Multiscale thermal-hydraulic analysis of experimental facilities in support of the lead-cooled fast reactors development

dc.contributor.author	Del Moro, Tommaso
dc.contributor.editor	Mašata, David
dc.date.accessioned	2025-09-22T08:38:17Z
dc.date.available	2025-09-22T08:38:17Z
dc.date.issued	2025
dc.description.abstract-translated	Nuclear energy plays a key role in reducing carbon emissions and enabling a sustainable energy transition. Among advanced reactor designs, Lead-cooled Fast Reactors (LFRs) stand out as a promising Generation IV technology due to their improved safety, fuel eSiciency, and waste reduction capabilities. By using Heavy Liquid Metals (HLMs) as coolants and MOX fuel from reprocessed spent fuel, LFRs help close the fuel cycle and minimize long-lived radioactive waste.	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/11025/62825
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	Multiscale thermal-hydraulic analysis of experimental facilities in support of the lead-cooled fast reactors development	en
dc.type	konferenční příspěvek	cs
dc.type	conferenceObject	en
dc.type.status	Peer reviewed	en
local.files.count	2	*
local.files.size	2204095	*
local.has.files	yes	*

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