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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 high-temperature engineering test reactor (HTTR) is a graphite-moderated gas-cooled research reactor in Ōarai, Ibaraki, Japan operated by the Japan Atomic Energy Agency. It uses long hexagonal fuel assemblies, unlike the competing pebble bed reactor designs. HTTR first reached its full design power of 30 MW (thermal) in 1999.
HTR-10: Beijing: High Temp Gas Operational 10,000 2000-12-21 MJTR Chengdu: Pool Operational 5,000 1991-03-02 ESR-901 Beijing: Pool-2 Cores Operational 1,000 1964-10-01 NHR-5 Beijing: Heating Prot Operational 5,000 1989-11-03 SPRR-300 Chengdu: Pool Operational 3,000 1979-06-28 HFETR Critical Chengdu: Crit Assembly Operational 0.00 1979-06-20 PPR ...
In 2005, China announced its intention to scale up the HTR-10 experimental reactor for commercial power generation. The first two 250-MWt High-Temperature Reactor-Pebble-bed Modules (HTR-PM) will be installed at Shidao Bay, and together drive a steam turbine generating 200 MWe.
The reactor is proprietary molten salt reactor design that builds on two existing designs: the Denatured Molten Salt Reactor (DMSR) and Small Modular Advanced High Temperature Reactor (smAHRT). Both designs are from Oak Ridge National Laboratory. The key technology of the IMSR® is the integration of the primary reactor components, the ...
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.
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.
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 ...
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