Loss-of-coolant accident - Wikipedia
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.
Loss Of Coolant Accident (LOCA) | NRC.gov
2023年2月15日 · Loss of coolant accident (LOCA) A potential accident in which a breach in a reactor’s pressure boundary causes the coolant water to rush out of the reactor faster than makeup water can be added back in.
Loss-of-coolant Accident – LOCA - Nuclear Power for Everybody
Loss-of-coolant accidents (LOCAs) are postulated accidents that result in a loss of reactor coolant at a rate in excess of the capability of the reactor makeup system from breaks in the reactor coolant pressure boundary, up to and including a break equivalent in size to the double-ended rupture of the largest pipe of the reactor coolant system.
Loss-of-coolant accidents (LOCAs) are postulated accidents that would result from the loss of reactor coolant, at a rate in excess of the capability of the normal reactor coolant makeup system, from piping breaks in the reactor coolant pressure boundary.
The Loss-of-Coolant Accident (LOCA) source term option in RASCAL implements the core damage and release timing sequences established in NUREG-1465, “Accident Source Terms for Light-Water Nuclear Power Plants.”
Loss of Coolant Accidents - an overview | ScienceDirect Topics
1979年3月28日 · The loss of coolant accident, popularly known as LOCA, is an accident scenario when there is a scarcity of coolant in the reactor circuit. There are two mechanisms of clad tube failure due to LOCA, viz. corrosion (oxidation) and creep (deformation).
The Loss of Coolant Accident (LOCA), is the design basis accident of most reactor concepts. It has different versions for each reactor design and its phenomenology
2005年10月12日 · Reactor scram systems need not contribute to the nuclear shut down because voiding of the core provides sufficient negative reactivity for shutdown. The reactor is isolated after the initiation of the accident, i.e. the regular heat sink is removed.
Cladding Behavior during Postulated Loss-of-Coolant Accidents …
2021年3月24日 · A previous report by this laboratory provided results on cladding embrittlement, breakaway oxidation, and ballooning with rupture under conditions of loss-of-coolant accidents …
6 Loss-of-Coolant Events in Spent Fuel Pools - The National …
Potential mitigation strategies (dispersion of hot fuel assemblies in the pool, water sprays, water replacement) for delaying or preventing fuel damage following pool water loss.