Search results
Results from the WOW.Com Content Network
A layer of silicon carbide gives coated fuel particles structural support and is the main diffusion barrier to the release of fission products. [80] Silicon carbide composite material has been investigated for use as a replacement for Zircaloy cladding in light water reactors. One of the reasons for this investigation is that, Zircaloy ...
The rods may have the form of tubes filled with neutron-absorbing pellets or powder. The tubes can be made of stainless steel or other "neutron window" materials such as zirconium, chromium, silicon carbide, or cubic 11 B 15 N (cubic boron nitride). [3] The burnup of "burnable poison" isotopes also limits lifespan of a control rod. They may be ...
The reactor uses a composite of silicon carbide as a fuel cladding material and zirconium silicide as neutron reflector material. The reactor unit is coupled to direct-drive helium closed-cycle gas turbine which drives a generator to produce electricity.
Cladding is the outer layer of the fuel rods, standing between the coolant and the nuclear fuel. It is made of a corrosion-resistant material with low absorption cross section for thermal neutrons, usually Zircaloy or steel in modern constructions, or magnesium with small amount of aluminium and other metals for the now-obsolete Magnox reactors ...
The use of SiC/SiC CMCs on rotating engine components reduce the complexity of design and engine structure weight, providing improved performance and fuel emissions. The implementation of SiC/SiC ceramic matrix components will improve aircraft and space vehicle performance and fuel efficiency, reducing additional harm to the environment in a ...
The Chernobyl corium is composed of the reactor uranium dioxide fuel, its zircaloy cladding, molten concrete, as well as other materials in and below the reactor, and decomposed and molten serpentinite packed around the reactor as its thermal insulation. Analysis has shown that the corium was heated to at most 2,255 °C (4,091 °F), and ...
A gas-cooled reactor (GCR) is a nuclear reactor that uses graphite as a neutron moderator and a gas (carbon dioxide or helium in extant designs) as coolant. [1] Although there are many other types of reactor cooled by gas, the terms GCR and to a lesser extent gas cooled reactor are particularly used to refer to this type of reactor.
A high-temperature gas-cooled reactor (HTGR) is a type of gas-cooled nuclear reactor which uses uranium fuel and graphite moderation to produce very high reactor core output temperatures. [1] All existing HTGR reactors use helium coolant.