The Solution of the Time-dependent, Multi-group Neutron Transport Equation

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ISBN 13 :
Total Pages : 10 pages
Book Rating : 4.:/5 (894 download)

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Book Synopsis The Solution of the Time-dependent, Multi-group Neutron Transport Equation by : J.M. Fletcher

Download or read book The Solution of the Time-dependent, Multi-group Neutron Transport Equation written by J.M. Fletcher and published by . This book was released on 1977 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The solution of the time-dependent, multi-group neutron transport equation

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ISBN 13 :
Total Pages : 11 pages
Book Rating : 4.:/5 (888 download)

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Book Synopsis The solution of the time-dependent, multi-group neutron transport equation by : J. K. Fletcher

Download or read book The solution of the time-dependent, multi-group neutron transport equation written by J. K. Fletcher and published by . This book was released on 1977 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Space-time Flux Synthesis Methods for the Approximate Solution of Time-dependent Boltzmann Neutron Transport Equation

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ISBN 13 :
Total Pages : 42 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Space-time Flux Synthesis Methods for the Approximate Solution of Time-dependent Boltzmann Neutron Transport Equation by : V. Luco

Download or read book Space-time Flux Synthesis Methods for the Approximate Solution of Time-dependent Boltzmann Neutron Transport Equation written by V. Luco and published by . This book was released on 1966 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Numerical Solution of Transient and Steady-state Neutron Transport Problems

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ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Numerical Solution of Transient and Steady-state Neutron Transport Problems by : Bengt G. Carlson

Download or read book Numerical Solution of Transient and Steady-state Neutron Transport Problems written by Bengt G. Carlson and published by . This book was released on 1959 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

High Order Variational Solutions of Time-dependent Neutron Transport Problems

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ISBN 13 :
Total Pages : 306 pages
Book Rating : 4.:/5 (157 download)

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Book Synopsis High Order Variational Solutions of Time-dependent Neutron Transport Problems by : Bruce Carl Wilson

Download or read book High Order Variational Solutions of Time-dependent Neutron Transport Problems written by Bruce Carl Wilson and published by . This book was released on 1985 with total page 306 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Asymptotic Analysis of the Several Competitive Equations to Solve the Time-dependent Neutron Transport Equation

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ISBN 13 :
Total Pages : 12 pages
Book Rating : 4.:/5 (682 download)

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Book Synopsis Asymptotic Analysis of the Several Competitive Equations to Solve the Time-dependent Neutron Transport Equation by :

Download or read book Asymptotic Analysis of the Several Competitive Equations to Solve the Time-dependent Neutron Transport Equation written by and published by . This book was released on 1994 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Using conventional diffusion limit analysis, we asymptotically compare three competitive time-dependent equations (the telegrapher's equation, the time-dependent Simplified P2 (SP2) equation, and the time-dependent Simplified Evcn-Parity (SEP) equation). The time-dependent SP2 equation contains higher order asymptotic approximations of the time-dependent transport equation than the other equations in a physical regime in which the time-dependent diffusion equation is the leading order approximation. In addition, we derive the multigroup modified time-dependent SP2 equation from the multigroup time-dependent transport equation by means of an asymptotic expansion in which the multigroup time-dependent diffusion equation is the leading, order approximation. Numerical comparisons of the timedependent diffusion, the telegrapher's, the time-dependent SP2, and S solutions in 2-D X-Y geometry show that, in most cases, the SP2 solutions contain most of the transport corrections for the diffusion approximation.

Approximate Solution to the Time Dependent Multigroup Neutron Diffusion Equations Using a Restricted Variational Principle

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ISBN 13 :
Total Pages : 108 pages
Book Rating : 4.:/5 (87 download)

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Book Synopsis Approximate Solution to the Time Dependent Multigroup Neutron Diffusion Equations Using a Restricted Variational Principle by : James Conda Robinson

Download or read book Approximate Solution to the Time Dependent Multigroup Neutron Diffusion Equations Using a Restricted Variational Principle written by James Conda Robinson and published by . This book was released on 1966 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Handbook of Nuclear Engineering

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Publisher : Springer Science & Business Media
ISBN 13 : 0387981306
Total Pages : 3701 pages
Book Rating : 4.3/5 (879 download)

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Book Synopsis Handbook of Nuclear Engineering by : Dan Gabriel Cacuci

Download or read book Handbook of Nuclear Engineering written by Dan Gabriel Cacuci and published by Springer Science & Business Media. This book was released on 2010-09-14 with total page 3701 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Finite Difference Solution of the Time Dependent Neutron Group Diffusion Equations

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (953 download)

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Book Synopsis Finite Difference Solution of the Time Dependent Neutron Group Diffusion Equations by :

Download or read book Finite Difference Solution of the Time Dependent Neutron Group Diffusion Equations written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In this thesis two unrelated topics of reactor physics are examined: the prompt jump approximation and alternating direction checkerboard methods. In the prompt jump approximation it is assumed that the prompt and delayed neutrons in a nuclear reactor may be described mathematically as being instantaneously in equilibrium with each other. This approximation is applied to the spatially dependent neutron diffusion theory reactor kinetics model. Alternating direction checkerboard methods are a family of finite difference alternating direction methods which may be used to solve the multigroup, multidimension, time-dependent neutron diffusion equations. The reactor mesh grid is not swept line by line or point by point as in implicit or explicit alternating direction methods; instead, the reactor mesh grid may be thought of as a checkerboard in which all the ''red squares'' and '' black squares'' are treated successively. Two members of this family of methods, the ADC and NSADC methods, are at least as good as other alternating direction methods. It has been found that the accuracy of implicit and explicit alternating direction methods can be greatly improved by the application of an exponential transformation. This transformation is incompatible with checkerboard methods. Therefore, a new formulation of the exponential transformation has been developed which is compatible with checkerboard methods and at least as good as the former transformation for other alternating direction methods. (auth).

An Introduction to Neutron Transport Theory

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ISBN 13 :
Total Pages : 164 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis An Introduction to Neutron Transport Theory by : J. H. Tait

Download or read book An Introduction to Neutron Transport Theory written by J. H. Tait and published by . This book was released on 1965 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Neutron Transport

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Publisher : Springer Nature
ISBN 13 : 3031269322
Total Pages : 284 pages
Book Rating : 4.0/5 (312 download)

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Book Synopsis Neutron Transport by : Ramadan M. Kuridan

Download or read book Neutron Transport written by Ramadan M. Kuridan and published by Springer Nature. This book was released on 2023-10-28 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

A P-9 Multigroup Method for Solution of the Transport Equation in Slab Geometry

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ISBN 13 :
Total Pages : 50 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis A P-9 Multigroup Method for Solution of the Transport Equation in Slab Geometry by : R. C. Gast

Download or read book A P-9 Multigroup Method for Solution of the Transport Equation in Slab Geometry written by R. C. Gast and published by . This book was released on 1960 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Asymptotic Analyses and Numerical Experiments on the Multigroup Time-dependent Simplified P2 Equations

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ISBN 13 :
Total Pages : 226 pages
Book Rating : 4.:/5 (33 download)

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Book Synopsis Asymptotic Analyses and Numerical Experiments on the Multigroup Time-dependent Simplified P2 Equations by : Uncheol Shin

Download or read book Asymptotic Analyses and Numerical Experiments on the Multigroup Time-dependent Simplified P2 Equations written by Uncheol Shin and published by . This book was released on 1995 with total page 226 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Approximate Numerical Solutions to the Time-dependent Neutron Transport Equation Using the Task Algorithm

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ISBN 13 :
Total Pages : 64 pages
Book Rating : 4.:/5 (81 download)

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Book Synopsis Approximate Numerical Solutions to the Time-dependent Neutron Transport Equation Using the Task Algorithm by : Edward Thomas Tomlinson

Download or read book Approximate Numerical Solutions to the Time-dependent Neutron Transport Equation Using the Task Algorithm written by Edward Thomas Tomlinson and published by . This book was released on 1974 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Computational Methods of Neutron Transport

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Publisher : Wiley-Interscience
ISBN 13 :
Total Pages : 440 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Computational Methods of Neutron Transport by : Elmer Eugene Lewis

Download or read book Computational Methods of Neutron Transport written by Elmer Eugene Lewis and published by Wiley-Interscience. This book was released on 1984 with total page 440 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Computational Science

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Publisher : Springer Science & Business Media
ISBN 13 : 9048134110
Total Pages : 476 pages
Book Rating : 4.0/5 (481 download)

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Book Synopsis Nuclear Computational Science by : Yousry Azmy

Download or read book Nuclear Computational Science written by Yousry Azmy and published by Springer Science & Business Media. This book was released on 2010-04-15 with total page 476 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear engineering has undergone extensive progress over the years. In the past century, colossal developments have been made and with specific reference to the mathematical theory and computational science underlying this discipline, advances in areas such as high-order discretization methods, Krylov Methods and Iteration Acceleration have steadily grown. Nuclear Computational Science: A Century in Review addresses these topics and many more; topics which hold special ties to the first half of the century, and topics focused around the unique combination of nuclear engineering, computational science and mathematical theory. Comprising eight chapters, Nuclear Computational Science: A Century in Review incorporates a number of carefully selected issues representing a variety of problems, providing the reader with a wealth of information in both a clear and concise manner. The comprehensive nature of the coverage and the stature of the contributing authors combine to make this a unique landmark publication. Targeting the medium to advanced level academic, this book will appeal to researchers and students with an interest in the progression of mathematical theory and its application to nuclear computational science.

Numerical Formulation and Solution of Neutron Transport Problems

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ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Numerical Formulation and Solution of Neutron Transport Problems by : Bengt G. Carlson

Download or read book Numerical Formulation and Solution of Neutron Transport Problems written by Bengt G. Carlson and published by . This book was released on 1964 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt: