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The lead-cooled fast reactor is a nuclear reactor design that uses 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 these reactors operate with fast neutrons.
The concept is generally similar to sodium-cooled fast reactors, and most liquid-metal fast reactors have used sodium instead of lead. Few lead-cooled reactors have been constructed, except for the Soviet submarine K-27 and all 7 of the Soviet Alfa-class submarines (though these were beryllium-moderated intermediate energy reactors rather than fast reactors).[1] However, a number of proposed and one in construction new nuclear reactor designs are lead-cooled.
Fuel designs being explored for this reactor scheme include fertile uranium as a metal, metal oxide or metal nitride.[2]
The lead-cooled reactor design has been proposed as a generation IV reactor. Plans for future implementation of this type of reactor include modular arrangements rated at 300 to 400 MWe, and a large monolithic plant rated at 1,200 MWe.
- ^ Reistad, Ole; Ølgaard, Povl (April 2006). Russian Nuclear Power Plants for Marine Applications (NKS-138 ed.). Nordic nuclear safety research. ISBN 87-7893-200-9. Retrieved 23 September 2024.
- ^ Allen, T. R.; Crawford, D. C. (2007). "Lead-Cooled Fast Reactor Systems and the Fuels and Materials Challenges". Science and Technology of Nuclear Installations. 2007: 1–11. doi:10.1155/2007/97486.