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Русско-английский научно-технический словарь переводчика > внешний мир
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2 внешний мир
Русско-английский научно-технический словарь переводчика > внешний мир
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Heat pipe — A heat pipe is a heat transfer mechanism that can transport large quantities of heat with a very small difference in temperature between the hotter and colder interfaces. Inside a heat pipe, at the hot interface a fluid turns to vapour and the… … Wikipedia
Molten-Salt Reactor Experiment — MSRE plant diagram The Molten Salt Reactor Experiment (MSRE) was an experimental molten salt reactor at the Oak Ridge National Laboratory (ORNL) researching this technology through the 1960s; constructed by 1964, it went critical in 1965 and was… … Wikipedia
Fast breeder reactor — The fast breeder or fast breeder reactor (FBR) is a fast neutron reactor designed to breed fuel by producing more fissile material than it consumes. The FBR is one possible type of breeder reactor. The reactors are used in nuclear power plants to … 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
Breeder reactor — Assembly of the core of Experimental Breeder Reactor I in Idaho, 1951 A breeder reactor is a nuclear reactor that generates more fissile material in fuel than it consumes.[1] These reactors are considered appealing due to their superior fuel… … 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
Corium (nuclear reactor) — LFCM redirects here. For the airport, see List of airports by ICAO code: L. The Three Mile Island reactor 2 after the meltdown. Corium, also called fuel containing material (FCM) or lava like fuel containing material (LFCM), is a lava like molten … Wikipedia
Behavior of nuclear fuel during a reactor accident — This page is devoted to a discussion of how uranium dioxide nuclear fuel behaves during both normal nuclear reactor operation and under reactor accident conditions such as overheating. Work in this area is often very expensive to conduct, and so… … Wikipedia
Nuclear fuel response to reactor accidents — This page is devoted to a discussion of how uranium dioxide nuclear fuel behaves during both normal nuclear reactor operation and under reactor accident conditions such as overheating. Work in this area is often very expensive to conduct, and so… … 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
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