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On The Numerical Integration Of The Neutron Transport Equation
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Book Synopsis On the Numerical Integration of the Neutron Transport Equation by : Herbert Bishop Keller
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.
Book Synopsis On the Numerical Integration of the Neutron Transport Equation by : Herbert Bishop Keller
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.
Book Synopsis Numerical Methods in the Theory of Neutron Transport by : Guriĭ Ivanovich Marchuk
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:
Book Synopsis On the Numerical Integration of the Neutron Transport Equation - Primary Source Edition by : Herbert Bishop Keller
Download or read book On the Numerical Integration of the Neutron Transport Equation - Primary Source Edition written by Herbert Bishop Keller and published by Nabu Press. This book was released on 2014-01-05 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is a reproduction of a book published before 1923. This book may have occasional imperfections such as missing or blurred pages, poor pictures, errant marks, etc. that were either part of the original artifact, or were introduced by the scanning process. We believe this work is culturally important, and despite the imperfections, have elected to bring it back into print as part of our continuing commitment to the preservation of printed works worldwide. We appreciate your understanding of the imperfections in the preservation process, and hope you enjoy this valuable book.
Book Synopsis Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation by : Liangzhi Cao
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
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:
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:
Book Synopsis Some numerical methods for solving the neutron transport equation by : C. Budd
Download or read book Some numerical methods for solving the neutron transport equation written by C. Budd and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
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:
Book Synopsis The Discrete Sn Approximation to Transport Theory by : Clarence E. Lee
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 434 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Book Synopsis An Innovative Computational Method for Predicting Neutron Transport by :
Download or read book An Innovative Computational Method for Predicting Neutron Transport written by and published by . This book was released on 2000 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt: This final report indicates the work performed under DNA-OO1-96-0103 during the span covering June 1996 through June 1998. Several important findings are reported strongly suggesting that the proposed numerical methodology can perform as initially conceived upon resolving the remaining technical issue involving the numerical integration of integral containing Hadamard type kernels. Preliminary calculations are presented in bath cartesian and spherical geometries indicating that the symbolically augmented method has merit when addressing the numerical simulation of the integral form of the linearized Boltzmann transport equation.
Book Synopsis A Solution of the Neutron Transport Equation by : J. Certaine
Download or read book A Solution of the Neutron Transport Equation written by J. Certaine and published by . This book was released on 1954 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Method of Moments for Solving the Neutron Transport Equation by : Bengt G. Carlson
Download or read book A Method of Moments for Solving the Neutron Transport Equation written by Bengt G. Carlson and published by . This book was released on 1965 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations by : Jacques Tagoudjeu
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.
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.
Book Synopsis A Solution of the Neutron Transport Equation by : J. Certaine
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:
