Analysis of severe accidents of VVER 440 reactors

dc.contributor.author	Janíček, Filip
dc.contributor.editor	Mašata, David
dc.date.accessioned	2025-09-22T07:47:26Z
dc.date.available	2025-09-22T07:47:26Z
dc.date.issued	2025
dc.description.abstract-translated	The thesis presents a simulation of a combined severe accident scenario involving a large-break loss-of-coolant accident (LOCA 2×500 mm) and station blackout in a VVER 440/V-213 power plant under nominal operating conditions. The analysis focuses on the in-vessel phase, assessing core degradation, hydrogen production, and the delayed activation of severe accident management systems. Simulations were performed using MELCOR 2.2 and APROS–SA, with thermal-hydraulic behavior compared under identical boundary conditions. Results confirm the importance of in-vessel retention and validate the role of post-Fukushima safety upgrades.	en
dc.format	2 s.	cs
dc.identifier.isbn	978-80-261-1307-2
dc.identifier.isbn	978-80-261-1308-9 (printed)
dc.identifier.uri	http://hdl.handle.net/11025/62806
dc.language.iso	en	en
dc.publisher	University of West Bohemia in Pilsen	en
dc.rights	© University of West Bohemia in Pilsen	en
dc.rights.access	openAccess	en
dc.subject	poster	cs
dc.subject.translated	poster	en
dc.title	Analysis of severe accidents of VVER 440 reactors	en
dc.type	konferenční příspěvek	cs
dc.type	conferenceObject	en
dc.type.status	Peer reviewed	en
local.files.count	2	*
local.files.size	1484925	*
local.has.files	yes	*

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