Full metadata record
DC FieldValueLanguage
dc.contributor.authorZeman, Vladimír
dc.contributor.authorHlaváč, Zdeněk
dc.date.accessioned2013-04-29T12:13:30Z
dc.date.available2013-04-29T12:13:30Z
dc.date.issued2012
dc.identifier.citationApplied and Computational Mechanics. 2012, vol. 6, no. 2, p. 219-230.en
dc.identifier.issn1802-680X (Print)
dc.identifier.issn2336-1182 (Online)
dc.identifier.urihttp://hdl.handle.net/11025/1842
dc.identifier.urihttp://www.kme.zcu.cz/acm/index.php/acm/article/view/187/191
dc.description.abstractThe paper deals with dynamic load calculation of the hexagonal type nuclear fuel assembly caused by spatial motion of the support plates in the reactor core. The support plate motion is excited by pressure pulsations generated by main circulation pumps in the coolant loops of the primary circuit of the nuclear power plant. Slightly different pumps revolutions generate the beat vibrations which causes an amplification of fuel assembly component dynamic deformations and fuel rods coating abrasion. The cyclic and central symmetry of the fuel assembly makes it possible the system decomposition into six identical revolved fuel rod segments which are linked with central tube and skeleton by several spacer grids in horizontal planes. The modal synthesis method with condensation of the fuel rod segments is used for calculation of the normal and friction forces transmitted between fuel rods and spacer grids cells.en
dc.format12 s.
dc.format.mimetypeapplication/pdf
dc.language.isoenen
dc.publisherUniversity of West Bohemiaen
dc.relation.ispartofseriesApplied and Computational Mechanicsen
dc.rights© 2012 University of West Bohemia. All rights reserved.en
dc.subjectmodální logikacs
dc.subjectzátěžové charakteristikycs
dc.subjectpalivové články jaderných reaktorůcs
dc.subjectsimulace a modelovánícs
dc.titleDynamic response of nuclear fuel assembly excited by pressure pulsationsen
dc.typečlánekcs
dc.typearticleen
dc.rights.accessopenAccessen
dc.type.versionpublishedVersionen
dc.subject.translatedmodal logicen
dc.subject.translatedload characteristicsen
dc.subject.translatednuclear reactors fuel elementsen
dc.subject.translatedsimulation and modellingen
dc.type.statusPeer-revieweden
Appears in Collections:Volume 6, number 2 (2012)
Články / Articles (KME)
Volume 6, number 2 (2012)

Files in This Item:
File Description SizeFormat 
191.pdf5,48 MBAdobe PDFView/Open


Please use this identifier to cite or link to this item: http://hdl.handle.net/11025/1842

Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.