- primary (coolant )flow
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расход (теплоносителя) в первом контуре
Англо-русский словарь технических терминов. 2005.
primary (coolant )flow
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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
расход теплоносителя в первом контуре ядерного реактора — — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN primary coolant flowprimary flow rate … 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
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
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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
Three Mile Island accident — The Three Mile Island accident of 1979 was the most significant accident in the history of the American commercial nuclear power generating industry. It resulted in the release of a significant amount of radioactivity, an estimated 43,000 curies… … Wikipedia
Integral Fast Reactor — The Integral Fast Reactor or Advanced Liquid Metal Reactor is a design for a nuclear fast reactor with a specialized nuclear fuel cycle. A prototype of the reactor was built in the United States, but the project was canceled by the U.S.… … Wikipedia
Steam generator (nuclear power) — This is an article about nuclear power plant equipment. For other uses, see steam generator. Steam generators are heat exchangers used to convert water into steam from heat produced in a nuclear reactor core. They are used in pressurized water… … Wikipedia
