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  2. High-temperature gas-cooled reactor - Wikipedia

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

    The high operating temperatures of HTGR reactors potentially enable applications such as process heat or hydrogen production via the thermochemical sulfur–iodine cycle. A proposed development of the HGTR is the Generation IV very-high-temperature reactor (VHTR) which would initially work with temperatures of 750 to 950 °C.

  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. Pebble-bed reactor - Wikipedia

    en.wikipedia.org/wiki/Pebble-bed_reactor

    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 ...

  5. The power plant built in China’s Shandong province generates power from two high-temperature reactors that are cooled by ... It is cooled by helium and can reach high temperatures of up to 750 ...

  6. 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.

  7. Molten-salt reactor - Wikipedia

    en.wikipedia.org/wiki/Molten-salt_reactor

    The fluoride salt-cooled high-temperature reactor (FHR), also called advanced high temperature reactor (AHTR), [29] is also a proposed Generation IV molten-salt reactor variant regarded promising for the long-term future. [25] The FHR/AHTR reactor uses a solid-fuel system along with a molten fluoride salt as coolant.

  8. Generation IV reactor - Wikipedia

    en.wikipedia.org/wiki/Generation_IV_reactor

    The very-high-temperature reactor (VHTR) uses a graphite-moderated core with a once-through uranium fuel cycle, using helium or molten salt. This reactor design envisions an outlet temperature of 1,000 °C. The reactor core can be either a prismatic-block or a pebble bed reactor design.

  9. UHTREX - Wikipedia

    en.wikipedia.org/wiki/UHTREX

    The Ultra-High Temperature Reactor Experiment (UHTREX) was an experimental gas-cooled nuclear reactor run at Los Alamos National Laboratory between 1959 and 1971 [1] [2] as part of research into reducing the cost of nuclear power. [3]

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