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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 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.
It is a high-temperature gas-cooled (HTGR) pebble-bed generation IV reactor evolved from the HTR-10 prototype. The technology is intended to replace coal-fired power plants in China's interior, in line with the country's plan to reach carbon neutrality by 2060. [1] The first plant has an electrical output of 210 MW.
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 GFR base design is a fast reactor, but in other ways similar to a high temperature gas-cooled reactor. It differs from the HTGR design in that the core has a higher fissile fuel content as well as a non-fissile, fertile, breeding component. There is no neutron moderator, as the chain reaction is sustained by fast neutrons. Due to the higher ...
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]
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