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natural circulation boiling-water reactor

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  • Boiling water reactor — A boiling water reactor (BWR) is a type of nuclear reactor developed by the General Electric in the mid 1950s.Fact|date=April 2008 The BWR is characterized by two phase fluid flow (water and steam) in the upper part of the reactor core. See… …   Wikipedia

  • Economic Simplified Boiling Water Reactor — The reactor formally known as Economic Simplified Boiling Water Reactor (ESBWR) is a passively safe generation III+ reactor which builds on the success of the ABWR. Both are designs by General Electric, and are based on their BWR design.The ESBWR …   Wikipedia

  • Advanced Boiling Water Reactor — The Advanced Boiling Water Reactor (ABWR) is a Generation III reactor boiling water reactor. The ABWR was designed by General Electric. The standard ABWR plant design has a net output of about 1350 MWe, however General Electric Hitachi (GEH)has… …   Wikipedia

  • Supercritical water reactor — The Supercritical water reactor (SCWR) is a Generation IV reactor concept that uses supercritical water as the working fluid. SCWRs are basically LWRs operating at higher pressure and temperatures with a direct, once through cycle. As most… …   Wikipedia

  • Advanced Heavy Water Reactor — The Advanced Heavy Water Reactor (AHWR) is the latest Indian design for a next generation nuclear reactor that will burn Thorium in its fuel core. It is slated to form the third stage in India s 3 stage fuel cycle plan.… …   Wikipedia

  • nuclear reactor — Physics. reactor (def. 4). Also called nuclear pile. [1940 45] * * * Device that can initiate and control a self sustaining series of nuclear fission reactions. Neutrons released in one fission reaction may strike other heavy nuclei, causing them …   Universalium

  • Pebble bed reactor — Sketch of a pebble bed reactor in Italian …   Wikipedia

  • Nuclear reactor coolant — Nuclear reactor coolants Coolant Melting point Boiling point Light water at 155 bar 345 °C Mercury 38.83 °C 356.73 °C NaK eutectic 11 °C 785 °C Sodium 97.72 °C 883 °C …   Wikipedia

  • водо-водяной кипящий ядерный реактор с естественной циркуляцией — — [Я.Н.Лугинский, М.С.Фези Жилинская, Ю.С.Кабиров. Англо русский словарь по электротехнике и электроэнергетике, Москва, 1999 г.] Тематики электротехника, основные понятия EN natural circulation boiling water reactor …   Справочник технического переводчика

  • Chernobyl disaster — This article is about the 1986 nuclear plant accident in Ukraine. For other uses, see Chernobyl (disambiguation). Chernobyl disaster …   Wikipedia

  • Thermal power station — Republika Power Plant, a thermal power station in Pernik, Bulgaria …   Wikipedia

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