Published 1977
| Version v1
Report
Approximative solution for discretized diffusion problems by means of a coarse-mesh method
Creators
- 1. Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.)
Description
A coarse-mesh method to solve the multigroup diffusion equation is described which is derived from the well-known difference formulation by using the difference equations only for those points which lie on cross-points of the primary fine-mesh grid. This leads to additional approximative assumptions on transversal leakage but also to a considerable shortening of the calculation time. (RW)
Abstract (German)
Es wird ueber ein Grobmaschenverfahren zur Loesung der Diffusionsgleichung im Multigruppenbild berichtet, das sich aus der bekannten Formulierung in Differenzenschreibweise dadurch herleitet, dass die Differenzengleichungen nur noch fuer solche Punkte mitgenommen werden, die auf Kreuzungspunkten des urspruenglichen Feinmaschengitters liegen. Das fuehrt zwar zu zusaetzlichen Naeherungsannahmen ueber die transversale Leakage, aber auch zu einer erheblichen Reduktion der Rechenzeit. (RW)Additional details
Additional titles
- Original title (German)
- Naeherungsloesung fuer diskretisierte Diffusionsprobleme durch ein Grobmaschenverfahren
Publishing Information
- Imprint Title
- Technical meeting on coarse-mesh methods: progress in the methods and their application to reactor problems
- Imprint Pagination
- vp.
- Report number
- AED-Conf--77-007-000
Conference
- Title
- progress in the methods and their application to reactor problems.
- Acronym
- Technical meeting on coarse-mesh methods
- Dates
- 25 Jan 1977.
- Place
- Erlangen, Germany, F.R.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 8313138
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FINITE DIFFERENCE METHOD; FLUX SYNTHESIS; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; REACTOR CORES; SPATIAL DISTRIBUTION
- Descriptors DEC
- DISTRIBUTION; ITERATIVE METHODS; NUMERICAL SOLUTION; RADIATION FLUX; REACTOR COMPONENTS; TRANSPORT THEORY
Optional Information
- Notes
- 4 figs. Imprint:Fachtagung ueber Grobmaschen-Rechenverfahren: Fortschritte in der Methodik und in der Anwendung auf Reaktorprobleme.;Vortrags-Kurzfassungen.
- Secondary number(s)
- AED-Conf--77-007-008.