reactor recirculation system

См. также в других словарях:

• 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

• 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

• Advanced Boiling Water Reactor — The Advanced Boiling Water Reactor (ABWR) is a Generation III reactor boiling water reactor. The ABWR was designed by General Electric. The standard ABWR plant design has a net output of about 1350 MWe, however General Electric Hitachi (GEH)has… …   Wikipedia

• Gas core reactor rocket — Gas core reactor rockets are a conceptual type of rocket that is propelled by the exhausted coolant of a gaseous fission reactor. The nuclear fission reactor core may be either a gas or plasma. They may be capable of creating specific impulses of …   Wikipedia

• 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

• 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

• система рециркуляции теплоносителя ядерного реактора — — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN reactor recirculation systemRRS …   Справочник технического переводчика

• Nuclear power accidents by country — The abandoned city of Pripyat, Ukraine with the Chernobyl nuclear power plant in the distance. 57 accidents have occurred since the Chernobyl disaster in 1986. Two thirds of these mishaps occurred in the US.[1] The French Atomic Energy Agency… …   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

• Control rod — PWR control rod assembly, above fuel element A control rod is a rod made of chemical elements capable of absorbing many neutrons without fissioning themselves. They are used in nuclear reactors to control the rate of fission of uranium and… …   Wikipedia

• Heat pipe — A heat pipe is a heat transfer mechanism that can transport large quantities of heat with a very small difference in temperature between the hotter and colder interfaces. Inside a heat pipe, at the hot interface a fluid turns to vapour and the… …   Wikipedia