primary coolant void

См. также в других словарях:

• Loss of coolant accident — A loss of coolant accident (LOCA) is a mode of failure for a nuclear reactor; if not managed effectively, the results of a LOCA could result in reactor core damage. Each nuclear plant s Emergency Core Cooling System (ECCS) exists specifically to… …   Wikipedia

• паросодержание теплоносителя первого контура ядерного реактора — — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN primary coolant void …   Справочник технического переводчика

• Nuclear meltdown — Three of the reactors at Fukushima I overheated, causing core meltdowns. This was compounded by hydrogen gas explosions and the venting of contaminated steam which released large amounts of radioactive material into the air.[1] …   Wikipedia

• Pressurized water reactor — (PWRs) (also VVER if of Russian design) are generation II nuclear power reactors that use ordinary water under high pressure (superheated water) as coolant and neutron moderator. The primary coolant loop is kept under high pressure to prevent the …   Wikipedia

• CANDU reactor — The CANDU reactor is a Canadian invented, pressurized heavy water reactor developed initially in the late 1950s and 1960s by a partnership between Atomic Energy of Canada Limited (AECL), the Hydro Electric Power Commission of Ontario (now known… …   Wikipedia

• VVER — The VVER (From (Russian: Водо водяной энергетический реактор , transliterates as Vodo Vodyanoi Energetichesky Reactor , translates as Water Water Energetic Reactor , WWER. Water water stands for coolant and moderator.) is a series of pressurised… …   Wikipedia

• Gas-cooled fast reactor — The Gas Cooled Fast Reactor (GFR) system is a nuclear reactor design which is currently in development. Classed as a Generation IV reactor, it features a fast neutron spectrum and closed fuel cycle for efficient conversion of fertile uranium and… …   Wikipedia

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

• 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

• Experimental Breeder Reactor II — There is also a separate, closed, unrelated facility called Experimental Breeder Reactor I .Experimental Breeder Reactor II (EBR II) is a reactor at the Materials and Fuels Complex of the Idaho National Laboratory, formerly the Argonne West… …   Wikipedia

• Nuclear reactor physics — See also: Critical mass Nuclear reactor physics is the branch of science that deals with the study and application of chain reaction to induce controlled rate of fission for energy in reactors. Most nuclear reactors use a chain reaction to induce …   Wikipedia