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Neutron Diffusion

Neutron Diffusion
Author: S. Chakraverty
Publisher: CRC Press
Total Pages: 216
Release: 2017-04-21
Genre: Mathematics
ISBN: 1351667505

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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.


Nuclear Reactor

Nuclear Reactor
Author: John C. Lee
Publisher: John Wiley & Sons
Total Pages: 658
Release: 2020-02-26
Genre: Technology & Engineering
ISBN: 1119582326

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An introductory text for broad areas of nuclear reactor physics Nuclear Reactor Physics and Engineering offers information on analysis, design, control, and operation of nuclear reactors. The author—a noted expert on the topic—explores the fundamentals and presents the mathematical formulations that are grounded in differential equations and linear algebra. The book puts the focus on the use of neutron diffusion theory for the development of techniques for lattice physics and global reactor system analysis. The author also includes recent developments in numerical algorithms, including the Krylov subspace method, and the MATLAB software, including the Simulink toolbox, for efficient studies of steady-state and transient reactor configurations. In addition, nuclear fuel cycle and associated economics analysis are presented, together with the application of modern control theory to reactor operation. This important book: Provides a comprehensive introduction to the fundamental concepts of nuclear reactor physics and engineering Contains information on nuclear reactor kinetics and reactor design analysis Presents illustrative examples to enhance understanding Offers self-contained derivation of fluid conservation equations Written for undergraduate and graduate students in nuclear engineering and practicing engineers, Nuclear Reactor Physics and Engineering covers the fundamental concepts and tools of nuclear reactor physics and analysis.


Neutron Diffusion Theory

Neutron Diffusion Theory
Author: Bengt Carlson
Publisher:
Total Pages: 12
Release: 1950
Genre: Neutron transport theory
ISBN:

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Theory of Neutron Chain Reactions

Theory of Neutron Chain Reactions
Author: Alvin Martin Weinberg
Publisher:
Total Pages: 260
Release: 1956
Genre: Neutron transport theory
ISBN:

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Finite Difference Approximations to the Neutron Diffusion Equation

Finite Difference Approximations to the Neutron Diffusion Equation
Author: H. P. Flatt
Publisher:
Total Pages: 40
Release: 1960
Genre: Finite differences
ISBN:

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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."


Diffusion of Thermal Neutrons

Diffusion of Thermal Neutrons
Author: A. M. Weinberg
Publisher:
Total Pages: 8
Release: 1947
Genre: Diffusion
ISBN:

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