KR100856501B1 - Integrated nuclear reactor safety equipment using driven sprinkling system - Google Patents

Abstract

The present invention relates to an integrated nuclear reactor safety equipment using a driven sprinkling system, and more particularly, is installed to be located in the upper part of the reactor assembly container inside the safety protection vessel, and by spraying the cooling water by gravity in the event of a loss of coolant accident through the broken pipe It is configured to include a driven sprinkling system for improving the condensation efficiency of the discharged steam, and a collecting tank for collecting the condensed water of the steam discharged through the cooling pipe and the break pipe piped by the driven sprinkling system and injected into the reactor assembly container, The present invention relates to a safety facility for an integrated reactor that effectively reduces the internal pressure of the safety protection vessel in the early stage of the loss of coolant and maintains the water level in the reactor assembly container until the middle and second half of the accident.

The integrated reactor safety equipment using the driven sprinkling system according to the present invention includes: a driven sprinkling system installed at a position higher than the reactor assembly container to spray cooling water by gravity; A collecting tank installed around the reactor assembly container and connected to the reactor assembly container through a connection pipe; A safety protective container configured to include the reactor assembly container, a driven sprinkling system, and a water collecting tank therein; And a steam discharged from the steam generator along the main steam pipe passes through a condensation heat exchanger provided inside the nuclear fuel storage tank installed outside the safety protective container and then flows back into the steam generator along the main water supply pipe. Characterized in that it comprises a residual heat removal system.

Description

Safety facility of an integral reactor using a passive spray system

1 is a cross-sectional view showing the structure of an integrated reactor to which the present invention is applied.

Figure 2 is a view showing the system configuration of the safety equipment of the integrated reactor using the driven sprinkler system according to an embodiment of the present invention.

3 is a view showing the internal structure of the watering tank shown in FIG.

4 is a view showing an operating state of the blood-to-electric equipment shown in FIG.

<Explanation of symbols for the main parts of the drawings>

11: reactor assembly container 12: core

13: reactor coolant pump 14: steam generator

16: main steam pipe 17: main water supply pipe

20: safety protective container 30: passive residual heat removal system

31: condensation heat exchanger 32: steam piping

41: nuclear fuel reload tank 50: passive sprinkling system

51: watering tank 52: watering pipe

53: water spray nozzle 54: upper piping

55: stand pipe 56: euro ball

18, 19, 57, 67, 87: valve 60: sump

61: connection pipe 68, 78: check valve

70: safety injection tank 71: safety injection piping

81: discharge piping

The present invention relates to an integrated nuclear reactor safety equipment using a driven sprinkling system, and more particularly, is installed to be located in the upper part of the reactor assembly container inside the safety protection vessel, and by spraying the cooling water by gravity in the event of a loss of coolant accident through the broken pipe It is configured to include a driven sprinkling system for improving the condensation efficiency of the discharged steam, and a collecting tank for collecting the condensed water of the steam discharged through the cooling pipe and the break pipe piped by the driven sprinkling system and injected into the reactor assembly container, The present invention relates to a safety facility for an integrated reactor that effectively reduces the internal pressure of the safety protection vessel in the early stage of the loss of coolant and maintains the water level in the reactor assembly container until the middle and second half of the accident.

In general, in a separate type pressurized water reactor (hereinafter referred to as a separate type reactor), main equipment such as a pressurizer, a steam generator, and a reactor coolant pump are installed outside the reactor vessel, and these main equipment are connected to each other by a large pipe.

In contrast, an integrated pressurized water reactor (hereinafter referred to as an integrated reactor) is a reactor in which the above-mentioned main devices are installed inside the reactor assembly vessel, and there is no need to provide a large size pipe such as a separate reactor outside the reactor assembly vessel. Safety can be further improved by fundamentally eliminating the Loss of Coolant Accident (LOCA) that may occur in a reactor. In this way, since a large coolant loss accident is excluded from an integrated reactor, it is not necessary to equip a facility for a coolant loss accident, thereby improving economic efficiency.

Safety systems applied to conventional separate reactors include safety systems using a combination of active and passive types (hereinafter referred to as active safety systems) and safety systems using only passive safety systems such as AP1000 (hereinafter referred to as passive safety). System line).

First of all, active safety systems are mostly applied in conventional separate reactors, and are used for supplying power to these devices such as containment vessels, nuclear fuel storage tanks, safety injection tanks, safety injection pumps, spraying systems, decompression systems, recirculation systems, etc. It is composed of a diesel generator and the like. This active safety system has been successfully operated in most of the separate reactors for decades and has proven its stability.

However, separate reactors with an active safety system require operator actions such as rearrangement of the associated valves for switching the coolant source within a short time after a coolant accident, which may cause operator error. There is a possibility that pump failure may occur due to long time use, and many facilities related to the active system are included, which increases the construction cost and increases the operation and maintenance costs of these facilities.

On the other hand, the passive safety system was developed to supplement the problems of the active safety system described above, and is a safety system that can be passively operated using natural forces such as gravity and gas compression force.

In general, separate containment vessels are equipped with large containment vessels that can accommodate a large amount of coolant discharge in case of large coolant loss accidents due to the large piping connecting the main equipment. In the case of a large loss of coolant accident in these reactors, the active sprinkling system is operated in the active split type reactor, and in the split type reactor implemented in the passive type, the outside of the containment vessel is cooled by using water or sprayed by gravity to store the temperature of the container. By keeping the temperature at a low temperature, the vapor inside the containment container is condensed on the inner wall of the containment container, and the inside pressure of the containment container is kept below the design pressure. In the case of such a large-scale pipe breakage, if the pressure of the reactor vessel is reduced to atmospheric pressure within a short time, pressure equilibrium is formed between the containment vessel and the reactor vessel, and in the case of small breakage that is not well balanced The auto decompression system is designed to achieve pressure balance.

On the other hand, since there is no large sized pipe in an integrated reactor, the pipe breakage is much smaller than that of a separate reactor, and even in the event of a loss of coolant, the internal pressure of the reactor assembly vessel gradually decreases. In the case of installing a large containment vessel used in a nuclear reactor, it takes a long time to achieve a pressure balance between the containment vessel and the reactor assembly vessel, which makes it difficult to apply the concept of blood-borne equipment using gravity from the beginning of the accident.

For example, AP1000 (or AP600) may be implemented when the passive safety system is implemented by introducing only passive equipment into a separate reactor. AP1000's safety system includes a containment vessel, a driven sprinkling system to reduce the temperature of the containment vessel, a passive residual heat removal system, a core replenishment tank, a accumulator similar to a safety injection tank, an automatic pressure reducing valve, and a nuclear fuel storage tank installed inside the containment vessel. And the like. Here, the containment vessel of AP1000 is very large, so in the event of a loss of coolant, the coolant is sprayed on the outer wall of the containment vessel to lower the temperature of the containment vessel through the driven sprinkling system installed outside the containment vessel. Sufficient condensation area can be secured to condense the vapor released.

However, in the case of a separate reactor such as AP1000, the safety system is designed in consideration of a large coolant loss accident, which is different from the safety system of an integrated reactor in which the possibility of a large coolant loss accident is excluded.

The introduction of a passive safety system into an integrated reactor has been proposed as in Korean Patent Registration No. 10-0419194 (name of the invention: emergency core cooling method and apparatus using a reactor protection vessel and a compression tank). This document describes the concept of implementing safety system by introducing safety protection container, safety injection tank and passive residual heat removal system into an integrated reactor, and implementing the restriction of leakage by safety protection container and long-term safety injection using safety injection tank. It is. However, this case is applicable only to the use of safety protective containers that can withstand relatively high pressures.In case of installing some equipment such as chemical and volume control systems inside the safety protective container, the free volume of the safety protective container is large. There is a problem that the additional pressure of the cooling water is required because the pressure to achieve the pressure balance lowered.

Another case of introducing a passive safety system into an integrated reactor is IRIS (Korean Patent Application No. 10-2004-0068264), which is an integrated reactor developed at the Westinghouse in the United States. IRIS acts like a safety protective container, a small, high-resistance containment vessel, passive residual heat removal system, a condensate tank to reduce the internal pressure of the initial containment vessel and to supply the safety injection in the second half. A safety system is constructed by applying an automatic pressure reduction system to accelerate the pressure balance between the containment vessel and the reactor assembly vessel.

Here, the condensation tank introduces the concept of a condensation tank applied to a boiling pressurized water reactor in order to lower the design pressure of the containment vessel, and the pressure inside the containment vessel increases due to the steam released into the containment vessel due to the loss of coolant. If a pressure differential occurs between the vessel and the condensation tank, the mixed fluid of vapor and gas is introduced into the condensation tank from the containment vessel. The steam introduced into the condensation tank is cooled and condensed in the water of the condensation tank, and the gas is introduced into the gas space of the condensation tank, thereby reducing the pressure of the containment container until the equilibrium between the containment container and the condensation tank. Thereafter, the cooling water of the condensation tank is discharged to the containment vessel when the pressure of the condensation tank becomes higher than the pressure of the containment vessel while the containment vessel is cooled, and is injected into the reactor when the pressure balance between the condensation tank and the reactor is achieved.

However, in this type of reactor, since the supply point of the safety injection water can be changed flexibly according to the pressure difference between the containment vessel and the reactor and the condensation tank, it is difficult to design the condensation tank to control the supply point of the safety injection water. do. In addition, since the discharge line of the automatic decompression system is connected from the reactor to the condensation tank, the condensation tank must accommodate the discharge pressure of the auto decompression system, thereby increasing the design pressure of the condensation tank and securing sufficient gas space in the condensation tank. In order to increase the installation space, the manufacturing cost of the condensation tank is expected to increase.

The present invention solves the problems of the prior art described above. That is, an object of the present invention, by using the driven sprinkling system installed to be located above the reactor assembly container inside the safety protective container by spraying the coolant by gravity in the event of a coolant loss accident, is discharged through the break pipe at the beginning of the accident It improves the condensation efficiency of the steam to reduce the internal pressure of the safety protection container, and utilizes as a cooling water source to collect the sprinkled cooling water in the collection tank and inject it into the reactor assembly container, thereby keeping the water level in the reactor assembly container stable for a long time. The state is to provide safety facilities for integrated reactors.

In addition, by configuring the safety equipment to operate only by the driving force such as gravity or gas pressure, in the event of a coolant loss, it is passively operated without using an active device such as a pump, thereby improving the reliability and safety of the safety system. Another objective is to improve economics by reducing the number of facilities such as related piping and control cables, thereby reducing the cost of manufacturing nuclear power plants.

The present invention as a technical idea for achieving the above object, the drive sprinkling system which is installed at a position higher than the reactor assembly container to spray the cooling water by gravity; A collecting tank installed around the reactor assembly container and connected to the reactor assembly container through a connection pipe; A safety protective container configured to include the reactor assembly container, a driven sprinkling system, and a water collecting tank therein; And a steam discharged from the steam generator along the main steam pipe passes through a condensation heat exchanger provided inside the nuclear fuel storage tank installed outside the safety protective container and then flows back into the steam generator along the main water supply pipe. It provides an integrated nuclear reactor safety equipment using a passive sprinkling system, characterized in that configured to include a residual heat removal system.

Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings.

1 is a cross-sectional view showing the structure of an integrated reactor to which the present invention is applied.

As the integrated reactor to which the present invention is applied, as shown in FIG. 1, main equipment such as the core 12, the pressurizer 15, the reactor coolant pump 13, and the steam generator 14 is a reactor assembly container 11. As a reactor installed therein, a primary cooling system for cooling the core 12 is configured inside the reactor assembly container 11 without piping exposed to the outside.

Looking at the process of circulating the coolant in the primary cooling system of the integral reactor configured as described above are as follows.

The coolant heated in the core 12 is supplied to the reactor coolant pump 13, and flows downward through the reactor coolant pump 13 to be supplied to the annular cavity above the steam generator 14. Subsequently, the coolant passes through the steam generator 14 and is cooled by heat exchange, and then is supplied to the core 12. The coolant is heated in the core 12 and then supplied to the reactor coolant pump 13 again. .

2 is a view showing the system configuration of the safety equipment of the integrated reactor using the driven sprinkler system according to an embodiment of the present invention.

As shown in FIG. 2, the safety facility for the integrated reactor using the driven sprinkling system according to an embodiment of the present invention is connected to the reactor assembly container 11 through a safety injection pipe 71. And a driven sprinkling system (50) installed at a position higher than the reactor assembly container (11) to sprinkle the cooling water by gravity in the event of a loss of coolant, and a connection pipe (61) installed around the reactor assembly container (11). Comprising a water tank (60) connected to the reactor assembly container (11) through, and the reactor assembly container (11), driven sprinkling system (50) and a safety protection container (20) provided to surround the water tank (60). do. In addition, the condensation heat exchanger 31 provided inside the nuclear fuel reloading tank 41 installed outside the safety protective container 20 condenses the steam discharged from the steam generator 14 into water to the steam generator 14. The passive residual heat removal system 30 is configured to be introduced again.

The safety protective container 20 is provided to surround the outside of the reactor assembly container 11 to prevent leakage of the coolant and gas so that radioactive materials emitted from the reactor assembly container 11 do not leak to the external environment in the event of a coolant loss accident. By doing so, it functions as a containment vessel for a conventional commercially available separate reactor.

In addition, the safety protective container 20 is to achieve a state in which the passive safety equipment, such as the driven sprinkling system 50 is operated by gravity to achieve a pressure balance within the reactor assembly vessel in the event of a coolant loss accident, so as to operate a separate reactor It should be designed to withstand high pressures better than large containment vessels.

The passive residual heat removal system 30 is a system for removing residual heat of the core 12 in the case of a loss of coolant or an uncooled loss, and a steam pipe 32 branched from the main steam pipe 16 at the outlet of the steam generator 14. And a condensation heat exchanger (31) provided inside the nuclear fuel storage tank (41) installed at a position higher than the steam generator (14) outside the safety protective container (20), and the inlet side is connected to the steam pipe (32). And a closed circuit composed of a cooling water pipe 33 connecting the outlet of the condensation heat exchanger 31 and the main water supply pipe 17 of the steam generator 14.

Isolation valves 36 and 37 are installed on the steam pipe 32 and the cooling water pipe 33, respectively. When a coolant loss accident occurs and an operation signal for the driven residual heat removal system 30 is generated, the passive residual heat removal system ( The isolation valves 36 and 37 of 30 are automatically opened, and the isolation valves 18 and 19 of the main steam pipe 16 and the main water supply pipe 17 are closed automatically, The operation starts. When the driven residual heat removal system 30 is started, steam formed in the steam generator 14 secondary circuit by the residual heat of the core 12 passes through the main steam pipe 16 and the steam pipe 32 to form a condensation heat exchanger ( 31 is condensed in the course of passing through the condensation heat exchanger (31). The condensed cooling water is re-introduced into the steam generator 14 through the cooling water pipe 33 and the main water supply pipe 17 and recycled.

As described above, the passive residual heat removal system 30 is circulated by the natural force due to the difference in density of steam and water without the help of an active device such as a pump. Cooling performance of the passive residual heat removal system 30 and the safety protective container 20 in the case of a coolant loss accident is an important factor for determining the equilibrium pressure between the reactor assembly container 11 and the safety protective container 20, The better the performance of the passive residual heat removal system 30, the earlier the pressure inside the reactor assembly vessel 11 is lowered, thereby speeding up the pressure balance period between the reactor assembly vessel 11 and the safety protective vessel 20.

The safety injection tank 70 corresponds to a safety injection tank (or accumulator) applied to a conventional separate reactor, and stores cooling water for injecting the reactor assembly vessel 11 therein by using a gas such as nitrogen in advance. Although it is pressurized to the set pressure, when the pressure in the reactor assembly vessel 11 decreases due to the coolant loss accident, the cooling water inside is automatically injected into the reactor assembly vessel 11 by the pressure difference. The safety injection pipe (71) connecting the safety injection tank (70) with the reactor assembly container (11) is provided with a check valve to prevent a backflow from the reactor assembly container (11) to the safety injection tank (70).

The driven sprinkling system 50 has a sprinkling tank 51 for storing cooling water, a sprinkling pipe 52 connected to the sprinkling tank 51 so that the coolant inside the sprinkling tank 51 can be discharged to the outside, and a sprinkling pipe It is installed in the (52) is composed of a plurality of spray nozzles (53) for spraying the cooling water flowing out from the spray tank (51) through the spray pipe (52) to the lower portion, the coolant loss accident occurs to the safety protective container (20) In accordance with the spraying signal automatically generated when the internal pressure of the () rises above the allowable value or the pressure or the water level of the reactor assembly vessel 11, the cooling water inside the spraying tank 51 through the spraying nozzle 53 to gravity Watered by

Integral reactors to which the present invention is applied may cause pipe breaking accidents of various sizes. In an integrated reactor in which a small safety protective container 20 is designed to withstand high pressure, when a small pipe rupture occurs in which the pipe is partially broken, the accident progresses slowly, and thus, the reactor assembly container 11 is removed. Most of the released steam is condensed on the inner wall of the safety protection container 20, and the outer wall of the safety protection container 20 is continuously cooled by air, so that the pressure of the safety protection container 20 is not greatly increased. However, when a relatively large pipe rupture occurs, a relatively large amount of coolant that can be condensed on the inner wall of the safety protection container 20 is released in the middle of the accident, thereby increasing the pressure inside the safety protection container 20. At this time, the small safety protective container 20 has a relatively small condensation area compared to a large containment container, so that the internal pressure is not reduced by condensation of steam discharged from the reactor assembly container 11, and thus, a relatively large condenser in the integrated reactor. The loss of coolant that breaks the pipe (smaller than the separate reactor) causes most of the time for causing the pressure rise of the safety protective container 20 to be concentrated in the middle of the accident.

Therefore, the present embodiment is provided with a passive sprinkling system 50 for sprinkling a large amount of low-temperature cooling water in the middle of the coolant loss accident to increase the condensation area, so that the safety protection container from the pipe break of the reactor assembly container 11 ( 20) By improving the condensation efficiency of the steam discharged to the inside, the internal pressure of the safety protective container 20 can be maintained below the design pressure even in the case of a loss of coolant that causes a relatively large pipe break. Here, the sprinkled cooling water is collected in the cavity 42 and the sump tank 60 around the reactor assembly vessel 11, and in the middle and second half where the pressure equilibrium is required, the cooling water of the sprinkling tank 51 is depleted and the sprinkling function is stopped. It is designed to be.

The upper portion of the watering tank 51 is open at the top is connected to the upper pipe 54 to balance the pressure between the watering tank 51 and the safety protective container (20). In addition, the cooling water storage capacity of the water spray tank 51 is a flow rate required to reduce the internal pressure of the safety protection container 20 in the middle of the coolant loss accident, and the coolant water sprayed in the middle and late of the coolant loss accident and collected in the water collecting tank 60. It is preferable to consider all the flow rates necessary for use as the safety injection water injected into the reactor assembly vessel 11 through the connection pipe 61 or the pipe rupture. Here, it is preferable that the inside of the watering tank 51 is provided with a standpipe 55 for adjusting the flow rate so that the proper flow rate flows out over time after the accident occurs, the internal structure of such watering tank 51 This will be described later in detail.

The sprinkling pipe 52 is equipped with a sprinkling valve 57 which is opened by a sprinkling signal generated in the case of a coolant loss accident, and the sprinkling nozzle 53 is sprinkled to supply a flow rate required for depressurization of the safety protective container 20. A sufficient number is installed on the pipe 52. Here, the watering pipe 52 is connected to the lower portion of the watering tank 51 and extends downward and is connected to the vertical pipe 52a and the vertical pipe 52a on which the watering valve 57 is mounted on the pipe line. Consists of at least one horizontal pipe (52b) is provided with a plurality of spray nozzles (53) in the, it is preferable to be provided to enable spraying over a wide area inside the safety protective container (20).

By condensing a large amount of steam discharged into the safety protection container 20 of the coolant accident accident using the driven sprinkling system 50 configured as described above, the design pressure of the safety protection container 20 is reduced to reduce its manufacturing cost. You can do it.

The collection tank 60 is installed to be connected to the reactor assembly container 11 through the connection pipe 61 around the reactor assembly container 11, and to the coolant and the driven sprinkling system 50 discharged from the reactor assembly container 11. A device for collecting and spraying the coolant sprayed by the reactor assembly container (11), which is installed at a position higher than the safety injection nozzle (not shown) of the reactor assembly container (11) connected to the pipe of the safety injection system.

The connection pipe 61 is connected to the safety injection pipe 71 for transporting the cooling water from the safety injection tank 70 to the reactor assembly container 11, so that the safety protection container 20 and the reactor assembly container 11 are pressure balanced. After the water is collected is configured to be injected into the reactor assembly vessel (11) via the connecting pipe 61 and the safety injection pipe 71 by gravity. Here, the connection pipe 61 is directly connected to the safety injection nozzle of the reactor assembly container 11, not the safety injection pipe 71, so that the collected water is inside the reactor assembly container 11 through the connection pipe 61. It may also be configured to be injected directly into.

On the connection pipe 61, a collection tank connecting valve 67 operated by a safety injection signal and a first check valve 68 for blocking the inflow of coolant from the safety injection tank 70 are installed. In addition, a second check valve 78 is installed on the safety injection pipe 71 between the outlet of the safety injection tank 70 and the connection point of the connection pipe 61, so that the collection tank 60 and the reactor assembly container 11 are separated from each other. To prevent backflow. When safety injection from the safety injection tank 70 to the reactor assembly container 11 is completed and the pressures of the reactor assembly container 11 and the safety protection container 20 are in equilibrium with each other, the water collected in the collection tank 60 is collected in the collection tank 60. (60) and the reactor assembly container 11 are supplied to the reactor assembly container 11 by the water head difference. As such, the structure for supplying water to the reactor assembly vessel 11 using the safety injection tank 70 and the sump tank 60 is the reactor assembly vessel after pressure equilibrium of the reactor assembly vessel 11 and the safety protection vessel 20. 11) can keep the water level stable for a long time.

On the other hand, when a small pipe rupture occurs in which the pipe partially breaks, as described above, most of the steam discharged from the rupture portion condenses in the safety protective container 20 or the like, and the pressure of the safety protective container 20 greatly increases. In contrast, since the internal pressure of the safety protection container 20 does not significantly decrease, it is not easy to achieve pressure balance between the reactor assembly container 11 and the safety protection container 20.

Therefore, one end is connected to the reactor assembly container 11 and the other end is discharged through the discharge pipe 81 connected to the collection tank 60 to discharge the high pressure steam in the reactor assembly container 11 to the water region of the collection tank 60 to condense. The automatic pressure reducing system is configured to further reduce the internal pressure of the reactor assembly vessel 11 when the pressure balance between the reactor assembly vessel 11 and the safety protection vessel 20 is delayed, such as a small pipe break. To promote pressure equilibrium.

The discharge pipe 81 is provided with an automatic pressure reducing valve 87 which is automatically opened when the pressure reduction of the safety protective container 20 proceeds slowly and the pressure balance is delayed when the small pipe is broken. As the opening of the reactor assembly vessel 11 decreases rapidly, the safety protection vessel 20 and the reactor assembly vessel 11 gradually achieve pressure equilibrium.

3 is a view showing the internal structure of the watering tank shown in FIG.

As shown in Figure 3, the inside of the watering tank 51, one end is connected to the inside of the watering tank 51 and the other end is connected to the watering pipe 52, a plurality of flow passages 56 in the longitudinal direction The stand pipe 55 is formed vertically.

As described above, the standpipe 55 vertically provided inside the watering tank 51 has a plurality of flow paths 56 formed along the longitudinal direction, so that the coolant flows out as the water level of the watering tank 51 decreases. As the number of flow paths 56 decreases, the amount of outflow of cooling water decreases. That is, when the internal pressure of the safety protective container 20 at the beginning of the accident reaches the maximum value, the flow rate of the sprayed coolant may be maximized, and the flow rate may be controlled so that the flow rate of the sprayed coolant gradually decreases over time. Will be. Here, the flow rate of the cooling water flowing out of the watering tank 51 can be easily adjusted through the total number and arrangement intervals of the flow passages 56 formed along the longitudinal direction of the standpipe 55.

FIG. 4 is a view showing an operating state of the pre-fungal equipment shown in FIG. 2, and shows a state in which a long-term cooling operation is performed by using the pre-fungal equipment according to the present embodiment after a cooling material loss accident.

Hereinafter, with reference to Figure 4 will be described the operation of the blood-holding equipment according to an embodiment of the present invention when a coolant loss accident occurs.

When a coolant loss accident occurs due to the pipe breakage and the watering signal is operated, the watering valve 57 installed in the watering pipe 52 of the driven watering system 50 is opened to operate the driven watering system 50. As the cooling water in the spraying tank 51 is sprinkled by the operation of the driven sprinkling system 50, the condensation area of the safety protection container 20 increases, and thus, the reactor assembly vessel 11 through the breakage portion of the pipe. The vapor emitted from the condensation is sufficiently condensed in the safety protective container 20 so that the internal pressure of the safety protective container 20 does not increase excessively and is kept below the design pressure. Here, the cooling water discharged from the driven sprinkling system 50 fills the cavity 42 and the sump 60 around the reactor assembly container 11.

At this time, when the pressure inside the reactor assembly container 11 continues to decrease due to the discharge of the coolant through the pipe rupture portion and decreases below the set pressure of the safety injection tank 70, the coolant in the safety injection tank 70 due to the pressure difference. Is injected into the reactor assembly vessel (11) to maintain the water level in the reactor assembly vessel (11).

In addition, the isolation valves 36 and 37 of the driven residual heat removal system 30 are opened by the operation signal to the driven residual heat removal system 30, and the isolation valves of the main steam pipe 16 and the main water supply pipe 17 are opened. When 18 and 19 are closed, the operation of the driven residual heat removal system 30 is started to remove the residual heat of the core 12.

With the safety injection signal, the sump connection valve 67 installed in the connection pipe 61 connecting the sump tank 60 and the safety injection pipe 71 is opened. The safety protection container 20 and the reactor assembly container 11 are opened. When the pressure is in equilibrium, the water collected in the sump tank 60, that is, the water condensed in the sump tank 60, the cooling water sprayed by the driven water sprinkling system 50 and the steam condensed from the reactor assembly vessel 11 are collected. The gravity is supplied into the reactor assembly vessel 11 through the connection pipe 61 and the safety injection pipe 71. Thus, even after the cooling water in the safety injection tank 70 is exhausted by continuously injecting the water collected in the collection tank 60 into the reactor assembly container 11, the safety protection container 20 and the reactor assembly container 11 is By maintaining the water level in the reactor assembly container (11) for a long period of time after the mid-balance pressure accident can be prevented core exposure.

As described above, in the present invention, the safety equipment for the accident of loss of coolant in the integrated reactor includes a safety protective container 20, a safety injection tank 70, a driven water spray system 50, a passive residual heat removal system 30, It consists of devices that use only the driving force (gravity, gas pressure) such as automatic decompression system and sump tank 60 to improve the reliability of the system, remove the pump that requires operation in the event of an accident, and simplify the system to make valves and related piping. By reducing the number of facilities such as can reduce the production cost of nuclear power plants.

The present invention described above is not limited to the above-described embodiments and the accompanying drawings, and various substitutions, modifications, and changes are possible in the art without departing from the technical spirit of the present invention. It will be obvious to those with ordinary knowledge.

As described above, the integrated nuclear reactor safety equipment using the driven sprinkling system according to the present invention, by reducing the internal pressure of the safety protective vessel at the beginning of the loss of coolant by using the driven sprinkling system installed in the upper portion of the safety protection vessel. In addition, the design pressure of the safety protection vessel can be lowered to reduce the manufacturing cost, and the water level in the reactor assembly container can be stabilized for a long time by utilizing it as a cooling water source for collecting the sprinkled coolant into the sump and injecting it into the reactor assembly container. It is effective to improve the stability at the time of accident by maintaining.

In addition, by configuring the safety equipment to operate only by the driving force such as gravity or gas pressure, it is possible to improve the reliability of the system, and to reduce the number of facilities such as valves and related pipes, thereby reducing the production cost of nuclear power plants.

Claims (8)

In the safety equipment to alleviate the loss of coolant to the integral reactor, A driven sprinkling system 50 installed at a position higher than the reactor assembly container 11 to sprinkle the cooling water by gravity in the event of a loss of coolant; A collecting tank 60 installed around the reactor assembly container 11 and connected to the reactor assembly container 11 through a connection pipe 61; A safety protective container 20 configured to include the reactor assembly container 11, a driven water sprinkling system 50, and a water collecting tank 60 therein; And After the steam discharged from the steam generator 14 along the main steam pipe 16 passes through the condensation heat exchanger 31 provided inside the nuclear fuel recharging tank 41 installed outside the safety protection container 20, A passive residual heat removal system 30 configured to flow back into the steam generator 14 along the water supply pipe 17; Integral reactor safety equipment using a driven sprinkler system, characterized in that comprising a. The method of claim 1, The driven sprinkling system 50, The watering tank 51 for storing the cooling water, the watering pipe 52 connected to the watering tank 51 so that the cooling water in the watering tank 51 to the outside, and the watering pipe 52 Integral reactor safety equipment using a passive sprinkling system, characterized in that consisting of a plurality of spraying nozzles (53) for spraying the cooling water flowing out from the watering tank (51) through the watering pipe (52) to the bottom. The method of claim 2, In the upper portion of the watering tank 51, An upper end opening is a safety facility for an integrated reactor using a driven sprinkler system, characterized in that the upper pipe (54) connected between the watering tank (51) and the safety protective container 20 to achieve a pressure balance. The method of claim 2, The sprinkling pipe 52 is, A vertical pipe 52a connected to a lower portion of the water spray tank 51 and extending downward, and equipped with a water spray valve 57 for controlling a flow rate on the pipeline; At least one horizontal pipe (52b) connected to the vertical pipe (52a) and provided with a plurality of spray nozzles (53) on a pipe line; Integral reactor safety equipment using a driven sprinkler system, characterized in that consisting of. The method of claim 2, Inside the watering tank 51, One end is connected to the inside of the watering tank 51, the other end is connected to the watering pipe 52, the stand pipe 55 is formed with a plurality of flow paths 56 in the longitudinal direction is provided vertically Integral reactor safety equipment using a passive sprinkling system, characterized in that. The method of claim 1, Inside the safety protective container 20, A safety injection tank (70) is connected to the reactor assembly container (11) through a safety injection pipe (71) and configured to inject cooling water into the reactor assembly container (11) in the event of a loss of coolant. Safety equipment with integrated reactor using passive sprinkling system. The method of claim 6, The sump tank 60, The safety equipment of the integrated reactor using the driven sprinkling system, characterized in that installed in the position higher than the safety injection nozzle of the reactor assembly container 11 is connected to the safety injection pipe (71). The method of claim 1, The integrated nuclear reactor safety equipment using the driven sprinkling system, One end is connected to the reactor assembly vessel (11) and the other end is configured to include a discharge pipe (81) connected to the sump (60), the pressure balance between the reactor assembly vessel (11) and the safety protection vessel (20) When the delay is delayed, an integrated type using a driven sprinkler system is further provided with an automatic decompression system for releasing steam inside the reactor assembly container 11 through the discharge pipe 81 into the water collection tank 60. Reactor safety equipment.

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