On the Stochastic Formulation and Interpretation of Neutron Transport Equations PDF Download
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Author: Chio-min Yang
Publisher:
ISBN:
Category :
Languages : en
Pages : 216
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Book Description
Author: Chio-min Yang
Publisher:
ISBN:
Category :
Languages : en
Pages : 216
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Book Description
Author: Emma Horton
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
Author: Mustapha Mokhtar Kharroubi
Publisher: World Scientific
ISBN: 981449819X
Category : Science
Languages : en
Pages : 372
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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.
Author: M. Mokhtar-Kharroubi
Publisher: World Scientific
ISBN: 9789810228699
Category : Mathematics
Languages : en
Pages : 372
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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 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: Bengt G. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 54
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Book Description
Author: Wyatt Duncan Sharp
Publisher:
ISBN:
Category : Finite differences
Languages : en
Pages : 158
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Book Description
Author: J. H. Tait
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 164
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Book Description
Author: Guriĭ Ivanovich Marchuk
Publisher: Harwood Academic Publishers
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 632
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Book Description
Author: S. Chakraverty
Publisher: CRC Press
ISBN: 1351667505
Category : Mathematics
Languages : en
Pages : 216
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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.
Author: Ramadan M. Kuridan
Publisher: Springer Nature
ISBN: 3031269322
Category : Science
Languages : en
Pages : 284
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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.
