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|Title:||Comparison of Lead and Sodium-Cooled Reactors. Safety, Fuel Cycle Performance and Some Economical Aspects|
|Authors:||TUCEK Kamil; WIDER HARTMUT|
|Other Contributors:||CARLSSON JOHAN|
|Citation:||Proceedings of the European Nuclear Conference 2005 p. Reference number 255|
|Publisher:||Cap Grand Large Agency|
|JRC Publication N°:||JRC32066|
|Type:||Contributions to Conferences|
|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 Institute:||Institute for Energy and Transport|
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