- loss of coolant
- Техника: потеря теплоносителя
Универсальный англо-русский словарь. Академик.ру. 2011.
loss of coolant
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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
Loss of pressure control accident — Most commercial types of nuclear reactor use a pressure vessel to maintain pressure in the reactor plant. This is necessary in a pressurized water reactor to prevent boiling in the core, which could lead to a nuclear meltdown. This is also… … Wikipedia
Coolant — A coolant is a fluid which flows through a device to prevent its overheating, transferring the heat produced by the device to other devices that use or dissipate it. An ideal coolant has high thermal capacity, low viscosity, is low cost, non… … Wikipedia
LOCA — Loss Of Coolant Accident (An incident involving the loss of primary coolant in a nuclear reactor) Contributor: CASI … NASA Acronyms
LOCA — Loss Of Coolant Accident (Academic & Science » Physics) * Laguna Outreach Community Arts (Community) … Abbreviations dictionary
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
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
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
