Nuclear fuel cycle
Nuclear - Japan
Seism in Japan
nuclear reactor types - Search results
A simple light water reactor The light water reactor (LWR) is a type of thermal reactor that uses normal water, as opposed to heavy water, as its coolant and neutron moderator and a solid compound of fissile element as its fuel. Thermal reactors are the most common type of nuclear reactor, and light water reactors are the most common type of thermal reactor. Light water reactor - Wiki
AP1000 Nuclear Reactor
The control room of NC State's Pulstar Nuclear Reactor. Pool-type reactors, also called swimming pool reactors, are a type of nuclear reactor that has a core (consisting of the fuel elements and the control rods) immersed in an open pool of water. The water acts as neutron moderator, cooling agent and radiation shield. The layer of water directly above the reactor core shields the radiation so completely that operators may work above the reactor safely. This design has two major advantages: the reactor is easily accessible and the whole primary cooling system, i.e. the pool water, is under normal pressure. This avoids the high temperatures and great pressures of nuclear power plants. Pool-Type Reactor - Wiki
Boiling water reactor The boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. It is the second most common type of electricity-generating nuclear reactor after the pressurized water reactor (PWR), also a type of light water nuclear reactor. The main difference between a BWR and PWR is that in a BWR, the reactor core heats water, which turns to steam and then drives a steam turbine. In a PWR, the reactor core heats water, which does not boil.
List of nuclear reactors - Wiki This List of nuclear reactors is an annotated list of all the nuclear reactors in the world, sorted by country, with operational status. The list includes military, commercial and research reactors, excludes nuclear marine propulsion reactors, except those at land installations, and excludes uncompleted nuclear reactors. Algeria Es Salam (The Peace), 15 MW reactor for research, located in Aïn Oussera, in service since 1993Nur, research reactor built by Argentine INVAP Antarctica
Advanced gas-cooled reactor - Wiki An advanced gas-cooled reactor (AGR) is a type of nuclear reactor. These are the second generation of British gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as coolant. The AGR was developed from the Magnox reactor, operating at a higher gas temperature for improved thermal efficiency, requiring stainless steel fuel cladding to withstand the higher temperature. Because the stainless steel fuel cladding has a higher neutron capture cross section than Magnox fuel cans, enriched uranium fuel is needed, with the benefit of higher "burn ups" of 18,000 MWt-days per tonne of fuel, requiring less frequent refuelling.
Sodium - Wiki Sodium is a chemical element with the symbol Na (from Latin: natrium) and atomic number 11. It is a soft, silver-white, highly reactive metal and is a member of the alkali metals; its only stable isotope is 23Na. The free metal does not occur in nature, but instead must be prepared from its compounds; it was first isolated by Humphry Davy in 1807 by the electrolysis of sodium hydroxide. Sodium is the sixth most abundant element in the Earth's crust, and exists in numerous minerals such as feldspars, sodalite and rock salt (NaCl).
Shevchenko BN350 nuclear fast reactor and desalination plant situated on the shore of the Caspian Sea. The plant generated 135 MWe and provided steam for an associated desalination plant. View of the interior of the reactor hall. A fast neutron reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons. Such a reactor needs no neutron moderator, but must use fuel that is relatively rich in fissile material when compared to that required for a thermal reactor. Advantages Fast-neutron reactor - Wiki
The CANDU (short for CANada Deuterium Uranium) reactor is a Canadian-invented, pressurized heavy water reactor. The acronym refers to its deuterium-oxide (heavy water) moderator and its use of (originally, natural) uranium fuel. CANDU reactors were first developed in the late 1950s and 1960s by a partnership between Atomic Energy of Canada Limited (AECL), the Hydro-Electric Power Commission of Ontario (now Ontario Power Generation), Canadian General Electric (now GE Canada), and other companies. CANDU Reactor - Wiki
introduction to nuclear engineering
videos for education of nuclear engineering
Nuclear engineering Nuclear engineering is the branch of engineering concerned with the application of the breakdown (fission) as well as the fusion of atomic nuclei and/or the application of other sub-atomic physics, based on the principles of nuclear physics. In the sub-field of nuclear fission, it particularly includes the interaction and maintenance of systems and components like nuclear reactors, nuclear power plants, and/or nuclear weapons. The field also includes the study of medical and other applications of (generally ionizing) radiation, nuclear safety, heat/thermodynamics transport, nuclear fuel and/or other related technology (e.g., radioactive waste disposal), and the problems of nuclear proliferation. Professional areas Smaller elements and other particles including neutrons.
Nuclear Energy vs. Global Warming
The Generation IV International Forum (GIF) is a cooperative international endeavor organized to carry out the research and development (R&D) needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems. The Generation IV International Forum has thirteen Members which are signatories of its founding document, the GIF Charter. Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, the United Kingdom and the United States signed the GIF Charter in July 2001. The Generation IV International Forum