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New Splitting Iterative Methods for Solving Multidimensional Neutron Transport
Equations als eBook von Jacques Tagoudjeu
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Jacques Tagoudjeusearch
New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations (2011)search

ISBN: 9781599423968search or 1599423960, in english, 160 pages, Dissertation.Com, Paperback, Used.
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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. paperback, Label: Dissertation.Com, Dissertation.Com, Produktgruppe: Book, Publiziert: 2011-04-10, Studio: Dissertation.Com, Verkaufsrang: 6981414.
From Seller/Antiquarian, tabletopart.
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. paperback, Label: Dissertation.Com, Dissertation.Com, Produktgruppe: Book, Publiziert: 2011-04-10, Studio: Dissertation.Com, Verkaufsrang: 6981414.
2

Jacques Tagoudjeusearch
New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations (2011)search

ISBN: 9781599423968search or 1599423960, in english, 160 pages, Dissertation.Com, Paperback, New.
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From Seller/Antiquarian, Amazon.com.
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. paperback, Label: Dissertation.Com, Dissertation.Com, Produktgruppe: Book, Publiziert: 2011-04-10, Studio: Dissertation.Com, Verkaufsrang: 6981414.
From Seller/Antiquarian, Amazon.com.
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. paperback, Label: Dissertation.Com, Dissertation.Com, Produktgruppe: Book, Publiziert: 2011-04-10, Studio: Dissertation.Com, Verkaufsrang: 6981414.
3

Jacques Tagoudjeusearch
New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations (2011)search

ISBN: 9781599423968search or 1599423960, in english, 160 pages, Dissertation.com, Paperback, Used.
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From Seller/Antiquarian, Vanderbilt CA.
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New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations als eBook von Jacques Tagoudjeusearch

ISBN: 9781612338873search or 1612338879, in english, Universal-Publishers.com, New, ebook, digital download.
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New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations ab 20.99 EURO.
New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations ab 20.99 EURO.
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Jacques Tagoudjeusearch
New Splitting Iterative Methods For Solving Multidimensional Neutron Transport Equationssearch

ISBN: 9781599423968search or 1599423960, in english, Universal-Publishers.com, Paperback, New.
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New-Splitting-Iterative-Methods-for-Solving-Multidimensional-Neutron-Transport-Equations~~Jacques-Tagoudjeu, New Splitting Iterative Methods For Solving Multidimensional Neutron Transport Equations.
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New-Splitting-Iterative-Methods-for-Solving-Multidimensional-Neutron-Transport-Equations~~Jacques-Tagoudjeu, New Splitting Iterative Methods For Solving Multidimensional Neutron Transport Equations.
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