Lead-cooled fast reactor

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Lead-cooled fast reactor (LFR) is a type of nuclear reactor that uses lead or lead-bismuth eutectic (LBE) as a coolant. LFRs are part of the Generation IV reactor designs, which aim to improve upon the safety, sustainability, and economic viability of previous generations of nuclear reactors.

Design and Operation[edit | edit source]

The LFR design utilizes fast neutron spectrum and lead-based coolant. The lead or LBE serves as both the reactor coolant and the neutron reflector. The high boiling point of lead allows the reactor to operate at atmospheric pressure, reducing the risk of a loss-of-coolant accident.

The fuel for LFRs can be either enriched uranium, plutonium, or minor actinide fuels. The choice of fuel can influence the reactor's waste output and proliferation resistance.

Advantages[edit | edit source]

LFRs offer several advantages over other reactor designs. The high boiling point of lead reduces the risk of coolant loss, and its high atomic number makes it an excellent shield against radiation. Lead is also abundant and relatively cheap, making it an economically viable choice for reactor coolant.

Furthermore, LFRs can operate at higher temperatures than traditional reactors, improving their thermal efficiency. They also have the potential for fuel breeding, which could significantly reduce the amount of nuclear waste produced.

Challenges[edit | edit source]

Despite their advantages, LFRs also face several challenges. The corrosive nature of lead can cause damage to reactor components, and the high melting point of lead can pose challenges for reactor startup and shutdown. Additionally, the use of fast neutrons can lead to increased production of transuranic elements, which are difficult to manage and dispose of.

Current Projects[edit | edit source]

Several countries, including Russia, China, and the United States, are currently researching and developing LFR technology. The European Sustainable Nuclear Industrial Initiative (ESNII) also includes LFR in its portfolio of advanced reactor designs.

See Also[edit | edit source]

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Contributors: Prab R. Tumpati, MD