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Titlebook: Integral Methods in Science and Engineering; Progress in Numerica Christian Constanda,Bardo E.J. Bodmann,Haroldo F. Book 2013 Springer Sci

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A Novel Approach to the Hankel Transform Inversion of the Neutron Diffusion Problem Using the Parsen accurate solution to an approximate problem for the multi-group steady state and multi-region diffusion equation in cylinder coordinates. The Parseval identity is shown to be an efficient technique to solve this type of problem.
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What Is Convergence Acceleration Anyway?, of misfolded proteins described by moments of the filament length distribution. With convergence acceleration, highly accurate moments can be found, as confirmed by a manufactured solution, leading to a more accurate estimate of spongiform disease onset. The second application considers the transie
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On the Fractal Pattern Phenomenology of Geological Fracture Signatures from a Scaling Law,rock evolution for that region. Our discussion showed that fractal analysis is beyond a mere classification scheme but closely related to the dynamics by virtue of a clear self-similarity signature. We came to this conclusion by the structural geology analysis, where we distinguished different fract
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Spectral Boundary Homogenization Problems in Perforated Domains with Robin Boundary Conditions and is the Laplacian, and the spectral problem is posed in a three-dimensional domain ., outside the cavities. The boundary conditions are of the Dirichlet type on the boundary of . and of the Robin type on the boundary of the cavities. The periodicity of the structure is?; it is a small parameter that
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A Finite Element Formulation of the Total Variation Method for Denoising a Set of Data,rent method is used to approximate the differential equation and a fixed-point method is used to solve the resulting nonlinear algebraic equations. However, the differential equation is such that an alternative system of nonlinear equations can be obtained by using a Galerkin based finite element fo
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On the Convergence of the Multi-group Isotropic Neutron ,, Nodal Solution in Cartesian Geometry,dal approach is presented for the transverse integrated multi-group neutron transport equation in a multidimensional Cartesian geometry domain. The resulting coupled system of one-dimensional SN equations for the average angular fluxes are solved by the Laplace Transform technique (LT SN method). We
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