- loss of coolant flow
- Техника: потеря потока теплоносителя
Универсальный англо-русский словарь. Академик.ру. 2011.
loss of 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
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Two-phase flow — In fluid mechanics, two phase flow occurs in a system containing gas and liquid with a meniscus separating the two phases. Historically, probably the most commonly studied cases of two phase flow are in large scale power systems. Coal and gas… … Wikipedia
Pebble bed reactor — Sketch of a pebble bed reactor in Italian … Wikipedia
Passive nuclear safety — describes a safety feature of a nuclear reactor that does not require operator action or electronic feedback in order to shut down safely in the event of a particular type of emergency (usually overheating resulting from a loss of coolant or loss … Wikipedia
Nuclear chain reaction — A possible nuclear fission chain reaction. 1. A uranium 235 atom absorbs a neutron, and fissions into two new atoms (fission fragments), releasing three new neutrons and a large amount of binding energy. 2. One of those neutrons is absorbed by an … Wikipedia
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
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
Chernobyl disaster — This article is about the 1986 nuclear plant accident in Ukraine. For other uses, see Chernobyl (disambiguation). Chernobyl disaster … Wikipedia
Void coefficient — In nuclear engineering, the void coefficient (more properly called void coefficient of reactivity ) is a number that can be used to estimate how much the reactivity of a nuclear reactor changes as voids (steam bubbles) form in the reactor… … 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
