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  2. Loss-of-coolant accident - Wikipedia

    en.wikipedia.org/wiki/Loss-of-coolant_accident

    The Fukushima Daiichi nuclear disaster in 2011 occurred due to a loss-of-coolant accident. The circuits that provided electrical power to the coolant pumps failed causing a loss-of-core-cooling that was critical for the removal of residual decay heat which is produced even after active reactors are shut down and nuclear fission has ceased.

  3. Nuclear meltdown - Wikipedia

    en.wikipedia.org/wiki/Nuclear_meltdown

    A loss-of-coolant accident and a loss-of-pressure-control accident are closely related in some reactors. In a pressurized water reactor, a LOCA can also cause a "steam bubble" to form in the core due to excessive heating of stalled coolant or by the subsequent loss-of-pressure-control accident caused by a rapid loss of coolant.

  4. Fukushima nuclear accident (Unit 3 Reactor) - Wikipedia

    en.wikipedia.org/wiki/Fukushima_nuclear_accident...

    At 05:38 there was no means of adding coolant to the reactor, owing to loss of power. Work to restore power and to vent excessive pressure continued. [12] At one point, the top three meters of the uranium/mixed oxide fuel rods were not covered by coolant. [13]

  5. List of nuclear power accidents by country - Wikipedia

    en.wikipedia.org/wiki/List_of_nuclear_power...

    LOCA loss of coolant accident. 2,739 litres of coolant oil leaked, most of it into the Winnipeg River. The repair took several weeks for workers to complete. [23] 0: Unknown August 1, 1983: Pickering nuclear Reactor 2, Pickering, Ontario, Canada: LOCA loss of coolant accident. Pressure tube, that holds the fuel bundles, ruptured due to hydriding.

  6. Behavior of nuclear fuel during a reactor accident - Wikipedia

    en.wikipedia.org/wiki/Behavior_of_nuclear_fuel...

    The Loss of Fluid Tests (LOFT) were an early attempt to scope the response of real nuclear fuel to conditions under a loss-of-coolant accident, funded by USNRC. The facility was built at Idaho National Laboratory, and was essentially a scale-model of a commercial PWR. ('Power/volume scaling' was used between the LOFT model, with a 50MWth core ...

  7. Investigations into the Chernobyl disaster - Wikipedia

    en.wikipedia.org/wiki/Investigations_into_the...

    RBMK issues: 1. Using a graphite moderator in a water-cooled reactor, permitting criticality in a total loss of coolant accident. 2. A positive steam void coefficient that made the destructive power excursion possible. 3. Control rods design; taking 18–20 seconds to be fully inserted, and with graphite tips that increased reactivity initially. 4.

  8. Chernobyl disaster - Wikipedia

    en.wikipedia.org/wiki/Chernobyl_disaster

    [21]: 51–52 The test program called for disabling the emergency core cooling system, a passive/active system of core cooling intended to provide water to the core in a loss-of-coolant accident. Approval from the site chief engineer had been obtained according to regulations. [21]: 18 The test procedure was intended to run as follows:

  9. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    In the case of a loss of coolant accident (LOCA), the water-loss of the primary cooling system can be compensated with normal water pumped into the cooling circuit. On the other hand, the standby liquid control (SLC) system (SLCS) consists of a solution containing boric acid , which acts as a neutron poison and rapidly floods the core in case ...