Search results
Results from the WOW.Com Content Network
The integral fast reactor (IFR), originally the advanced liquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron moderator (a "fast" reactor). IFRs can breed more fuel and are distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.
The concept can be applied to any sort of underlying reactor design, there are examples of integral pressurized water reactors, sodium-cooled fast reactors, and others. The main goals are mass production of the reactor, as the entire working design can be delivered as a single unit and then connected to the non-nuclear generation sections of ...
The first fast reactor built and operated was the Los Alamos Plutonium Fast Reactor ("Clementine") in Los Alamos, NM. [14] Clementine was fueled by Ga-stabilized delta-phase Pu and cooled with mercury. It contained a 'window' of Th-232 in anticipation of breeding experiments, but no reports were made available regarding this feature.
Types of nuclear reactors Advanced gas-cooled reactor; Boiling water reactor; Fast breeder reactor; Fast neutron reactor; Gas-cooled fast reactor; Generation IV reactor; Integral Fast Reactor; Lead-cooled fast reactor; Liquid-metal-cooled reactor; Magnox reactor; Molten salt reactor; Pebble bed reactor; Pressurized water reactor; Sodium-cooled ...
The integral fast reactor was developed at the West Campus of the Argonne National Laboratory in Idaho Falls, Idaho and was an extension (inc fuel reprocessing) to the Experimental Breeder Reactor II, which achieved first criticality in 1965 and ran for 30 years. The Integral Fast Reactor project (and EBR II) was shut down by the U.S. Congress ...
The BN-350 fast-neutron reactor at Aktau, Kazakhstan.It operated between 1973 and 1994. A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons (carrying energies above 1 MeV, on average), as opposed to slow thermal neutrons used in thermal-neutron reactors.
The PFBR was to be followed by six more Commercial Fast Breeder Reactors (CFBRs) of 600 MW e each. The Gen IV SFR [27] is a project that builds on the oxide fueled fast breeder reactor and the metal fueled integral fast reactor. Its goals are to increase the efficiency of uranium usage by breeding plutonium and eliminating transuranic isotopes.
A fast reactor uses no moderator but relies on fission produced by unmoderated fast neutrons to sustain the chain reaction. In some fast reactor designs, up to 20% of fissions can come from direct fast neutron fission of uranium-238, an isotope which is not fissile at all with thermal neutrons.