Numerical Methods In The Theory Of Neutron Transport
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Author |
: Guriĭ Ivanovich Marchuk |
Publisher |
: Harwood Academic Publishers |
Total Pages |
: 632 |
Release |
: 1986 |
ISBN-10 |
: UCAL:B4348211 |
ISBN-13 |
: |
Rating |
: 4/5 (11 Downloads) |
Synopsis Numerical Methods in the Theory of Neutron Transport by : Guriĭ Ivanovich Marchuk
Author |
: Bengt G. Carlson |
Publisher |
: |
Total Pages |
: 34 |
Release |
: 1959 |
ISBN-10 |
: UOM:39015086457499 |
ISBN-13 |
: |
Rating |
: 4/5 (99 Downloads) |
Synopsis Numerical Solution of Transient and Steady-state Neutron Transport Problems by : Bengt G. Carlson
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 |
: Clarence E. Lee |
Publisher |
: |
Total Pages |
: 434 |
Release |
: 1962 |
ISBN-10 |
: CORNELL:31924004086066 |
ISBN-13 |
: |
Rating |
: 4/5 (66 Downloads) |
Synopsis The Discrete Sn Approximation to Transport Theory by : Clarence E. Lee
Author |
: Bengt G. Carlson |
Publisher |
: |
Total Pages |
: 54 |
Release |
: 1964 |
ISBN-10 |
: UOM:39015086459610 |
ISBN-13 |
: |
Rating |
: 4/5 (10 Downloads) |
Synopsis Numerical Formulation and Solution of Neutron Transport Problems by : Bengt G. Carlson
Author |
: Richard Bellman |
Publisher |
: American Mathematical Soc. |
Total Pages |
: 340 |
Release |
: 1969 |
ISBN-10 |
: 082181320X |
ISBN-13 |
: 9780821813201 |
Rating |
: 4/5 (0X Downloads) |
Synopsis Transport Theory by : Richard Bellman
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.
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 |
: Elmer Eugene Lewis |
Publisher |
: Wiley-Interscience |
Total Pages |
: 440 |
Release |
: 1984 |
ISBN-10 |
: UOM:39015009827075 |
ISBN-13 |
: |
Rating |
: 4/5 (75 Downloads) |
Synopsis Computational Methods of Neutron Transport by : Elmer Eugene Lewis
Author |
: Herbert Bishop Keller |
Publisher |
: |
Total Pages |
: 48 |
Release |
: 1955 |
ISBN-10 |
: UOM:39015095117290 |
ISBN-13 |
: |
Rating |
: 4/5 (90 Downloads) |
Synopsis On the Numerical Integration of the Neutron Transport Equation by : Herbert Bishop Keller
A procedure for the direct numerical integration of the steady-state, elastic scattering neutron transport equation is presented.
Author |
: Liangzhi Cao |
Publisher |
: Woodhead Publishing |
Total Pages |
: 294 |
Release |
: 2020-08-30 |
ISBN-10 |
: 9780128182222 |
ISBN-13 |
: 0128182229 |
Rating |
: 4/5 (22 Downloads) |
Synopsis Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation by : Liangzhi Cao
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