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  2. VVER - Wikipedia

    en.wikipedia.org/wiki/VVER

    The water-water energetic reactor (WWER), [1] or VVER (from Russian: водо-водяной энергетический реактор; transliterates as vodo-vodyanoi enyergeticheskiy reaktor; water-water power reactor) is a series of pressurized water reactor designs originally developed in the Soviet Union, and now Russia, by OKB Gidropress. [2]

  3. VVER-TOI - Wikipedia

    en.wikipedia.org/wiki/VVER-TOI

    The VVER-TOI reactor pressure vessel has fewer welds than the VVER-1200, all out of the central area, and a more symmetric arrangement of coolant nozzles. This gives the potential for two 20 year life extensions, which could give a 100 year life.

  4. Steam generator (nuclear power) - Wikipedia

    en.wikipedia.org/wiki/Steam_generator_(nuclear...

    This Babcock & Wilcox nuclear steam generator moved in a special train (restricted to 20 mph) via the Penn Central Railroad and Southern Railway from Barberton, Ohio to a Duke Energy site in Oconee, S.C. This generator weights 1,140,000 lbs and is a record shipment for the Railroad at that time (1970). A once-through steam generator A VVER ...

  5. Paks Nuclear Power Plant - Wikipedia

    en.wikipedia.org/wiki/Paks_Nuclear_Power_Plant

    VVER is the Soviet designation for a pressurized water reactor.The number following VVER, in this case 440, represents the power output of the original design. The VVER-440 Model V213 was a product of the first uniform safety requirements drawn up by the Soviet designers.

  6. Kudankulam Nuclear Power Plant - Wikipedia

    en.wikipedia.org/wiki/Kudankulam_Nuclear_Power_Plant

    The reactors are pressurised water reactor of Russian design, model VVER-1000/V-412 referred also as AES-92. Thermal capacity is 3,000 MW, gross electrical capacity is 1,000 MW with a net capacity of 917 MW. [ 29 ]

  7. Russian nuclear company reports attack on Zaporizhzhia plant

    www.aol.com/news/ukraine-strikes-zaporizhzhia...

    The nuclear plant has six Soviet-designed VVER-1000 V-320 water-cooled and water-moderated reactors containing Uranium 235, and also has spent nuclear fuel at the facility. ...

  8. Pressurized water reactor - Wikipedia

    en.wikipedia.org/wiki/Pressurized_water_reactor

    After picking up heat as it passes through the reactor core, the primary coolant transfers heat in a steam generator to water in a lower pressure secondary circuit, evaporating the secondary coolant to saturated steam — in most designs 6.2 MPa (60 atm, 900 psia), 275 °C (530 °F) — for use in the steam turbine. The cooled primary coolant ...

  9. Generation III reactor - Wikipedia

    en.wikipedia.org/wiki/Generation_III_reactor

    The VVER-1300/510 is based on the VVER-1200/392M that was originally used as the reference design for the VVER-TOI project, although the VVER-1300/510 now serves that role (which has led to confusion between the VVER-TOI plant design and the VVER-1300/510 reactor design). Multiple units are currently planned for construction at several Russian ...

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