Results 231 to 240 of about 14,958 (259)

A Fast Nodal Neutron Diffusion Method for Cartesian Geometry

Nuclear Science and Engineering, 1983
A numerical method based on an analytical solution to the three-dimensional two-group diffusion equation has been derived assuming that the flux is a sum of the functions of one variable. In each mesh the incoming currents are used as boundary conditions. The final equations for the average flux and the outgoing currents are of the response matrix type.
Mihály Makai, Claude Maeder
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Adaptive expansion order for diffusion Variational Nodal Method

Annals of Nuclear Energy, 2018
Abstract The Variational Nodal Method (VNM) has been employed as the diffusion module in our PWR core analysis code Bamboo-Core within our PWR fuel management code system NECP-Bamboo. It expands the nodal volumetric flux and surface partial currents into the sums of orthogonal basis functions without using the transverse integration technique.
Boning Liang, Hongchun Wu, Yunzhao Li
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Studies on Nodal Integral Methods for the Convection-Diffusion Equation

Nuclear Science and Engineering, 2001
The computational efficiencies of two nodal integral methods for the numerical solution of linear convection-diffusion equations are studied. Although the first, which leads to a second-order spatial truncation error, has been reported earlier, it is reviewed in order to lead logically to the development here of the second, which has a third-order ...
E. P. E. Michael, J. Dorning, null Rizwan-Uddin   +2 more
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Unified Formulation of Nodal Expansion Method and Analytic Nodal Method Solutions to Two-Group Diffusion Equations

Nuclear Science and Engineering, 2001
This paper demonstrates that the analytic nodal method (ANM) solution to two-group (2-G) diffusion equations can be formulated in the same way as the nodal expansion method (NEM) solution, and ther...
Hyun Chul Lee, Chang Hyo Kim
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On the use of the SPH method in nodal diffusion analyses of SFR cores

Annals of Nuclear Energy, 2015
Abstract A number of recent studies successfully demonstrated the feasibility of using Monte Carlo code Serpent to generate few-group cross sections (XS) for full core nodal diffusion analyses of SFR cores. The current study investigated the potential of the SPH method, applied to correct the few-group XS produced by Serpent, to further improve the ...
Nikitin, E., Fridman, E., Mikityuk, K.
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A Coarse Nodal Method For Solving The Neutron Diffusion Equation.

1973
PhD ; Energy ; Nuclear physics ; University of Michigan, Horace H. Rackham School of Graduate Studies ; http://deepblue.lib.umich.edu/bitstream/2027.42/189751/2/7324691 ...
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A Nodal Diffusion Technique for Synthetic Acceleration of NodalS_nCalculations

Nuclear Science and Engineering, 1985
A diffusion theory method is developed for synthetic acceleration of nodal Sn calculations in multidimensional Cartesian geometries.
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Development of an Embedded Scheme for Improved Nodal Diffusion Solutions

Mathematics and Computation 2021, 2021
R. Prinsloo, S.A. Groenewald, D.I. Tomasevic   +2 more
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A Nodal Method for Transient Analysis of Multigroup Neutron Diffusion

1988
The purpose of the nodal model developed is to analyze the fast transient behavior of the reactor cores on the basis of time dependent multigroup neutron diffusion equation and precursor density equations given below. Although the current form of the model, which analyzes the transient behavior in one dimension without introducing the affects of the ...
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A Legendre polynomial nodal model for 2-D diffusion problems

Annals of Nuclear Energy, 1986
Abstract A polynomial nodal model which uses Legendre expansions was developed for the multigroup diffusion equation in 2-D. The development depends upon a least-squares minimization of the trial functions over a 2-D node. Analytical expressions were developed for the polynomial coefficients.
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