| Gas Cooled Fast Reactor |
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The Gas-Cooled Fast Reactor (GFR) system is a 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. NUCLEAR REACTOR DESIGN The GFR base design is a Fast Reactor but in other ways similar to a high temperature gas-cooled reactor ( HTGR ). It differs from the HTGR design in that the core has a higher fissile fuel content as well as a non-fissile, fertile, breeding component, and of course there is no Neutron Moderator . Due to the higher fissile fuel content, the design has a higher power density than the HTGR. RESEARCH HISTORY Past pilot and demonstration projects have all used thermal designs with graphite moderators. These projects include decommissioned reactors such as the Dragon Project , built and operated in the United Kingdom , the AVR and the THTR-300 , built and operated in Germany , and Peach Bottom and Fort St Vrain , built and operated in the United States . Ongoing demonstrations include the HTTR in Japan , which reached full power (30 MWth) using fuel compacts in 1999 , and the HTR-10 in China , which may reach 10 MWth in 2002 using pebble fuel. A 300 MWth pebble bed modular demonstration plant is being designed by PBMR Pty for deployment in South Africa , and a consortium of Russian institutes is designing a 300 MWth GT-MHR in cooperation with General Atomics . The main challenges that have yet to be overcome are in-vessel structural materials, both in-core and out-of-core, that will have to withstand fast-neutron damage and high temperatures, (up to 1600°C) and low thermal inertia and poor heat removal capability at low helium pressures. SEE ALSO REFERENCES # THE GAS-COOLED FAST REACTOR SYSTEM # Flexibility of the Gas Cooled Fast Reactor to Meet the Requirements of the 21st Century # INL GFR summary # Generation IV International Forum GFR website EXTERNAL LINKS |
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