Author: V. ProtopopescuPublisher:
ISBN:
Category :
Languages : en
Pages : 29
Book Description
Diffusion Approximation of a Neutron Transport Equation with Multiplying Boundary Conditions
Author: V. ProtopopescuThe Discrete Sn Approximation to Transport Theory
Author: Clarence E. LeePublisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 434
Book Description
Neutron Transport
Author: Ramadan M. KuridanPublisher: 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.
Numerical Formulation and Solution of Neutron Transport Problems
Author: Bengt G. CarlsonPublisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 54
Book Description
Variational Boundary Conditions for the Spherical Harmonics Approximation to the Neutron Transport Equation
Author: Gerald C. PomraningPublisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 88
Book Description
Finite Difference Approximations to the Neutron Diffusion Equation
Author: H. P. FlattPublisher:
ISBN:
Category : Finite differences
Languages : en
Pages : 40
Book Description
The finite difference approximations used in several one-dimensional neutron diffusion codes are studied from the point of view of conservation of neutrons. A new set of approximation formulae is proposed which conserve neutrons. These formulae differ only slightly from earlier formulae, thus allowing a small effect to be corrected by a small amount of effort."
Variational Solutions to the Neutron Transport Equation in P[subscript N] Approximation
![Variational Solutions to the Neutron Transport Equation in P[subscript N] Approximation PDF](https://books.google.com/books/content/images/frontcover/HxG5NwAACAAJ?fife=w80-h100)
Author: Mahendra Prinath DiasPublisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 598
Book Description
Neutron Transport Theory
Author: B. DavisonPublisher: Oxford : Clarendon Press
ISBN:
Category : Mathematical physics
Languages : en
Pages : 480
Book Description
Handbook of Nuclear Engineering
Author: Dan Gabriel CacuciPublisher: Springer Science & Business Media
ISBN: 0387981306
Category : Science
Languages : en
Pages : 3701
Book Description
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.
Neutron Diffusion
Author: S. ChakravertyPublisher: CRC Press
ISBN: 1351667505
Category : Mathematics
Languages : en
Pages : 216
Book Description
This book is designed for a systematic understanding of nuclear diffusion theory along with fuzzy/interval/stochastic uncertainty. This will serve to be a benchmark book for graduate & postgraduate students, teachers, engineers and researchers throughout the globe. In view of the recent developments in nuclear engineering, it is important to study the basic concepts of this field along with the diffusion processes for nuclear reactor design. Also, it is known that uncertainty is a must in every field of engineering and science and, in particular, with regards to nuclear-related problems. As such, one may need to understand the nuclear diffusion principles/theories corresponding with reliable and efficient techniques for the solution of such uncertain problems. Accordingly this book aims to provide a new direction for readers with basic concepts of reactor physics as well as neutron diffusion theory. On the other hand, it also includes uncertainty (in terms of fuzzy, interval, stochastic) and their applications in nuclear diffusion problems in a systematic manner, along with recent developments. The underlying concepts of the presented methods in this book may very well be used/extended to various other engineering disciplines viz. electronics, marine, chemical, mining engineering and other sciences such as physics, chemistry, biotechnology etc. This book then can be widely applied wherever one wants to model their physical problems in terms of non-probabilistic methods viz. fuzzy/stochastic for the true essence of the real problems.