Wielandt method applied to the diffusion equations discretized by finite element nodal methods
Description
Nowadays the numerical methods of solution to the diffusion equation by means of algorithms and computer programs result so extensive due to the great number of routines and calculations that should carry out, this rebounds directly in the execution times of this programs, being obtained results in relatively long times. This work shows the application of an acceleration method of the convergence of the classic method of those powers that it reduces notably the number of necessary iterations for to obtain reliable results, what means that the compute times they see reduced in great measure. This method is known in the literature like Wielandt method and it has incorporated to a computer program that is based on the discretization of the neutron diffusion equations in plate geometry and stationary state by polynomial nodal methods. In this work the neutron diffusion equations are described for several energy groups and their discretization by means of those called physical nodal methods, being illustrated in particular the quadratic case. It is described a model problem widely described in the literature which is solved for the physical nodal grade schemes 1, 2, 3 and 4 in three different ways: to) with the classic method of the powers, b) method of the powers with the Wielandt acceleration and c) method of the powers with the Wielandt modified acceleration. The results for the model problem as well as for two additional problems known as benchmark problems are reported. Such acceleration method can also be implemented to problems of different geometry to the proposal in this work, besides being possible to extend their application to problems in 2 or 3 dimensions. (Author)
Availability note (English)
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Additional details
Additional titles
- Original title (Spanish)
- Metodo de Wielandt aplicado a las ecuaciones de difusion discretizadas por metodos nodales de elemento finito
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- INIS-MX--1954
Conference
- Title
- 14. Annual Congress of the SNM; 21. Annual Meeting of the SMSR
- Original Conference Title
- Energia Nuclear y Seguridad Radiologica: Nuevos retos y perspectivas
- Dates
- 10-13 Sep 2003
- Place
- Guadalajara (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 36115700
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; CROSS SECTIONS; DIFFUSION EQUATIONS; FINITE ELEMENT METHOD; FISSION NEUTRONS; ITERATIVE METHODS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NUMERICAL SOLUTION
- Descriptors DEC
- BARYONS; CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTARY PARTICLES; EQUATIONS; FERMIONS; HADRONS; MATHEMATICAL SOLUTIONS; NEUTRONS; NUCLEONS; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX