Results 261 to 270 of about 16,653 (299)
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A Hennart Nodal Method for the Diffusion Equation

Nuclear Science and Engineering, 1995
A modification of the Hennart nodal method for neutron diffusion problems is presented. The final system of equations obtained by this method is not positive definite. However, a flux elimination technique leads to a simple positive definite system, which can be solved by the traditional iterative methods.
P. Lesaint, S. Noceir, D. Verwaerde
openaire   +1 more source

High-Order Analytical Nodal Method for the Multigroup Diffusion Equations

Numerical Algorithms, 2003
zbMATH Open Web Interface contents unavailable due to conflicting licenses.
M. Akhmouch, N. Guessous
openaire   +1 more source

An Adaptive Approach to Variational Nodal Diffusion Problems

Nuclear Science and Engineering, 2001
An adaptive grid method is presented for the solution of neutron diffusion problems in two dimensions. The primal hybrid finite elements employed in the variational nodal method are used to reduce the diffusion equation to a coupled set of elemental response matrices.
Hui Zhang, E. E. Lewis
openaire   +1 more source

A physical interpretation and benchmarking of nodal diffusion error estimators

Annals of Nuclear Energy, 1998
Abstract An error estimator application was evaluated for the analysis and interpretation of nodal solutions of the neutron diffusion problem extended to reactor core level. This error estimator application relies on the residual of the equation and gives a global and local characterisation of approximate solutions by the determination of unbalances ...
F.E. Jatuff, C.J. Gho
openaire   +1 more source

A Fundamental Derivation of the Nodal Diffusion Equation and Its Variation

Nuclear Science and Engineering, 1990
A new nodal interface diffusion equation is derived by applying the second form of Green’s theorem to the transverse-integrated diffusion equation.
Hoju Moon, Samuel H. Levine
openaire   +1 more source

Variational Formulation of a Higher Order Nodal Diffusion Method

Nuclear Science and Engineering, 1990
A higher order nodal diffusion method is formulated, based on variational principle Kantorovich's variational method, and the patch test. In this paper, the relationship between finite element and nodal methods is discussed and the differences are pointed out.
D. V. Altiparmakov, Dj. Tomašević
openaire   +1 more source

Extension of nodal diffusion solver of Ants to hexagonal geometry

Kerntechnik, 2019
Abstract The development of a new computational framework for core multi-physics problems, called Kraken, has been started at VTT Technical Research Centre of Finland Ltd. The framework consists of modular neutronics, thermal hydraulics and thermal mechanics solvers, and is based on the use of continuous-energy Monte Carlo reactor ...
Sahlberg, Ville, Rintala, Antti
openaire   +5 more sources

Nodal diffusion methods for space-time neutron kinetics

Progress in Nuclear Energy, 2007
After recalling the space-time kinetics equations, the finite-element method is presented as a general discretization technique and then applied to the so-called nodal diffusion methods, both primal and mixed-hybrid ones, for the space discretization. In the last section of the paper, a general nodal formalism is applied to the time discretization.
Lawrence M. Grossman   +1 more
exaly   +2 more sources

Nonlinear Analytic and Semi-Analytic Nodal Methods for Multigroup Neutron Diffusion Calculations

open access: yesJournal of Nuclear Science and Technology, 2002
Two advanced nodal methods for the solution of the multigroup neutron diffusion equations are developed, using the nonlinear coarse-mesh finite difference (CMFD) scheme.
Nam Zin Cho
exaly   +1 more source

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
openaire   +1 more source

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