Numerical Solution of Transient and Steady-state Neutron Transport Problems PDF Download

Author: Bengt G. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 34

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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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A general numerical procedure, called the discrete S/sub n/ method, for solving the neutron transport equation is described. The main topics relate to the derivation of suitable difference equations, and to the problem of solving these, while maintaining generality, accuracy, and reasonable computing speed. A few comparisons with other methods are made. (auth).

Author: B. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 52

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This report describes two reactor codes, one for the one-dimensional geometries (DSN) and the other for the finite cylindrical case (TDC), based on the transport difference equations and calculation methods developed in "Numerical Solutions of Transient and Steady State Neutron Transport Problems" (LA-2260). Appendices I and II, which contain the actual machine codes, have been separated from the descriptive part of the report to make it easier for the user to study the material and apply it to problems.

Author: Bruce Carl Wilson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 306

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Author: Bengt G. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 54

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Author: Herbert Bishop Keller
Publisher:
ISBN:
Category : Elastic scattering
Languages : en
Pages : 48

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A procedure for the direct numerical integration of the steady-state, elastic scattering neutron transport equation is presented.

Author: B. Carlson
Publisher:
ISBN:
Category : Neutron transport theory
Languages : en
Pages : 38

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Book Description
This report describes two reactor codes, one for the one-dimensional geometries (DSN) and the other for the finite cylindrical case (TDC), based on the transport difference equations and calculation methods developed in "Numerical Solutions of Transient and Steady State Neutron Transport Problems" (LA-2260). Appendices I and II, which contain the actual machine codes, have been separated from the descriptive part of the report to make it easier for the user to study the material and apply it to problems.

Author: Herbert Keller
Publisher: Sagwan Press
ISBN: 9781376953213
Category : History
Languages : en
Pages : 64

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Book Description
This work has been selected by scholars as being culturally important, and is part of the knowledge base of civilization as we know it. This work was reproduced from the original artifact, and remains as true to the original work as possible. Therefore, you will see the original copyright references, library stamps (as most of these works have been housed in our most important libraries around the world), and other notations in the work. This work is in the public domain in the United States of America, and possibly other nations. Within the United States, you may freely copy and distribute this work, as no entity (individual or corporate) has a copyright on the body of the work. As a reproduction of a historical artifact, this work may contain missing or blurred pages, poor pictures, errant marks, etc. Scholars believe, and we concur, that this work is important enough to be preserved, reproduced, and made generally available to the public. We appreciate your support of the preservation process, and thank you for being an important part of keeping this knowledge alive and relevant.

Author: L. Fox
Publisher: Elsevier
ISBN: 1483149471
Category : Mathematics
Languages : en
Pages : 521

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Numerical Solution of Ordinary and Partial Differential Equations is based on a summer school held in Oxford in August-September 1961. The book is organized into four parts. The first three cover the numerical solution of ordinary differential equations, integral equations, and partial differential equations of quasi-linear form. Most of the techniques are evaluated from the standpoints of accuracy, convergence, and stability (in the various senses of these terms) as well as ease of coding and convenience of machine computation. The last part, on practical problems, uses and develops the techniques for the treatment of problems of the greatest difficulty and complexity, which tax not only the best machines but also the best brains. This book was written for scientists who have problems to solve, and who want to know what methods exist, why and in what circumstances some are better than others, and how to adapt and develop techniques for new problems. The budding numerical analyst should also benefit from this book, and should find some topics for valuable research. The first three parts, in fact, could be used not only by practical men but also by students, though a preliminary elementary course would assist the reading.

Author: Mahendra Prinath Dias
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 598

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