Neutron Transport
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An Introduction To Neutron Transport Theory
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Author : J. H. Tait
language : en
Publisher:
Release Date : 1965
An Introduction To Neutron Transport Theory written by J. H. Tait and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1965 with Science categories.
Computational Methods Of Neutron Transport
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Author : Elmer Eugene Lewis
language : en
Publisher: Wiley-Interscience
Release Date : 1984
Computational Methods Of Neutron Transport written by Elmer Eugene Lewis and has been published by Wiley-Interscience this book supported file pdf, txt, epub, kindle and other format this book has been release on 1984 with Science categories.
The Foundations Of Neutron Transport Theory
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Author : Richard K. Osborn
language : en
Publisher: Routledge
Release Date : 1966
The Foundations Of Neutron Transport Theory written by Richard K. Osborn and has been published by Routledge this book supported file pdf, txt, epub, kindle and other format this book has been release on 1966 with Science categories.
Neutron Transport
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Author : Ramadan M. Kuridan
language : en
Publisher: Springer Nature
Release Date : 2023-10-28
Neutron Transport written by Ramadan M. Kuridan and has been published by Springer Nature this book supported file pdf, txt, epub, kindle and other format this book has been release on 2023-10-28 with Science categories.
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.
Deterministic Numerical Methods For Unstructured Mesh Neutron Transport Calculation
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Author : Liangzhi Cao
language : en
Publisher: Woodhead Publishing
Release Date : 2020-08-30
Deterministic Numerical Methods For Unstructured Mesh Neutron Transport Calculation written by Liangzhi Cao and has been published by Woodhead Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2020-08-30 with Technology & Engineering categories.
Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation presents the latest deterministic numerical methods for neutron transport equations (NTEs) with complex geometry, which are of great demand in recent years due to the rapid development of advanced nuclear reactor concepts and high-performance computational technologies. This book covers the wellknown methods proposed and used in recent years, not only theoretical modeling but also numerical results. This book provides readers with a very thorough understanding of unstructured neutron transport calculations and enables them to develop their own computational codes. The fundamentals, numerical discretization methods, algorithms, and numerical results are discussed. Researchers and engineers from utilities and research institutes are provided with examples on how to model an advanced nuclear reactor, which they can then apply to their own research projects and lab settings. Combines the theoretical models with numerical methods and results in one complete resource Presents the latest progress on the topic in an easy-to-navigate format
Mathematical Topics In Neutron Transport Theory New Aspects
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Author : Mustapha Mokhtar Kharroubi
language : en
Publisher: World Scientific
Release Date : 1997-12-18
Mathematical Topics In Neutron Transport Theory New Aspects written by Mustapha Mokhtar Kharroubi and has been published by World Scientific this book supported file pdf, txt, epub, kindle and other format this book has been release on 1997-12-18 with Science categories.
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.
Mathematical Topics In Neutron Transport Theory
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Author : M. Mokhtar-Kharroubi
language : en
Publisher: World Scientific
Release Date : 1997
Mathematical Topics In Neutron Transport Theory written by M. Mokhtar-Kharroubi and has been published by World Scientific this book supported file pdf, txt, epub, kindle and other format this book has been release on 1997 with Mathematics categories.
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.
Numerical Methods In The Theory Of Neutron Transport
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Author : Guriĭ Ivanovich Marchuk
language : en
Publisher: Harwood Academic Publishers
Release Date : 1986
Numerical Methods In The Theory Of Neutron Transport written by Guriĭ Ivanovich Marchuk and has been published by Harwood Academic Publishers this book supported file pdf, txt, epub, kindle and other format this book has been release on 1986 with Neutron transport theory categories.
Numerical Solution Of Transient And Steady State Neutron Transport Problems
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Author : Bengt G. Carlson
language : en
Publisher:
Release Date : 1959
Numerical Solution Of Transient And Steady State Neutron Transport Problems written by Bengt G. Carlson and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Neutron transport theory categories.
Numerical Formulation And Solution Of Neutron Transport Problems
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Author : Bengt G. Carlson
language : en
Publisher:
Release Date : 1964
Numerical Formulation And Solution Of Neutron Transport Problems written by Bengt G. Carlson and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1964 with Neutron transport theory categories.
