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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 ...
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 ...
For a typical late 20th-century power station, superheated steam from the boiler is delivered through 14–16-inch-diameter (360–410 mm) piping at 2,400 psi (17 MPa; 160 atm) and 1,000 °F (540 °C) to the high-pressure turbine, where it falls in pressure to 600 psi (4.1 MPa; 41 atm) and to 600 °F (320 °C) in temperature through the stage.
The power plant built in China’s Shandong province generates power from two high-temperature reactors that are cooled by gas rather than water, state news agency Xinhua reported on Wednesday.
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.
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.
Farhang-e-Asifiya (Urdu: فرہنگ آصفیہ, lit. 'The Dictionary of Asif') is an Urdu-to-Urdu dictionary compiled by Syed Ahmad Dehlvi. [1] It has more than 60,000 entries in four volumes. [2] It was first published in January 1901 by Rifah-e-Aam Press in Lahore, present-day Pakistan. [3] [4]