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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]
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.
English: A schematic of the two types of liquid metal fast breeder reactor (LMFBR), a fast neutron reactor designed to breed fuel by producing more fissile material than it consumes. FBRs are used in nuclear power plants to produce nuclear power from nuclear fuel .
Download as PDF; Printable version; In other projects ... Pages in category "Fast-neutron reactors" The following 9 pages are in this category, out of 9 total.
1943 Reactor diagram using boron control rods. Control rods are inserted into the core of a nuclear reactor and adjusted in order to control the rate of the nuclear chain reaction and, thereby, the thermal power output of the reactor, the rate of steam production, and the electrical power output of the power station.
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. Clementine was located at Los Alamos National Laboratory in Los Alamos, New ...
The Fast Flux Test Facility with labels Commemorative photo marking the completion of the FFTF system. The Fast Flux Test Facility (FFTF) is a 400 MW thermal, liquid sodium cooled, nuclear test reactor owned by the U.S. Department of Energy. It does not generate electricity.
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 reference reactor design is a helium - cooled system operating with an outlet temperature of 850 °C (1,560 °F) using a direct Brayton closed-cycle gas turbine for high ...