small loss-of-coolant accident
1Loss 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… …
2Three 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… …
3Behavior 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… …
4авария ядерного реактора с малой течью — авария ядерного реактора при разрыве трубопровода малого диаметра — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом Синонимы авария ядерного реактора при разрыве трубопровода малого диаметра EN… …
5Nuclear 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] …
6Nuclear and radiation accidents — This article is about nuclear and radiation accidents in general. For a list of military nuclear accidents, see List of military nuclear accidents. For a list of civilian nuclear accidents, see List of civilian nuclear accidents. For a discussion …
7Nuclear safety in the United States — Nuclear safety in the U.S. is governed by federal regulations and continues to be studied by the Nuclear Regulatory Commission (NRC). The safety of nuclear plants and materials controlled by the U.S. government for research and weapons production …
8Nuclear safety — covers the actions taken to prevent nuclear and radiation accidents or to limit their consequences. This covers nuclear power plants as well as all other nuclear facilities, the transportation of nuclear materials, and the use and storage of… …
9Void 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… …
10Nuclear 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… …
