Author: Guriĭ Ivanovich Marchuk
Publisher: Harwood Academic Publishers
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 632
Book Description
Numerical Methods in the Theory of Neutron Transport
Author: Guriĭ Ivanovich Marchuk
Publisher: Harwood Academic Publishers
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 632
Book Description
Publisher: Harwood Academic Publishers
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 632
Book Description
Numerical Solution of Transient and Steady-state Neutron Transport Problems
Author: Bengt G. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 34
Book Description
Neutron Transport
Author: Ramadan M. Kuridan
Publisher: Springer Nature
ISBN: 3031269322
Category : Science
Languages : en
Pages : 284
Book Description
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.
Publisher: Springer Nature
ISBN: 3031269322
Category : Science
Languages : en
Pages : 284
Book Description
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.
The Discrete Sn Approximation to Transport Theory
Author: Clarence E. Lee
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 434
Book Description
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 434
Book Description
Numerical Formulation and Solution of Neutron Transport Problems
Author: Bengt G. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 54
Book Description
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 54
Book Description
Mathematical Topics In Neutron Transport Theory: New Aspects
Author: Mustapha Mokhtar Kharroubi
Publisher: World Scientific
ISBN: 981449819X
Category : Science
Languages : en
Pages : 372
Book Description
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.
Publisher: World Scientific
ISBN: 981449819X
Category : Science
Languages : en
Pages : 372
Book Description
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.
Computational Methods of Neutron Transport
Author: Elmer Eugene Lewis
Publisher: Wiley-Interscience
ISBN:
Category : Science
Languages : en
Pages : 440
Book Description
Publisher: Wiley-Interscience
ISBN:
Category : Science
Languages : en
Pages : 440
Book Description
Transport Theory
Author: Richard Bellman
Publisher: American Mathematical Soc.
ISBN: 9780821813201
Category : Mathematics
Languages : en
Pages : 340
Book Description
The industrial and military applications of atomic energy have stimulated much mathematical research in neutron transport theory. The possibility of controlled thermonuclear processes has similarly focussed attention upon plasmas, sometimes called the "fourth state of matter". Independently, many classical aspects of kinetic theory and radiative transfer theory have been studied both because of their basic mathematical interest and of their physical applications to areas such as upper-atmosphere meteorology - introduction.
Publisher: American Mathematical Soc.
ISBN: 9780821813201
Category : Mathematics
Languages : en
Pages : 340
Book Description
The industrial and military applications of atomic energy have stimulated much mathematical research in neutron transport theory. The possibility of controlled thermonuclear processes has similarly focussed attention upon plasmas, sometimes called the "fourth state of matter". Independently, many classical aspects of kinetic theory and radiative transfer theory have been studied both because of their basic mathematical interest and of their physical applications to areas such as upper-atmosphere meteorology - introduction.
Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation
Author: Liangzhi Cao
Publisher: Woodhead Publishing
ISBN: 0128182229
Category : Technology & Engineering
Languages : en
Pages : 294
Book Description
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
Publisher: Woodhead Publishing
ISBN: 0128182229
Category : Technology & Engineering
Languages : en
Pages : 294
Book Description
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
On the Numerical Integration of the Neutron Transport Equation
Author: Herbert Bishop Keller
Publisher:
ISBN:
Category : Elastic scattering
Languages : en
Pages : 48
Book Description
A procedure for the direct numerical integration of the steady-state, elastic scattering neutron transport equation is presented.
Publisher:
ISBN:
Category : Elastic scattering
Languages : en
Pages : 48
Book Description
A procedure for the direct numerical integration of the steady-state, elastic scattering neutron transport equation is presented.