Search results
Results from the WOW.Com Content Network
Like the HTR-MODUL, HTR-10 is claimed to be fundamentally safer, [2] potentially cheaper and more efficient than other nuclear reactor designs. [3] Outlet temperature ranges between 700 and 750 °C (1,300–1,375 °F). [4] [5] HTR-10 is a pebble-bed high-temperature gas reactor utilizing spherical fuel elements with ceramic coated fuel particles.
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]
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.
Reactor two achieved first criticality in November 2021. [14] Reactor one was connected to the state power grid and began producing power in December 2021 [15] The HTR-PM project demonstrated it had reached "initial full power" in December 2022. [16] The HTR-PM project finally entered commercial operation in December 2023. [17]
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 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]
VVR-K – 10 MWe reactor [citation needed] RA Kurchatov: Tank Permanent Shutdown 500 1987-01-01 National Nuclear Center, Semipalatinsk Test Site: zirconium hydride moderated reactor (dismantled) IVG.1M Kurchatov: Pwr Operational 35,000 1972-09-19 National Nuclear Center, Semipalatinsk Test Site: WWR-K CF Almaty: Crit Assembly Operational 0.10 ...