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nuclear reactor reactivity protection system

См. также в других словарях:

  • 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

  • Nuclear reactor — Core of CROCUS, a small nuclear reactor used for research at the EPFL in Switzerland This article is a subarticle of Nuclear power. A nuclear reactor is a device to initiate and control a sustained nuclear chain reaction. Most commonly they are… …   Wikipedia

  • Nuclear reactor technology — This article is a subarticle of Nuclear power .A nuclear reactor is a device in which nuclear chain reactions are initiated, controlled, and sustained at a steady rate, as opposed to a nuclear bomb, in which the chain reaction occurs in a… …   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

  • 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

  • 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

  • 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

  • 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

  • ГОСТ 17137-87: Системы контроля, управления и защиты ядерных реакторов. Термины и определения — Терминология ГОСТ 17137 87: Системы контроля, управления и защиты ядерных реакторов. Термины и определения оригинал документа: 25. Аварийная защита ядерного реактора AЗ D. Schnellschlusssystem Е. Protection system Функция системы управления и… …   Словарь-справочник терминов нормативно-технической документации

  • Аварийная защита — 1. Аварийная защита функция безопасности, состоящая в быстром переводе активной зоны реактора в подкритическое состояние и поддержании ее в подкритическом состоянии; комплекс систем безопасности, выполняющий функцию АЗ. Источник: ПНАЭ Г 1 024 90 …   Словарь-справочник терминов нормативно-технической документации

  • аварийная защита ядерного реактора по реактивности — АЗС [ГОСТ 17137 87] Тематики системы контроля, управл. и защиты ядерных реакторов Синонимы АЗС EN nuclear reactor reactivity protection system DE Reaktivitätsschnellschlusssystem …   Справочник технического переводчика

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