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Description
| - This paper presents three variants of a hexagonal nodal method for determining neutron ux distribution in a nuclear reactor and its critical number. Their common framework constitutes the few-group, coarse-mesh nite-difference diffusion equations for all nodes inside the core domain. To achieve better accuracy without sacricing efciency, they are corrected by higher order nodal calculations formulated on pairs of nodes using the transverse integration procedure. This leads to three 1D equations coupled through neutron currents at transverse nodal boundaries. Approximation of the coupling has huge impact on the accuracy of transverse-integration based nodal methods and as such receives considerable attention. Three possibilities are discussed that dene the variants of the developed nodal method. Once the transverse coupling term is suitably approximated, solution of nodal equations is computed semi-analytically by using an efcient node-by-node iterative procedure. The three implementations are compare
- This paper presents three variants of a hexagonal nodal method for determining neutron ux distribution in a nuclear reactor and its critical number. Their common framework constitutes the few-group, coarse-mesh nite-difference diffusion equations for all nodes inside the core domain. To achieve better accuracy without sacricing efciency, they are corrected by higher order nodal calculations formulated on pairs of nodes using the transverse integration procedure. This leads to three 1D equations coupled through neutron currents at transverse nodal boundaries. Approximation of the coupling has huge impact on the accuracy of transverse-integration based nodal methods and as such receives considerable attention. Three possibilities are discussed that dene the variants of the developed nodal method. Once the transverse coupling term is suitably approximated, solution of nodal equations is computed semi-analytically by using an efcient node-by-node iterative procedure. The three implementations are compare (en)
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Title
| - Nodal methods for a two-dimensional static multigroup diffusion calculation of nuclear reactors with hexagonal assemblies
- Nodal methods for a two-dimensional static multigroup diffusion calculation of nuclear reactors with hexagonal assemblies (en)
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skos:prefLabel
| - Nodal methods for a two-dimensional static multigroup diffusion calculation of nuclear reactors with hexagonal assemblies
- Nodal methods for a two-dimensional static multigroup diffusion calculation of nuclear reactors with hexagonal assemblies (en)
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skos:notation
| - RIV/49777513:23520/09:00501630!RIV10-MSM-23520___
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http://linked.open...avai/riv/aktivita
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http://linked.open...avai/riv/aktivity
| - P(1M0545), S, Z(MSM4977751301)
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http://linked.open...iv/cisloPeriodika
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http://linked.open...vai/riv/dodaniDat
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http://linked.open...aciTvurceVysledku
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http://linked.open.../riv/druhVysledku
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http://linked.open...iv/duvernostUdaju
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http://linked.open...titaPredkladatele
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http://linked.open...dnocenehoVysledku
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http://linked.open...ai/riv/idVysledku
| - RIV/49777513:23520/09:00501630
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http://linked.open...riv/jazykVysledku
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http://linked.open.../riv/klicovaSlova
| - tok neutronů; šestihranná geometrie; VVER; mnohagrupové přiblížení; difúze; CMFD; kritické číslo reaktoru; nodální metoda; příčná integrace; semi-analytické řešení (en)
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http://linked.open.../riv/klicoveSlovo
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http://linked.open...odStatuVydavatele
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http://linked.open...ontrolniKodProRIV
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http://linked.open...i/riv/nazevZdroje
| - Journal of Interdisciplinary Mathematics
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http://linked.open...in/vavai/riv/obor
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http://linked.open...ichTvurcuVysledku
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http://linked.open...cetTvurcuVysledku
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http://linked.open...vavai/riv/projekt
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http://linked.open...UplatneniVysledku
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http://linked.open...v/svazekPeriodika
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http://linked.open...iv/tvurceVysledku
| - Hanuš, Milan
- Brandner, Marek
- Kužel, Roman
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http://linked.open...n/vavai/riv/zamer
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issn
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number of pages
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http://localhost/t...ganizacniJednotka
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