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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 reactor is a sodium-cooled fast reactor, which uses liquid sodium as the coolant. [4] It uses two separate sodium loops, and these are connected to a main water-cooled loop which feeds the steam generators and turbines for producing electricity. [7] The sodium coolant is pressurized to 5.5 MPa, and is heated to over 500 °C in the reactor. [6]
Gas-cooled fast reactor scheme. The gas-cooled fast reactor (GFR) system is a nuclear reactor design which is currently in development.Classed as a Generation IV reactor, it features a fast-neutron spectrum and closed fuel cycle for efficient conversion of fertile uranium and management of actinides.
The mere fact that an assembly is supercritical does not guarantee that it contains any free neutrons at all. At least one neutron is required to "strike" a chain reaction, and if the spontaneous fission rate is sufficiently low it may take a long time (in 235 U reactors, as long as many minutes) before a chance neutron encounter starts a chain reaction even if the reactor is supercritical.
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 Argonne Fast Source Reactor was a tool used to calibrate instruments and to study fast reactor physics, augmenting the Zero Power Plutonium Reactor (ZPPR) research program. Located at Argonne-West, this low-power reactor—designed to operate at a power of only one kilowatt—contributed to an improvement in the techniques and instruments ...
(fast utilization) is the probability that a fast neutron is absorbed in fuel. P F A F {\displaystyle P_{FAF}} is the probability that a fast neutron absorption in fuel causes fission. P T A F {\displaystyle P_{TAF}} is the probability that a thermal neutron absorption in fuel causes fission.
Lead cooled fast reactor scheme. The lead-cooled fast reactor is a nuclear reactor design that uses molten lead or lead-bismuth eutectic coolant.These materials can be used as the primary coolant because they have low neutron absorption and relatively low melting points.