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English: Nuclear reactor: pressurized water type. Water is heated through the splitting of uranium atoms in the reactor core. The water, held under high pressure to keep it from boiling, produces steam by transferring heat to a secondary source of water. The steam is used to generate electricity.
English: Diagram of the reactor core of the BOR-60 experimental fast-neutron reactor. Gray: fuel elements White: blanket assemblies Blue: experimental material testing assemblies Green: experimental fuel testing assemblies Red: control rods. Yellow: experimentation channels
See the Soviet-made RBMK nuclear-power reactor. This was the type of reactor involved in the Chernobyl disaster. In the Advanced Gas-cooled Reactor, a British design, the core is made of a graphite neutron moderator where the fuel assemblies are located. Carbon dioxide gas acts as a coolant and it circulates through the core, removing heat.
The light-water reactor produces heat by controlled nuclear fission. The nuclear reactor core is the portion of a nuclear reactor where the nuclear reactions take place. It mainly consists of nuclear fuel and control elements. The pencil-thin nuclear fuel rods, each about 12 feet (3.7 m) long, are grouped by the hundreds in bundles called fuel ...
- A pressurised heavy water reactor is a nuclear power reactor that uses unenriched natural uranium as nuclear fuel and heavy water as moderator and as primary coolant. The heavy water is kept under pressure in order to raise its boiling point, allowing it to be heated to higher temperatures and thereby carry more heat out of the reactor core.
Schematic diagram of an RBMK Schematic side view of the layout of an RBMK reactor core The reactor hall and piping systems of the RBMK reactor. The reactor pit or vault is made of reinforced concrete and has dimensions 21.6 m × 21.6 m × 25.5 m. It houses the vessel of the reactor, which is annular, made of an inner and outer cylindrical wall ...
The reactor buildings of Bradwell magnox nuclear power station. The magnox reactors were considered at the time to have a considerable degree of inherent safety because of their simple design, low power density, and gas coolant. Because of this they were not provided with secondary containment features. A safety design principle at the time was ...
Containment systems for nuclear power reactors are distinguished by size, shape, materials used, and suppression systems. The kind of containment used is determined by the type of reactor, generation of the reactor, and the specific plant needs. Suppression systems are critical to safety analysis and greatly affect the size of containment.