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dc.contributor.authorTUCEK Kamilen_GB
dc.contributor.authorWIDER HARTMUTen_GB
dc.contributor.otherCARLSSON JOHANen_GB
dc.date.accessioned2010-02-25T15:51:20Z-
dc.date.available2006-01-20en_GB
dc.date.available2010-02-25T15:51:20Z-
dc.date.issued2005en_GB
dc.date.submitted2006-01-17en_GB
dc.identifier.citationProceedings of the European Nuclear Conference 2005 p. Reference number 255en_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC32066-
dc.description.abstractThis paper compares the Lead-Cooled Fast Reactor (LFR) and the Sodium-Cooled Fast Reactor (SFR) regarding different aspects of the coolant, safety and economics. A brief review of design and safety experience of an SFR (BN-600) and some safety philosophy of the most developed LFR (BREST) are presented as well. This paper presents results concerning the coolant temperature evolution during three accident scenarios, i.e. Loss-Of-Flow, Loss-Of-Heat-Sink, and Total-Loss-Of-Power. It also studies possible moderators, like BeO and hydrides.en_GB
dc.description.sponsorshipJRC.F.4-Nuclear design safetyen_GB
dc.format.mediumCD-ROMen_GB
dc.languageENGen_GB
dc.publisherCap Grand Large Agencyen_GB
dc.relation.ispartofseriesJRC32066en_GB
dc.titleComparison of Lead and Sodium-Cooled Reactors. Safety, Fuel Cycle Performance and Some Economical Aspectsen_GB
dc.typeArticles in periodicals and booksen_GB
JRC Directorate:Energy, Transport and Climate

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