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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.
A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor .
The type of coolants, temperatures, and fast neutron spectrum puts the fuel cladding material (normally austenitic stainless or ferritic-martensitic steels) under extreme conditions. The understanding of the radiation damage, coolant interactions, stresses, and temperatures are necessary for the safe operation of any reactor core.
In a fast-neutron reactor, the minor actinides produced by neutron capture of uranium and plutonium can be used as fuel. Metal actinide fuel is typically an alloy of zirconium, uranium, plutonium, and minor actinides. It can be made inherently safe as thermal expansion of the metal alloy will increase neutron leakage.
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.
Clementine was the code name for the world's first continuous [note 1] fast-neutron reactor, also known as the Los Alamos fast plutonium reactor. It was an experimental-scale reactor. The maximum output was 25 kW and was fueled by plutonium and cooled by liquid mercury.
Fast reactors of the BN series use a core running on enriched fuels including highly (80%) or medium (20%) enriched uranium or plutonium. This design produces many neutrons that escape the core area. These neutrons create additional reactions in a "blanket" of material, normally natural or depleted uranium or thorium, where new plutonium- or 233
For example, EBR-II used metallic fuel, which is the major factor in its inherent safety, while BN-800 uses oxide fuel. The design of this plant was started in 1983 and was completely revised in 1987 after the Chernobyl disaster and to a somewhat lesser degree in 1993, according to the new safety guidelines.