primary coolant loss accident

См. также в других словарях:

• 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

• 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

• 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

• 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

• авария с потерей теплоносителя первого контура ядерного реактора — — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN primary coolant loss accidentPCLA …   Справочник технического переводчика

• LOCA — Loss Of Coolant Accident (An incident involving the loss of primary coolant in a nuclear reactor) Contributor: CASI …   NASA Acronyms

• 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

• Pebble bed reactor — Sketch of a pebble bed reactor in Italian …   Wikipedia

• VVER — The VVER (From (Russian: Водо водяной энергетический реактор , transliterates as Vodo Vodyanoi Energetichesky Reactor , translates as Water Water Energetic Reactor , WWER. Water water stands for coolant and moderator.) is a series of pressurised… …   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

• List of military nuclear accidents — This article lists notable military accidents involving nuclear material. Civilian accidents are listed at List of civilian nuclear accidents. For a general discussion of both civilian and military accidents, see nuclear and radiation accidents.… …   Wikipedia