MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION

dc.contributor.author	Cech, Miroslav
dc.contributor.author	Sevecek, Martin
dc.date.accessioned	2023-01-18T14:34:17Z
dc.date.available	2023-01-18T14:34:17Z
dc.date.issued	2016
dc.identifier.citation	Acta Polytechnica. 2016, vol. 4, no. 0, p. 13-18.
dc.identifier.issn	1210-2709 (print)
dc.identifier.issn	1805-2363 (online)
dc.identifier.uri	http://hdl.handle.net/10467/105850
dc.description.abstract	This paper describes materials made of zirconium-based alloys used for nuclear fuel cladding fabrication. It is focused on corrosion problems their theoretical description and modeling in nuclear engineering.	en
dc.format.mimetype	application/pdf
dc.language.iso	eng
dc.publisher	České vysoké učení technické v Praze	cs
dc.publisher	Czech Technical University in Prague	en
dc.relation.ispartofseries	Acta Polytechnica
dc.relation.uri	https://ojs.cvut.cz/ojs/index.php/APP/article/view/3740
dc.rights	Creative Commons Attribution 4.0 International License	en
dc.rights.uri	http://creativecommons.org/licenses/by/4.0/
dc.title	MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION
dc.type	article	en
dc.date.updated	2023-01-18T14:34:17Z
dc.identifier.doi	10.14311/AP.2016.4.0013
dc.rights.access	openAccess
dc.type.status	Peer-reviewed
dc.type.version	publishedVersion

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