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Method and system for dealing with loss of coolant accident (LOCA) of nuclear power station

A treatment method and coolant technology, applied in the field of nuclear power, can solve the problems of deepening the core exposure, unimaginable consequences, and aggravating the continuous deterioration of the core water content, so as to reduce the deterioration degree of the water content, alleviate the accident, and shorten the exposure time. effect of time

Active Publication Date: 2014-04-02
中广核工程有限公司 +1
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Problems solved by technology

[0005] It can be seen from the above that in the event of a coolant loss accident in a pressurized water reactor nuclear power plant, the continuous operation of the main pump will aggravate the continuous deterioration of the water content of the core, which will further lead to the deepening of the exposed degree of the core, making the consequences unimaginable

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  • Method and system for dealing with loss of coolant accident (LOCA) of nuclear power station
  • Method and system for dealing with loss of coolant accident (LOCA) of nuclear power station

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[0048]In order to make the purpose, technical solution and technical effect of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments. It should be understood that the specific implementations described in this specification are only for explaining the present invention, not for limiting the present invention.

[0049] In general, the main pump automatic shutdown signal is mainly designed to protect the main pump itself from damage. The purpose is to monitor the necessary parameters (including speed, bearing temperature, main pump shaft seal flow, etc.) When a certain parameter exceeds the limit value, the main pump will be automatically stopped to prevent the main pump from being damaged due to continuous operation when the parameter exceeds the limit value. In the event of a medium / small LOCA, if other superimposed events are not considered, the accident does not ne...

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Abstract

The invention discloses a method for dealing with a loss of coolant accident (LOCA) of a nuclear power station. The method comprises the steps of acquiring a pressure signal of a pressure collection point of a containment vessel of the nuclear power station and a pressure signal of a pressure stabilizer; judging whether the value of the pressure signal of the pressure collection point of the containment vessel exceeds a preset threshold value or not; and if yes, judging that the pressure signal of the pressure stabilizer indicates the pressure of the pressure stabilizer is low, and triggering a main pump to automatically shut down. After the method for dealing with the LOCA of the nuclear power station is adopted, the main pump can automatically and intelligently shut down after the medium / small LOCA happens. Furthermore, the invention also discloses a system for dealing with the LOCA of the nuclear power station.

Description

technical field [0001] The invention belongs to the technical field of nuclear power, and more specifically, the invention relates to a processing method and system for a nuclear power plant coolant loss accident. Background technique [0002] Loss of coolant accident (LOCA) refers to that there is a large breach in the primary circuit of the PWR nuclear power plant, and the coolant replenishment capacity is not enough to make up for the loss from the breach, so that the core gradually loses cooling, resulting in the failure of the fuel rods. Accidents in which the cladding heats up or even burns out. [0003] For a period of time at the beginning of the transient, the flow at the breach is liquid and single-phase. At this stage, the primary circuit loses a lot of water, but the heat discharged from the breach is very small. At this stage, the steam generator mainly relies on the steam generator to derive the heat. The pressure of the primary circuit depends on the pressure...

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Application Information

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IPC IPC(8): G21C9/02
CPCY02E30/40Y02E30/30
Inventor 王振营马廷伟刘玉华孙晨李闰生
Owner 中广核工程有限公司
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