Mathematical Topics In Neutron Transport Theory
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Author |
: Mustapha Mokhtar Kharroubi |
Publisher |
: World Scientific |
Total Pages |
: 372 |
Release |
: 1997-12-18 |
ISBN-10 |
: 9789814498197 |
ISBN-13 |
: 981449819X |
Rating |
: 4/5 (97 Downloads) |
Synopsis Mathematical Topics In Neutron Transport Theory: New Aspects by : Mustapha Mokhtar Kharroubi
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.
Author |
: M. Mokhtar-Kharroubi |
Publisher |
: World Scientific |
Total Pages |
: 372 |
Release |
: 1997 |
ISBN-10 |
: 9810228694 |
ISBN-13 |
: 9789810228699 |
Rating |
: 4/5 (94 Downloads) |
Synopsis Mathematical Topics in Neutron Transport Theory by : M. Mokhtar-Kharroubi
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 0-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.
Author |
: P.M. Blackall |
Publisher |
: |
Total Pages |
: |
Release |
: 1956 |
ISBN-10 |
: OCLC:990666457 |
ISBN-13 |
: |
Rating |
: 4/5 (57 Downloads) |
Synopsis Mathematical methods in neutron transport theory by : P.M. Blackall
Author |
: J. H. Tait |
Publisher |
: |
Total Pages |
: 164 |
Release |
: 1965 |
ISBN-10 |
: UOM:39015017250153 |
ISBN-13 |
: |
Rating |
: 4/5 (53 Downloads) |
Synopsis An Introduction to Neutron Transport Theory by : J. H. Tait
Author |
: Ramadan M. Kuridan |
Publisher |
: Springer Nature |
Total Pages |
: 284 |
Release |
: 2023-10-28 |
ISBN-10 |
: 9783031269325 |
ISBN-13 |
: 3031269322 |
Rating |
: 4/5 (25 Downloads) |
Synopsis Neutron Transport by : Ramadan M. Kuridan
This textbook provides a thorough explanation of the physical concepts and presents the general theory of different forms through approximations of the neutron transport processes in nuclear reactors and emphasize the numerical computing methods that lead to the prediction of neutron behavior. Detailed derivations and thorough discussions are the prominent features of this book unlike the brevity and conciseness which are the characteristic of most available textbooks on the subject where students find them difficult to follow. This conclusion has been reached from the experience gained through decades of teaching. The topics covered in this book are suitable for senior undergraduate and graduate students in the fields of nuclear engineering and physics. Other engineering and science students may find the construction and methodology of tackling problems as presented in this book appealing from which they can benefit in solving other problems numerically. The book provides access to a one dimensional, two energy group neutron diffusion program including a user manual, examples, and test problems for student practice. An option of a Matlab user interface is also available.
Author |
: Jerome Spanier |
Publisher |
: Courier Corporation |
Total Pages |
: 258 |
Release |
: 2008-01-01 |
ISBN-10 |
: 9780486462936 |
ISBN-13 |
: 0486462935 |
Rating |
: 4/5 (36 Downloads) |
Synopsis Monte Carlo Principles and Neutron Transport Problems by : Jerome Spanier
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.
Author |
: Milan Hanus |
Publisher |
: LAP Lambert Academic Publishing |
Total Pages |
: 156 |
Release |
: 2011-02 |
ISBN-10 |
: 3844301216 |
ISBN-13 |
: 9783844301212 |
Rating |
: 4/5 (16 Downloads) |
Synopsis Mathematical Modeling of Neutron Transport by : Milan Hanus
Recent renaissance of nuclear industry came along with a renewed interest in basic research and development activities in the field. Aiming at one of the most fundamental topics, this book takes a look at neutron transport from the viewpoint of computational mathematics. Mathematical basis of the theory is established first, including the rigorous setting of two main problems of steady-state neutron transport - the core criticality and fixed source calculations. Discretization of the governing equation with respect to energy, direction of motion and space is described next, leading to a numerical method readily programmable on a computer. An important factor guiding the selection of presented methods has been their simple applicability to enhancing existing diffusion codes which, may no longer be suitable for solving current problems with more significant transport effects. The multigroup SP3 finite volume method is derived in detail and practically demonstrated on numerical benchmarks at the end. The book may be very useful to researchers facing the task to upgrade a legacy diffusion code, but may also well serve as a concise overview of modern transport-theoretical techniques.
Author |
: Yousry Azmy |
Publisher |
: Springer Science & Business Media |
Total Pages |
: 476 |
Release |
: 2010-04-15 |
ISBN-10 |
: 9789048134113 |
ISBN-13 |
: 9048134110 |
Rating |
: 4/5 (13 Downloads) |
Synopsis Nuclear Computational Science by : Yousry Azmy
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.
Author |
: Emma Horton |
Publisher |
: Springer Nature |
Total Pages |
: 278 |
Release |
: 2023-12-17 |
ISBN-10 |
: 9783031395468 |
ISBN-13 |
: 3031395468 |
Rating |
: 4/5 (68 Downloads) |
Synopsis Stochastic Neutron Transport by : Emma Horton
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.
Author |
: Gabriel Oyibo |
Publisher |
: Nova Publishers |
Total Pages |
: 182 |
Release |
: 2003-10-17 |
ISBN-10 |
: 159033518X |
ISBN-13 |
: 9781590335185 |
Rating |
: 4/5 (8X Downloads) |
Synopsis Advances in Mathematics Research by : Gabriel Oyibo
Mathematics has been behind many of humanity's most significant advances in fields as varied as genome sequencing, medical science, space exploration, and computer technology. But those breakthroughs were yesterday. Where will mathematicians lead us tomorrow and can we help shape that destiny? This book assembles carefully selected articles highlighting and explaining cutting-edge research and scholarship in mathematics. Contents: Preface; Solvability of Quasilinear Elliptic Second Order Differential Equations in Rn without Condition at Infinity; Recent Topics on a Class of Nonlinear Integrodifferential Equations of Physical Significance'; Nonparametric Estimation with Censored Observations; Normalisers of Groups Commensurable with PSL2(Z); Spectral Analysis of a Class of Multigroup Neutron Transport Operators in Slab Geometry; Extremum of a Nonlocal Functional Depending on Higher Order Derivatives of the Unknown Function; On Quantum Conditional Probability Spaces; Index.