FAST-SPECTRUM REACTORS
Gas-Cooled Fast Reactor (GFR)
The Gas-Cooled Fast Reactor (GFR) system features a fast-neutron spectrum and closed fuel cycle for efficient conversion of fertile uranium and management of actinides. A full actinide recycle fuel cycle with on-site fuel cycle facilities is envisioned. The reference reactor is a 600-MWth/288-MWe helium-cooled system operating with an outlet temperature of 850°C using a direct Brayton cycle gas turbine for high thermal efficiency. Several fuel forms are being considered for their potential to operate at very high temperatures and to ensure an excellent retention of fission products: composite ceramic fuel, advanced fuel particles, or ceramic clad elements of actinide compounds. Core configurations are being considered based on pin- or plate-based fuel assemblies or prismatic blocks. The GFR is primarily envisioned for missions in electricity production and actinide management, although it may be able to also support hydrogen production.
Lead-Cooled Fast Reactor (LFR)
The Lead-Cooled Fast Reactor (LFR) system features a fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides. A full actinide recycle fuel cycle with central or regional fuel cycle facilities is envisioned. The system uses a lead or lead/bismuth eutectic liquid-metal-cooled reactor. Options include a range of plant ratings, including a battery of 50-150 MWe that features a very long refueling interval, a modular system rated at 300-400 MWe, and a large monolithic plant option at 1200 MWe. The term battery refers to the long-life, factory-fabricated core and not to any provision for electrochemical energy conversion. The fuel is metal or nitride-based and would contain fertile uranium and transuranics.
The most advanced of these is the Pb/Bi battery, which employs a small size core with a very long (10-30) year core life. The reactor module is designed to be fabricated at a factory and then be transported to the plant site, rather than being manufactured at the plant site itself. The reactor is cooled by natural convection and sized between 120-400 MWth. The reactor has a nominal outlet temperature of 550°C with a possible upper limit of 800°C. The system is designed for distributed generation of electricity and other energy products, including hydrogen and potable water.
Sodium-Cooled Fast Reactor (SFR)
The Sodium-Cooled Fast Reactor (SFR) system features a fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides. A full actinide recycle fuel cycle is envisioned with two options. One option is an intermediate size (150 to 500 MWe) sodium-cooled reactor with a uranium-plutonium-minor actinide-zirconium metal alloy fuel, supported by a fuel cycle based on pyrometallurgical processing in collocated facilities. The second option is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel, supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors. The outlet temperature is approximately 550°C for both reactor options. The SFR system is primarily envisioned for missions in electricity production and actinide management.
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