Experimental device for cooling water loss accident using a nuclear reactor containing building model

Abstract

The present invention relates to cooling water loss accident experiment equipment using a nuclear reactor for accommodating a building model; the cooling water loss accident experiment equipment includes a container for accommodating, an internal surface, a water injection pipe, and a measuring device; the top surface of the container for accommodating is open, the side surface and the bottom surface of the container for accommodating are transparent; the internal structure is arranged in the inside of the container for accommodating; the water injection pipe is arranged on the upper end of the container for accommodating, and can move; the measuring device is arranged on the bottom surface of the container for accommodating, and is used to monitor movements of a fluid and a foreign body in the container for accommodating; and the cooling water loss accident experiment equipment can provide data for overall visual grasp of a cooling water loss accident.

Description

technical field [0001] The invention relates to an experimental device for cooling water loss accident using a nuclear reactor to contain a building model. Background technique [0002] The safety equipment of nuclear power plants is designed in consideration of design basis accidents such as loss of cooling material accidents. When a loss of cooling material accident (LOCA, Loss Of Coolant Accident) occurs, the control rods do not work or cannot be suppressed only by emergency stop using the control rods. In the event of an accident, the emergency core cooling system (ECCS, Emergency Core Cooling System) located inside the nuclear reactor will be activated. At this time, the water stored in the refueling water tank (RWST) will be used as the water source of the sprinkler pump to cool the nuclear reactor. When the refueling water tank is exhausted, it switches to the recirculation operation mode using the recirculation sump, and performs recirculation cooling in which the co...

AI Technical Summary

Problems solved by technology

[0003] However, even if such an emergency core cooling system is in operation, in the event of a cooling water loss accident, there is a possibility that a physical reaction may occur in the containment vessel by substances including other substances such as the substances forming the pipeline and insulation materials due to the rupture of the main pipeline , chemical reaction to produce foreign matter, and this foreign matter hinders the flow path of recirculation cooling, resulting in failure to cool normally, and also moves to the bottom of the reactor building to hinder recirculation and cause filter screen (filter screen) clogging , pump damage can also occur if foreign matter accumulates excessively at specific locations including here

[0004] figure 1 It is a diagram showing the situation of this loss of cooling material accident (LOCA). It can be seen that the pipes inside the nuclear reactor containment vessel ruptured, causing the cooling water to flow at the bottom of the containment vessel, the refueling water tank was activated, and the refueling water tank was collected by the filter for reuse. Cooling water to the sink, it follows that in the event of filter clogging due to foreign matter, the pump is overloaded and cannot properly recirculate cooling

[0005] As for the influence caused by foreign matter, depending on the location of the fracture accident, there may be differences in the distribution of foreign matter, transfer rate, etc., and consideration should be given to the transfer of foreign matter, the chemical interaction during the flow at the front end of the sump filter, and the filtration process. Long-term interaction of foreign matter in the container, formation and decomposition of chemical particles in the recirculated water, head loss, etc., to explain the effect on head loss, but currently it is not possible to provide a visual correlation with foreign matter. Information about distribution, transfer speed, transfer rate, etc.

[0006] Korean Patent Application No. 10-2008-0064121 "A leak monitoring method for a nuclear reactor cooling material system before fracture by applying a Kalman filter or a Kalman smoother to calculate an unconfirmed leak rate of a nuclear reactor cooling material system in a nuclear power plant" provides a Kalman filter or Kalman smoother is used to monitor the leakage of nuclear reactor cooling material system before fracture, but this only provides the leakage rate as a numerical value, and fails to provide the distribution and transfer rate of foreign matter caused by the fracture accident related visibility information

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