Comparison of Lead and Sodium-Cooled Reactors. Safety, Fuel Cycle Performance and Some Economical Aspects

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.

TUCEK Kamil;  WIDER Hartmut; 

CARLSSON Johan; 

2006-01-20

Cap Grand Large Agency

JRC32066

https://publications.jrc.ec.europa.eu/repository/handle/JRC32066,