Transactions of the American Nuclear Society
Author : American Nuclear Society
Publisher :
Page : 788 pages
File Size : 40,17 MB
Release : 1999
Category : Nuclear engineering
ISBN :
Author : American Nuclear Society
Publisher :
Page : 788 pages
File Size : 40,17 MB
Release : 1999
Category : Nuclear engineering
ISBN :
Author :
Publisher :
Page : 490 pages
File Size : 50,13 MB
Release : 1993
Category : Power resources
ISBN :
Author : MUSA YAVUZ
Publisher :
Page : 530 pages
File Size : 30,9 MB
Release : 1991
Category :
ISBN :
performance of the new multigrid method degrades with an increasing number of processors, not because of the degradation in the convergence rate, but because of the domination of communication overhead and unemployment of some processors on the coarse grids.
Author : Jacques Tagoudjeu
Publisher : Universal-Publishers
Page : 161 pages
File Size : 17,82 MB
Release : 2011-04
Category : Mathematics
ISBN : 1599423960
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 :
Publisher :
Page : 324 pages
File Size : 38,34 MB
Release : 2004
Category : Dissertations, Academic
ISBN :
"Education, arts and social sciences, natural and technical sciences in the United States and Canada".
Author : Yousry Azmy
Publisher : Springer Science & Business Media
Page : 476 pages
File Size : 40,76 MB
Release : 2010-04-15
Category : Technology & Engineering
ISBN : 9048134110
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.
Author : Moaied Mohamad Miften
Publisher :
Page : 328 pages
File Size : 47,59 MB
Release : 1994
Category :
ISBN :
Author : OECD Nuclear Energy Agency
Publisher : Organisation for Economic Co-operation and Development
Page : 440 pages
File Size : 17,79 MB
Release : 1997
Category : Technology & Engineering
ISBN :
On cover: OECD proceedings
Author : Dan Gabriel Cacuci
Publisher : Springer Science & Business Media
Page : 3701 pages
File Size : 10,24 MB
Release : 2010-09-14
Category : Science
ISBN : 0387981306
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.
Author : Yican Wu
Publisher : Springer
Page : 497 pages
File Size : 50,87 MB
Release : 2019-03-19
Category : Technology & Engineering
ISBN : 9811365202
This book provides a systematic and comprehensive introduction to the neutronics of advanced nuclear systems, covering all key aspects, from the fundamental theories and methodologies to a wide range of advanced nuclear system designs and experiments. It is the first-ever book focusing on the neutronics of advanced nuclear systems in the world. Compared with traditional nuclear systems, advanced nuclear systems are characterized by more complex geometry and nuclear physics, and pose new challenges in terms of neutronics. Based on the achievements and experiences of the author and his team over the past few decades, the book focuses on the neutronics characteristics of advanced nuclear systems and introduces novel neutron transport methodologies for complex systems, high-fidelity calculation software for nuclear design and safety evaluation, and high-intensity neutron source and technologies for neutronics experiments. At the same time, it describes the development of various neutronics designs for advanced nuclear systems, including neutronics design for ITER, CLEAR and FDS series reactors. The book not only summarizes the progress and achievements of the author’s research work, but also highlights the latest advances and investigates the forefront of the field and the road ahead.