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  2. High-temperature gas-cooled reactor - Wikipedia

    en.wikipedia.org/wiki/High-temperature_gas...

    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.

  3. HTR-PM - Wikipedia

    en.wikipedia.org/wiki/HTR-PM

    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.

  4. Gas-cooled reactor - Wikipedia

    en.wikipedia.org/wiki/Gas-cooled_reactor

    A gas-cooled reactor (GCR) is a nuclear reactor that uses graphite as a neutron moderator and a gas (carbon dioxide or helium in extant designs) as coolant. [1] Although there are many other types of reactor cooled by gas, the terms GCR and to a lesser extent gas cooled reactor are particularly used to refer to this type of reactor.

  5. 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 ...

  6. Pebble-bed reactor - Wikipedia

    en.wikipedia.org/wiki/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 pebbles.

  7. High-temperature engineering test reactor - Wikipedia

    en.wikipedia.org/wiki/High-temperature...

    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.

  8. List of small modular reactor designs - Wikipedia

    en.wikipedia.org/wiki/List_of_small_modular...

    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]

  9. HTR-10 - Wikipedia

    en.wikipedia.org/wiki/HTR-10

    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 .