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The majority of reactors in operation around the world are considered second generation and third generation reactor systems, as the majority of the first generation systems have been retired. China was the first country to operate a demonstration generation-IV reactor, the HTR-PM in Shidaowan, Shandong , [ 7 ] [ 8 ] which is a pebble-bed type ...
The Lead-cooled Fast Reactor (LFR) system features a fast-spectrum lead or lead/bismuth eutectic liquid metal-cooled reactor and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides. From the Generation IV International Forum lead-cooled fast reactor website. Diagram from NEA. Recovered from web.archive.org
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.
Pool type sodium-cooled fast reactor (SFR) 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 fluoride salt-cooled high-temperature reactor (FHR), also called advanced high temperature reactor (AHTR), [29] is also a proposed Generation IV molten-salt reactor variant regarded promising for the long-term future. [25] The FHR/AHTR reactor uses a solid-fuel system along with a molten fluoride salt as coolant.
Sketch of a pebble-bed reactor. The pebble-bed reactor (PBR) is a design for a graphite-moderated, gas-cooled nuclear reactor. It is a type of very-high-temperature reactor (VHTR), one of the six classes of nuclear reactors in the Generation IV initiative. Graphite pebble for reactor. The basic design features spherical fuel elements called ...
The SCWR operates at supercritical pressure. The reactor outlet coolant is supercritical water.Light water is used as a neutron moderator and coolant. Above the critical point, steam and liquid become the same density and are indistinguishable, eliminating the need for pressurizers and steam generators (), or jet/recirculation pumps, steam separators and dryers ().
Schematic diagram of a CANDU reactor: ... These generation III+ and generation IV machines became a ... the CANDU is "the Ontario reactor". The system was developed ...