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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 ...
The reactor vessel used in the first US commercial nuclear power plant, the Shippingport Atomic Power Station. Photo from 1956. A reactor pressure vessel (RPV) in a nuclear power plant is the pressure vessel containing the nuclear reactor coolant, core shroud, and the reactor core.
Units 1 through 4 at the plant. At the time of the earthquake, Unit 4 had been shut down for shroud replacement and refueling since 29 November 2010. [1] [2] All 548 fuel assemblies had been transferred in December 2010 from the reactor to the spent fuel pool on an upper floor of the reactor building [3] where they were held in racks containing boron to damp down any nuclear reaction. [4]
The two triangle-shaped arms form a shroud around the cold target to protect it until they open five seconds before a shot. The National Ignition Facility ( NIF ) is a laser -based inertial confinement fusion (ICF) research device, located at Lawrence Livermore National Laboratory in Livermore, California , United States.
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
Major concerns about the safety of the reactor arose from the formation of cracks in the core shroud inside the reactor vessel since the 1990s. This is due to steel corrosion by the coolant. In spite of reinforcements of the shell, and chemical additives in the coolant, the cracks were increasing in length year after year.
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 ...
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.