The lead-cooled fast reactor is a nuclear power Generation IV reactor that features a fast neutron spectrum, molten lead or lead-bismuth eutectic coolant. Options include a range of plant ratings, including a number of 50 to 150 MWe (megawatts electric) units featuring long-life, pre-manufactured cores. Plans include modular arrangements rated at 300 to 400 MW, and a large monolithic plant rated at 1,200 MW. The fuel is metal or nitride-based containing fertile uranium and transuranics. The LFR is cooled by natural convection with a reactor outlet coolant temperature of 550 °C, possibly ranging over 800 °C with advanced materials. Temperatures higher than 830 °C are high enough to support thermochemical production of hydrogen.
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The LFR battery is a small turnkey-type power plant using cassette cores running on a closed fuel cycle with 15 to 20 years' refuelling interval, or entirely replaceable reactor modules. It is designed for generation of electricity on small grids (and other resources, including hydrogen and potable water).
Two types of LFR reactor were used in Soviet Alfa class submarines of the 1970s. The OK-550 and BM-40A designs were both capable of producing 155MWt. They were significantly lighter than typical water-cooled reactors and had an advantage of being capable to quickly switch between maximum power and minimum noise operation modes.
A joint venture called AKME Engineering was announced on 25 December 2009 between Rosatom and En+ Group, to develop a commercial lead-bismuth reactor.[1] The SVBR-100 ('Svintsovo-Vismutovyi Bystryi Reaktor' - lead-bismuth fast reactor) is based on the Alfa designs and will produce 100MWe electricity from gross thermal power of 280MWt,[1] about twice that of the submarine reactors. They can also be used in groups of up to 16 if more power is required.[1] The coolant increases from 345 °C (653 °F) to 495 °C (923 °F) as it goes through the core.[1] Uranium oxide enriched to 16.5% U-235 could be used as fuel, and refuelling would be required every 7–8 years.[1] A prototype is planned for 2019.
According to Nuclear Engineering International, the initial design of the Hyperion Power Module will be of this type, using uranium nitride fuel encased in HT-9 tubes, using a quartz reflector, and lead-bismuth eutectic as coolant.[2]
The MYRRHA reactor is a subcritical reactor that is cooled by lead-bismuth eutectic. It is powered by an external neutronsource (a particle accelerator), which means that it can be stopped fast and completely, if so needed. It is also capable of decreasing the toxicity of the waste by a factor 1000, and decrease the volume of the waste by a factor 100 (compared to the nuclear power plants that are currently in operation). The design of the nuclear reactor will be completed by 2014. The project was started by SCK•CEN (Studiecentrum voor Kernenergie, Centre d'Etude de l'Energie Nucleaire).[3]
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