Title: Comparison of Lead and Sodium-Cooled Reactors. Safety, Fuel Cycle Performance and Some Economical Aspects
Other Contributors: CARLSSON JOHAN
Citation: Proceedings of the European Nuclear Conference 2005 p. Reference number 255
Publisher: Cap Grand Large Agency
Publication Year: 2005
JRC N°: JRC32066
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC32066
Type: Articles in periodicals and books
Abstract: This 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.
JRC Directorate:Energy, Transport and Climate

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