: 258

ISBN-13: 0486462935

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This two-part treatment introduces the general principles of the Monte Carlo method within a unified mathematical point of view, applying them to problems in neutron transport. It describes several efficiency-enhancing approaches, including the method of superposition and simulation of the adjoint equation based on reciprocity. The first half of the book presents an exposition of the fundamentals of Monte Carlo methods, examining discrete and continuous random walk processes and standard variance reduction techniques. The second half of the text focuses directly on the methods of superposition and reciprocity, illustrating their applications to specific neutron transport problems. Topics include the computation of thermal neutron fluxes and the superposition principle in resonance escape computations.

Fractional Calculus with Applications for Nuclear Reactor Dynamics
Fractional Calculus with Applications for Nuclear Reactor Dynamics

Author: Santanu Saha Ray

Publisher: CRC Press

Published: 2015-07-29

Total Pages: 232

ISBN-13: 149872728X

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Introduces Novel Applications for Solving Neutron Transport EquationsWhile deemed nonessential in the past, fractional calculus is now gaining momentum in the science and engineering community. Various disciplines have discovered that realistic models of physical phenomenon can be achieved with fractional calculus and are using them in numerous way

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