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The use of a high-temperature, gas-cooled reactor for power production was proposed by in 1944 by Farrington Daniels, then associate director of the chemistry division at the University of Chicago's Metallurgical Laboratory. Initially, Daniels envisaged a reactor using beryllium moderator.
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 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.
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 pebbles.
The reactor in Shidao Bay, China is the world’s first gas-cooled nuclear power plant built for commercial demonstration. It is cooled by helium and can reach high temperatures of up to 750 ...
Advanced Gas-cooled Reactor (Magnox successor, 15 built, 1962-today) Heavy water gas cooled reactor (heavy water moderated, CO 2 cooled) Brennilis Nuclear Power Plant (1967-1985) KS 150 (1972-1979) Niederaichbach Nuclear Power Plant (1973-1974) High & Very-high temperature reactor (graphite moderated, Helium cooled) Prismatic block reactor ...
HTR-10 is a 10 MWt prototype high-temperature gas-cooled, pebble-bed reactor at Tsinghua University in China.Construction began in 1995, achieving its first criticality in December 2000, and was operated in full power condition in January 2003.
The plant has the first fourth-generation nuclear reactors in the world: [3] the HTR-PM, a high-temperature gas-cooled reactor (HTGR) concept (). The plant will ultimately have ten 210 MW e (megawatts electrical) units of this type.
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