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Nuclear meltdown. A simulated animation of a core melt in a light-water reactor after a loss-of-coolant accident. After reaching an extremely high temperature, the nuclear fuel and accompanying cladding liquefies and flows to the bottom of the reactor pressure vessel. Three of the reactors at Fukushima I overheated because the cooling systems ...
1975. Greifswald, East Germany. A near core meltdown at Greifswald Nuclear Power Plant: Three out of six cooling water pumps were switched off for a failed test. A fourth pump broke down by loss of electric power and control of the reactor was lost. 10 fuel elements were slightly damaged before recovery.
The pebble-bed reactor (PBR) is a design for a graphite- moderated, gas-cooled nuclear reactor. It is a type of very-high-temperature reactor (VHTR), one of the six classes of nuclear reactors in the Generation IV initiative. Graphite pebble for reactor. The basic design features spherical fuel elements called pebbles.
The Three Mile Island accident was a partial nuclear meltdown of the Unit 2 reactor (TMI-2) of the Three Mile Island Nuclear Generating Station on the Susquehanna River in Londonderry Township, near Harrisburg, Pennsylvania. The reactor accident began at 4:00 a.m. on March 28, 1979, and released radioactive gases and radioactive iodine into the ...
The country ranks third in the world both in total nuclear power capacity installed and electricity generated, accounting for around one tenth of global nuclear power generated. As of February 2023, China has 55 plants with 57GW in operation, 22 under construction with 24 GW and more than 70 planned with 88GW.
The CPR-1000, or CPR1000 (Chinese PWR) is a Generation II+ pressurized water reactor, based on the French 900 MWe three cooling loop design (M310) imported in the 1980s, improved to have a slightly increased net power output of 1,000 MWe (1080 MWe gross) and a 60-year design life. The CPR-1000 is built and operated by the China General Nuclear ...
The HTR-PM is a high-temperature gas-cooled (HTGR) pebble-bed reactor, the world’s first power plant of this kind. It is a generation IV design. The technology is based on the HTR-10 prototype reactor. [2] The reactor unit has a thermal capacity of 250 MW. Two reactors are connected to a single steam turbine to generate 210 MW of electricity ...
A loss-of-coolant accident (LOCA) is a mode of failure for a nuclear reactor; if not managed effectively, the results of a LOCA could result in reactor core damage. Each nuclear plant's emergency core cooling system (ECCS) exists specifically to deal with a LOCA. Nuclear reactors generate heat internally; to remove this heat and convert it into ...