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A core shroud is a stainless steel cylinder surrounding a nuclear reactor core whose main function is to direct the cooling water flow. [1] The nuclear reactor core is where the nuclear reactions take place. Because the reactions are exothermic, cool water is needed to prevent the reactor core from melting down. The core shroud helps by ...
Whilst most power reactors do have a pressure vessel, they are generally classified by the type of coolant rather than by the configuration of the vessel used to contain the coolant. The classifications are: Light-water reactor - Includes the pressurized water reactor and the boiling water reactor. Most nuclear power reactors are of this type.
A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction. They are used for commercial electricity, marine propulsion, weapons production and research. Fissile nuclei (primarily uranium-235 or plutonium-239) absorb single neutrons and split, releasing energy and multiple neutrons, which can induce further fission.
VVR-M 18 MW reactor at St. Petersburg Institute of Nuclear Physics IBR-2 2 MW pulsed reactor at Joint Institute for Nuclear Research SM, Arbus (ACT-1), MIR.M1, RBT-6, RBT-10 / 1, RBT-10 / 2, BOR-60 and VK-50 Research Institute of Atomic Reactors
One type uses solid nuclear graphite for the neutron moderator and ordinary water for the coolant. 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 ...
A WWER-1000 (or VVER-1000 as a direct transliteration of Russian ВВЭР-1000), a 1000 MWe Russian nuclear power reactor of PWR type. 1: control rod drives 2: reactor cover [10] or vessel head [11] 3: Reactor pressure vessel 4: inlet and outlet nozzles 5: reactor core barrel or core shroud 6: reactor core
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. [1] These reactors can be fueled with more-commonly available isotopes of uranium and thorium, such as uranium-238 and thorium-232, as opposed to the rare uranium-235 which is used in conventional reactors.
The high-temperature engineering test reactor (HTTR) is a graphite-moderated gas-cooled research reactor in Ōarai, Ibaraki, Japan operated by the Japan Atomic Energy Agency. It uses long hexagonal fuel assemblies, unlike the competing pebble bed reactor designs. HTTR first reached its full design power of 30 MW (thermal) in 1999.