New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations

New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations
Author: Jacques Tagoudjeu
Publisher: Universal-Publishers
Total Pages: 161
Release: 2011-04
Genre: Mathematics
ISBN: 1599423960


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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.


New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations
Language: en
Pages: 161
Authors: Jacques Tagoudjeu
Categories: Mathematics
Type: BOOK - Published: 2011-04 - Publisher: Universal-Publishers

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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
New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations
Language: en
Pages:
Nuclear Science Abstracts
Language: en
Pages: 680
Authors:
Categories: Nuclear energy
Type: BOOK - Published: 1976 - Publisher:

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A Comparison of Iterative Methods for the Solution of Elliptic Partial Differential Equations, Particularly the Neutron Diffusion Equation
Language: en
Pages: 342
Authors: Kevin N. Schwinkendorf
Categories: Differential equations, Elliptic
Type: BOOK - Published: 1983 - Publisher:

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Two new concepts have been explored in solving the neutron diffusion equation in one and two dimensions. At the present time, the diffusion equation is solved u
Numerical Methods and Techniques Used in the Two-dimensional Neutron-diffusion Program PDQ-5
Language: en
Pages: 90
Authors: L. A. Hageman
Categories: FORTRAN (Computer program language)
Type: BOOK - Published: 1963 - Publisher:

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