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Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.3/5 (91 download)
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:
Download or read book Numerical Solution of Transient and Steady-State Neutron Transport Problems written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 13 :
Total Pages : 52 pages
Book Rating : 4.3/5 (91 download)
Download or read book The DSN and TDC Neutron Transport Codes written by B. Carlson and published by . This book was released on 1960 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 13 :
Total Pages : 306 pages
Book Rating : 4.:/5 (157 download)
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:
Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.3/5 (91 download)
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:
Author : Herbert Bishop Keller
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.3/5 (91 download)
Download or read book On the Numerical Integration of the Neutron Transport Equation written by Herbert Bishop Keller and published by . This book was released on 1955 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt: A procedure for the direct numerical integration of the steady-state, elastic scattering neutron transport equation is presented.
Author : B. Carlson
Publisher :
ISBN 13 :
Total Pages : 38 pages
Book Rating : 4.3/5 (91 download)
Download or read book The DSN and TDC Neutron Transport Codes written by B. Carlson and published by . This book was released on 1960 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 13 : 9781376953213
Total Pages : 64 pages
Book Rating : 4.9/5 (532 download)
Download or read book Approximate Solutions of Steady-State Neutron Transport Problems for Slabs written by Herbert Keller and published by Sagwan Press. This book was released on 2018-02-07 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
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Author : Mahendra Prinath Dias
Publisher :
ISBN 13 :
Total Pages : 598 pages
Book Rating : 4.:/5 (97 download)
Download or read book Variational Solutions to the Neutron Transport Equation in P[subscript N] Approximation written by Mahendra Prinath Dias and published by . This book was released on 1982 with total page 598 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : L. Fox
Publisher : Elsevier
ISBN 13 : 1483149471
Total Pages : 521 pages
Book Rating : 4.4/5 (831 download)
Download or read book Numerical Solution of Ordinary and Partial Differential Equations written by L. Fox and published by Elsevier. This book was released on 2014-05-15 with total page 521 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 : James W. Smiley
Publisher :
ISBN 13 :
Total Pages : 70 pages
Book Rating : 4.3/5 (91 download)
Download or read book STREAK, a Numerical Solution for Space-time Neutron Diffusion Equations written by James W. Smiley and published by . This book was released on 1966 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Jacques Tagoudjeu
Publisher : Universal-Publishers
ISBN 13 : 1599423960
Total Pages : 161 pages
Book Rating : 4.5/5 (994 download)
Download or read book New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations written by Jacques Tagoudjeu and published by Universal-Publishers. This book was released on 2011-04 with total page 161 pages. Available in PDF, EPUB and Kindle. Book excerpt: This thesis focuses on iterative methods for the treatment of the steady state neutron transport equation in slab geometry, bounded convex domain of Rn (n = 2,3) and in 1-D spherical geometry. We introduce a generic Alternate Direction Implicit (ADI)-like iterative method based on positive definite and m-accretive splitting (PAS) for linear operator equations with operators admitting such splitting. This method converges unconditionally and its SOR acceleration yields convergence results similar to those obtained in presence of finite dimensional systems with matrices possessing the Young property A. The proposed methods are illustrated by a numerical example in which an integro-differential problem of transport theory is considered. In the particular case where the positive definite part of the linear equation operator is self-adjoint, an upper bound for the contraction factor of the iterative method, which depends solely on the spectrum of the self-adjoint part is derived. As such, this method has been successfully applied to the neutron transport equation in slab and 2-D cartesian geometry and in 1-D spherical geometry. The self-adjoint and m-accretive splitting leads to a fixed point problem where the operator is a 2 by 2 matrix of operators. An infinite dimensional adaptation of minimal residual and preconditioned minimal residual algorithms using Gauss-Seidel, symmetric Gauss-Seidel and polynomial preconditioning are then applied to solve the matrix operator equation. Theoretical analysis shows that the methods converge unconditionally and upper bounds of the rate of residual decreasing which depend solely on the spectrum of the self-adjoint part of the operator are derived. The convergence of theses solvers is illustrated numerically on a sample neutron transport problem in 2-D geometry. Various test cases, including pure scattering and optically thick domains are considered.
Author : Ramadan M. Kuridan
Publisher : Springer Nature
ISBN 13 : 3031269322
Total Pages : 284 pages
Book Rating : 4.0/5 (312 download)
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.
Author :
Publisher :
ISBN 13 :
Total Pages : 492 pages
Book Rating : 4.:/5 (319 download)
Download or read book Argonne Code Center written by and published by . This book was released on 1977 with total page 492 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Chih Ping Fan
Publisher :
ISBN 13 :
Total Pages : 450 pages
Book Rating : 4.:/5 (148 download)
Download or read book Approximate Solution to Neutron Transport Equation Using Spherical Harmonics Expansion and a Conservative Variational Principle written by Chih Ping Fan and published by . This book was released on 1984 with total page 450 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Clarence E. Lee
Publisher :
ISBN 13 :
Total Pages : 414 pages
Book Rating : 4.3/5 (91 download)
Download or read book The Discrete Sn Approximation to Transport Theory written by Clarence E. Lee and published by . This book was released on 1962 with total page 414 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Samuel Schechter
Publisher :
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4.:/5 (224 download)
Download or read book Approximate Solutions of Steady-state Neutron Transport Problems for Slabs written by Samuel Schechter and published by . This book was released on 1958 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:
