Please use this identifier to cite or link to this item:
|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|
|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 Institute:||Energy, Transport and Climate|
Files in This Item:
There are no files associated with this item.
Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.