- reactor severe accident
- Атомная энергия: тяжелая авария в реакторе
Универсальный англо-русский словарь. Академик.ру. 2011.
reactor severe accident
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nuclear reactor — Physics. reactor (def. 4). Also called nuclear pile. [1940 45] * * * Device that can initiate and control a self sustaining series of nuclear fission reactions. Neutrons released in one fission reaction may strike other heavy nuclei, causing them … Universalium
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
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
Economic Simplified Boiling Water Reactor — The reactor formally known as Economic Simplified Boiling Water Reactor (ESBWR) is a passively safe generation III+ reactor which builds on the success of the ABWR. Both are designs by General Electric, and are based on their BWR design.The ESBWR … Wikipedia
Nuclear reactor accidents in the United States — According to a 2010 survey of energy accidents, there have been at least 56 accidents near nuclear reactors in the United States (defined as incidents that either resulted in the loss of human life or more than US$50,000 of property damage). The… … 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
Criticality accident — … 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
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
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
Liquid metal cooled reactor — A Liquid metal cooled nuclear reactor, liquid metal fast reactor or LMFR is an advanced type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first adapted for nuclear submarine use but have also… … Wikipedia
