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The lead-cooled fast reactor is a nuclear reactor design that use molten lead or lead-bismuth eutectic coolant. These materials can be used as the primary coolant because they have low neutron absorption and relatively low melting points. Neutrons are slowed less by interaction with these heavy nuclei (thus not being neutron moderators) so ...
Lead-bismuth eutectic allows operation at lower temperatures while preventing the freezing of the metal coolant in a lower temperature range (eutectic point: 123.5 °C / 255.3 °F). [ 4 ] [ 6 ] Beside its highly corrosive character, [ 4 ] [ 5 ] its main disadvantage is the formation by neutron activation of 209
Power generation. Units planned. 1. Nameplate capacity. 125 MW. [ edit on Wikidata] ALFRED (Advanced Lead-cooled Fast Reactor European Demonstrator) is a planned lead-cooled fast reactor. Designed by Ansaldo Energia from Italy, it represents the last stage of the ELSY and LEADER projects.
Lead-bismuth eutectic. 123.5 °C. 1670 °C. A nuclear reactor coolant is a coolant in a nuclear reactor used to remove heat from the nuclear reactor core and transfer it to electrical generators and the environment . Frequently, a chain of two coolant loops are used because the primary coolant loop takes on short-term radioactivity from the ...
Lead-bismuth eutectic. Lead-Bismuth Eutectic or LBE is a eutectic alloy of lead (44.5 at%) and bismuth (55.5 at%) used as a coolant in some nuclear reactors, and is a proposed coolant for the lead-cooled fast reactor, part of the Generation IV reactor initiative. It has a melting point of 123.5 °C/254.3 °F (pure lead melts at 327 °C/621 °F ...
The unit would be refuelled every year, with each fuel element spending five years in total within the core. Lead coolant temperature would be around 540 °C, giving a high efficiency of 43%, primary heat production of 700 MWt yielding electrical power of 300 MWe. The operational lifespan of the unit could be 60 years.
BREST (reactor) The BREST reactor is a Russian conceptual design for a lead-cooled fast reactor based on a generation IV reactor. Two designs are planned, the BREST-300 (300 MWe) and the BREST-1200 (1200 MWe). The main characteristics of the BREST reactor are passive safety and a closed fuel cycle.
The lead-cooled fast reactor (LFR) [27] features a fast-neutron-spectrum lead or lead/bismuth eutectic coolant with a closed fuel cycle. Proposals include a small 50 to 150 MW e that features a long refueling interval, a modular system rated at 300 to 400 MW e, and a large monolithic plant at 1,200 MW e.