On The Numerical Integration Of The Neutron Transport Equation

Author : Herbert Bishop Keller
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.90/5 ( download)

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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 : Herbert Bishop Keller
Publisher : Andesite Press
ISBN 13 : 9781296832483
Total Pages : 84 pages
Book Rating : 4.81/5 ( download)

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Download or read book On the Numerical Integration of the Neutron Transport Equation written by Herbert Bishop Keller and published by Andesite Press. This book was released on 2015-08-13 with total page 84 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.

Author : Guriĭ Ivanovich Marchuk
Publisher : Harwood Academic Publishers
ISBN 13 :
Total Pages : 632 pages
Book Rating : 4.76/5 ( download)

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Download or read book Numerical Methods in the Theory of Neutron Transport written by Guriĭ Ivanovich Marchuk and published by Harwood Academic Publishers. This book was released on 1986 with total page 632 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.99/5 ( download)

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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:

Author : Liangzhi Cao
Publisher : Woodhead Publishing
ISBN 13 : 0128182229
Total Pages : 294 pages
Book Rating : 4.22/5 ( download)

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Download or read book Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation written by Liangzhi Cao and published by Woodhead Publishing. This book was released on 2020-08-30 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation presents the latest deterministic numerical methods for neutron transport equations (NTEs) with complex geometry, which are of great demand in recent years due to the rapid development of advanced nuclear reactor concepts and high-performance computational technologies. This book covers the wellknown methods proposed and used in recent years, not only theoretical modeling but also numerical results. This book provides readers with a very thorough understanding of unstructured neutron transport calculations and enables them to develop their own computational codes. The fundamentals, numerical discretization methods, algorithms, and numerical results are discussed. Researchers and engineers from utilities and research institutes are provided with examples on how to model an advanced nuclear reactor, which they can then apply to their own research projects and lab settings. Combines the theoretical models with numerical methods and results in one complete resource Presents the latest progress on the topic in an easy-to-navigate format

Author : Elmer Eugene Lewis
Publisher : Wiley-Interscience
ISBN 13 :
Total Pages : 440 pages
Book Rating : 4.75/5 ( download)

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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:

Author : J. H. Tait
Publisher :
ISBN 13 :
Total Pages : 164 pages
Book Rating : 4.53/5 ( download)

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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:

Author : J. Certaine
Publisher :
ISBN 13 :
Total Pages : 140 pages
Book Rating : 4.68/5 ( download)

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Download or read book A Solution of the Neutron Transport Equation written by J. Certaine and published by . This book was released on 1955 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 30 pages
Book Rating : 4.09/5 ( download)

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Download or read book Mechanical Quadrature and the Transport Equation written by Bengt G. Carlson and published by . This book was released on 1961 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Author : Perry A. Newman
Publisher :
ISBN 13 :
Total Pages : 122 pages
Book Rating : 4.40/5 ( download)

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Download or read book Solution of an Initial-value Problem in Linear Transport Theory written by Perry A. Newman and published by . This book was released on 1971 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt: The solution of an initial-value problem in linear transport theory is obtained by using the normal-mode expansion technique of Case. The problem is that of monoenergetic neutrons migrating in a thin slab surrounded by infinitely thick reflectors and the scattering is taken to be isotropic. The results obtained indicate that the reflector may give rise to a branch-cut integral term typical of a semi-infinite medium whereas the central slab may contribute a summation over discrete residue terms. Exact expressions are obtained for these discrete time eigenvalues, and numerical results showing the behavior of real time eigenvalues as a function of the material properties of the slab and reflector are presented. These eigenvalues are finite in number and may disappear into the branch cut or continuum as the material properties are varied; such disappearing eigenvalues correspond to exponentially time-decaying modes. The two largest eigenvalues can be compared with critical dimensions of slabs and spheres, and the numerical values are shown to agree with the critically results of others. In the limit of purely absorbing reflectors or a bare slab, the present solution has the same properties as have been previously reported by others who used the approach of Lehner and Wing.