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HTR-10 is a pebble-bed high-temperature gas reactor utilizing spherical fuel elements with ceramic coated fuel particles. The reactor core has a diameter of 1.8 metres (5 ft 11 in), a mean height of 1.97 metres (6 ft 6 in) and the volume of 5.0 cubic metres (180 cu ft), and is surrounded by graphite reflectors .
The 10 megawatt prototype is called the HTR-10. It is a conventional helium-cooled, helium-turbine design. In 2021 the Chinese then built a 211 MW e gross unit HTR-PM, which incorporates two 250 MW t reactors. [21] As of 2021, four sites were being considered for a 6-reactor successor, the HTR-PM600. [21]
According to the patent application [5] the reactor design has some notable characteristics, that sets it apart from other reactor designs. It uses uranium hydride (UH 3) "low-enriched" to 5% uranium-235—the remainder is uranium-238—as the nuclear fuel, rather than the usual metallic uranium or uranium dioxide that composes the fuel rods of contemporary light-water reactors.
The HTR-PM is a high-temperature gas-cooled (HTGR) pebble-bed reactor. While the German AVR and THTR-300, operating from 1969 to 1988, were the first pebble-bed reactors and operated at similar temperatures, the HTR-PM is the first such design using modular construction and the second small modular reactor, following Russia's Akademik Lomonosov floating plant in 2019.
The HTR-PM is a high-temperature gas-cooled (HTGR) pebble-bed generation IV reactor partly based on the earlier HTR-10 prototype reactor. [70] The reactor unit has a thermal capacity of 250 MW, and two reactors are connected to a single steam turbine to generate 210 MW of electricity. [70]
A high-temperature gas-cooled reactor (HTGR) is a type of gas-cooled nuclear reactor which uses uranium fuel and graphite moderation to produce very high reactor core output temperatures. [1] All existing HTGR reactors use helium coolant. The reactor core can be either a "prismatic block" (reminiscent of a conventional reactor core) or a ...
The Generation IV International Forum (GIF) is an international organization with its stated goal being "the development of concepts for one or more Generation IV systems that can be licensed, constructed, and operated in a manner that will provide a competitively priced and reliable supply of energy ... while satisfactorily addressing nuclear safety, waste, proliferation and public perception ...
Control room of HTR-10 reactor at Tshinghua University. China is developing several generation IV reactor designs. The HTR-PM, a HTGR, is under construction. The HTR-PM is a descendant of the AVR reactor, and it is partly based on the earlier Chinese HTR-10 reactor. A sodium-cooled fast reactor, the CFR-600, is also under construction.