Calculation of stress and deformation in fuel rod cladding during pellet-cladding interaction

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dc.contributor.authorHalabuk, Dávidcs
dc.contributor.authorMartinec, Jiřícs
dc.coverage.issue6cs
dc.coverage.volume55cs
dc.date.accessioned2021-08-18T10:53:20Z
dc.date.available2021-08-18T10:53:20Z
dc.date.issued2015-12-18cs
dc.description.abstractThe elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main function of cladding is hermetic separation of nuclear fuel from coolant. The fuel rod works in very specific and difficult conditions, so there are high requirements on its reliability and safety. During irradiation of fuel rods, a state may occur when fuel pellet and cladding interact. This state is followed by changes of stress and deformations in the fuel cladding. The article is focused on stress and deformation analysis of fuel cladding, where two fuels are compared: a fresh one and a spent one, which is in contact with cladding. The calculations are done for 4 different shapes of fuel pellets. It is possible to evaluate which shape of fuel pellet is the most appropriate in consideration of stress and deformation forming in fuel cladding, axial dilatation of fuel, and radial temperature distribution in the fuel rod, based on the obtained results.en
dc.formattextcs
dc.format.extent384-387cs
dc.format.mimetypeapplication/pdfcs
dc.identifier.citationActa Polytechnica. 2015, vol. 55, issue 6, p. 384-387.en
dc.identifier.doi10.14311/AP.2015.55.0384cs
dc.identifier.issn1210-2709cs
dc.identifier.other139245cs
dc.identifier.urihttp://hdl.handle.net/11012/201028
dc.language.isoencs
dc.publisherCzech Technical University in Praguecs
dc.relation.ispartofActa Polytechnicacs
dc.relation.urihttps://ojs.cvut.cz/ojs/index.php/ap/article/view/2942cs
dc.rightsCreative Commons Attribution 4.0 Internationalcs
dc.rights.accessopenAccesscs
dc.rights.sherpahttp://www.sherpa.ac.uk/romeo/issn/1210-2709/cs
dc.rights.urihttp://creativecommons.org/licenses/by/4.0/cs
dc.subjectfuel claddingen
dc.subjectfuel roden
dc.subjectnuclear fuelen
dc.subjectstress and deformation analysisen
dc.titleCalculation of stress and deformation in fuel rod cladding during pellet-cladding interactionen
dc.type.driverarticleen
dc.type.statusPeer-revieweden
dc.type.versionpublishedVersionen
sync.item.dbidVAV-139245en
sync.item.dbtypeVAVen
sync.item.insts2021.08.18 12:53:20en
sync.item.modts2021.08.18 12:14:45en
thesis.grantorVysoké učení technické v Brně. Fakulta strojního inženýrství. Energetický ústavcs
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