Author: E. Nasjleti
Publisher:
ISBN:
Category :
Languages : en
Pages : 25
Book Description
Diffusion of Neutrons in a Heavy Elements Medium and Application to the Multigroup Diffusion Theory
Author: E. Nasjleti
Publisher:
ISBN:
Category :
Languages : en
Pages : 25
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 25
Book Description
Introduction to the Theory of Neutron Diffusion
Author: K. M. Case
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 192
Book Description
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 192
Book Description
Neutron Diffusion
Author: S. Chakraverty
Publisher: 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.
Publisher: 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.
Introduction T the Theory of Diffusion and Slowing Down of Neutrons
Author: Robert Eugene Marshak
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 40
Book Description
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 40
Book Description
Theory of Neutron Chain Reactions
Author: Alvin Martin Weinberg
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 260
Book Description
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 260
Book Description
Diffusion of Thermal Neutrons
Author: A. M. Weinberg
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 8
Book Description
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 8
Book Description
Neutron Slowing Down in Group Diffusion Theory
Author: Robert Linton Hellens
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 178
Book Description
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 178
Book Description
Neutron Diffusion Theory
Author: Bengt Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 12
Book Description
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 12
Book Description
Introduction to the Theory of Neutron Diffusion
Author: Kenneth M. Case
Publisher:
ISBN:
Category :
Languages : en
Pages : 174
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 174
Book Description
Multigroup Diffusion Theory Formulation of the Calculation of the Mean Square Slowing Down Distance in an Infinite Medium
Author: B. J. Toppel
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 30
Book Description
Simple expressions for the mean square distance from a point fission source for slowing down past a given energy and for the mean square distance of neutrons that belong to a given energy group are derived within the framework of multigroup diffusion theory. The expressions may be applied to systems having arbitrary group transfer cross sections.
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 30
Book Description
Simple expressions for the mean square distance from a point fission source for slowing down past a given energy and for the mean square distance of neutrons that belong to a given energy group are derived within the framework of multigroup diffusion theory. The expressions may be applied to systems having arbitrary group transfer cross sections.