KR101540671B1 - Passive containment cooling system and nuclear power plant having the same - Google Patents

Abstract

The present invention suggests a passive containment cooling system which is formed to make only the air flow in a heat exchanger in the normal operation of a nuclear power plant. The passive containment cooling system includes a cooling water storage unit which is formed to store cooling water inside, a first heat exchanger and a second heat exchanger which are installed on the inner side and the outer side of a containment, respectively, and are connected by a circulation pipe, and suppress pressure rise in the containment by circulating the cooling water received from the cooling water storage unit if the inner pressure of the containment rises over reference pressure, and a connection pipe whose one end is inserted into the cooling water storage unit through the upper side of the cooling water storage unit and the other end is connected to the first heat exchanger, to supply the cooling water of the cooling water storage unit to the first heat exchanger if the pressure of the containment rises over the reference pressure.

Description

BACKGROUND OF THE INVENTION 1. Field of the Invention [0001] The present invention relates to a cooling system,

The present invention relates to a facility for preparing for an accident of a nuclear power plant, and more particularly, to an apparatus for cooling a to-be-poured water cooling system for suppressing an increase in pressure of the storage unit through heat exchange when an accident occurs It is about nuclear power plants.

Nuclear reactors can be classified according to the configuration of the safety system and the installation location of the main equipment. First, reactors are divided into active reactors, which use the same power as pumps, and passive reactors, which use force such as gravity or gas pressure, depending on how the safety system is constructed. Next, the reactor is equipped with a separate reactor (eg, a domestic pressurized water reactor) having main equipment (steam generator, pressurizer, pump impeller, etc.) outside the reactor depending on the installation position of the main equipment, (For example, SMART reactors).

Generally, an enclosure that protects the outside of a reactor vessel (or reactor coolant system of a separate reactor) is called a containment building (or reactor building) when it is built and built using reinforced concrete. (Safety protection container in case of small size). In the present invention, a containment building, a nuclear reactor building, a containment vessel, a safety protection container, and the like are collectively referred to as " storage part "

In the field of nuclear power industry, disputed cooling systems (eg, passive containment building cooling systems or containment building cooling systems) are used in a variety of reactors including integrated reactors. When cooling water or steam is discharged due to the occurrence of a coolant accident or steam tube breakage, the pressure inside the compartment rises. In this case, the coaxial cooling system cools the steam and cools the internal air to maintain the integrity of the compartment System. Other schemes may be used for similar purposes as the counterbalanced cooling system. For example, a method of using a suppression tank (a commercial BWR, CAREM: Argentina, IRIS: Westinghouse Inc.) for guiding and condensing the vapor discharged into the decompression tank to a decompression tank, (SW1000: Pramatom ANP, AHWR: India, SBWR: GE), which uses a heat exchanger (AP1000: Westinghouse) A shell and tube type heat exchanger or a condenser (SBWR: American GE Company, etc.) is mainly applied to the heat exchanger of the compartment cooling system according to the present invention. In active pressurized light water reactors such as domestic commercial reactors (active reactors), active reactor building water sprinkling systems (internal spraying) operated by sprinkling pumps are used.

(Reference: IAEA-TECDOC-1624, Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants, 2009.)

In the conventional storage compartment cooling system (Korean Patent Registration No. 10-1242746, Korean Patent Registration No. 10-1242743, Korean Patent Registration No. 10-1224023), in general, the inside of the heat exchanger is exposed to cooling water, The valve is opened or the pump is driven. Accordingly, in the system in which the inside of the heat exchanger is exposed to cooling water, there is a difficulty in periodically inspecting the inside of the heat exchanger which is very difficult to perform maintenance work. Further, in the system operated according to the operation signal, there is a possibility that the system function due to the malfunction of the measurement and signal processing system or the valve or the pump is lost.

An object of the present invention is to provide an equivalence cooling system and a nuclear power plant having the same, which can reduce the necessity of maintenance work.

Another object of the present invention is to propose a counterbalanced cooling system which is operated by a natural force and has high reliability and can improve the safety of a nuclear power plant.

In order to accomplish the above object, according to one embodiment of the present invention, there is provided a cooling system of an asphalt pavement cooling system, comprising: a cooling water storage unit configured to store cooling water therein; Wherein when the pressure inside the compartment rises above a reference pressure, the refrigerant is supplied to the inside of the compartment by heat exchange of the cooling water supplied from the compartment, A first heat exchanger and a second heat exchanger for suppressing a pressure rise inside the compartment; And one end is inserted into the cooling water storage portion through the upper portion of the cooling water storage portion and the other end is inserted into the cooling water storage portion through the upper portion of the cooling water storage portion so that the cooling water in the cooling water storage portion is supplied to the circulation flow passage when the pressure of the storage portion rises above the reference pressure. As shown in FIG.

According to an embodiment of the present invention, the connection pipe includes: a rising passage portion extending to a predetermined height so as to prevent a flow of cooling water from the cooling water storage portion from being formed in the normal operation pressure range of the nuclear power plant; And when the pressure of the storage portion rises above the reference pressure to form a flow of cooling water at a height equal to or higher than the height of the upward flow path portion, the cooling water is bent by the upward flow path portion to supply the cooling water to the circulation flow path, As shown in Fig.

According to another embodiment of the present invention, the driven poultry cooling system may include a cooling water storage unit that extends from the cooling water storage unit to the internal space of the storage unit, and is configured to form a pressure balance between the storage unit and the cooling water storage unit, And a pressure equalizing pipe for supplying a coolant to the coolant storage unit.

According to another embodiment of the present invention, the first heat exchanger may be installed in the internal space of the compartment, and may be configured to heat-exchange the cooling water supplied through the connection pipe at the time of an accident with the atmosphere.

According to another embodiment of the present invention, the second heat exchanger may be installed outside the compartment and may be formed to remove heat from the fluid transferred from the first heat exchanger.

According to another embodiment of the present invention, the driven pneumatic cooling system further includes an emergency cooling water storage portion formed to store cooling water therein and provided outside the storage portion, and the second heat exchanger includes at least a part Is disposed to be immersed in the cooling water stored in the emergency cooling water storage part, and the emergency cooling water storage part evaporates the cooling water in the emergency cooling water storage part to discharge the heat transferred from the second heat exchanger to the outside.

The second heat exchanger may include a flow path extending at least partially to a position higher than the level of the emergency cooling water storage part and passing the cooling water of the emergency cooling water storage part, Respectively.

According to another embodiment of the present invention, the circulation pipe is connected to the upper part of the first heat exchanger and the upper part of the second heat exchanger so as to transfer the heated or evaporated fluid to the second heat exchanger while passing through the first heat exchanger. A first circulation pipe connected to the first circulation pipe; And a second circulation pipe connected to a lower portion of the second heat exchanger and a lower portion of the first heat exchanger so as to transfer the cooled or condensed fluid to the first heat exchanger while passing through the second heat exchanger.

The to-be-poured cooling system may further include a discharge pipe branched from the circulation flow passage to discharge the non-condensable gas inside the circulation flow passage.

The discharge pipe is inserted into the cooling water storage part to transfer the non-condensable gas to the cooling water storage part, and is immersed in the cooling water, and a sparger installed at the end of the discharge pipe to spray the non-condensable gas to the cooling water storage part. As shown in FIG.

The discharge pipe may be branched from the first circulation pipe to extend into the internal space of the storage part to discharge the non-condensable gas into the inside of the storage part.

According to another embodiment of the present invention, the cooling water storage unit may be installed at a position higher than the lower end of the first heat exchanger to supply cooling water to the circulation channel by using a siphon phenomenon.

According to another embodiment of the present invention, the to-be-poured cooling system includes: a storage pipe connected to a lower portion of the cooling water storage unit and the circulation channel; And an isolation valve installed in the storage pipe and formed to be openable and closable in case of an accident.

In order to achieve the above-mentioned object, the present invention also discloses a nuclear power plant equipped with a coin-driven cooling system. Nuclear reactors, reactor coolant system; A compartment for enclosing the reactor coolant system to prevent leakage of the radioactive material during an accident; And a counterbalanced part cooling system formed to suppress an increase in the pressure inside the compartment by steam emitted from the reactor coolant system or the secondary system at the time of an accident, A cooling water storage unit configured to store the cooling water; Wherein when the pressure inside the compartment rises above a reference pressure, the refrigerant is supplied to the inside of the compartment by heat exchange of the cooling water supplied from the compartment, A first heat exchanger and a second heat exchanger for suppressing a pressure rise inside the compartment; And one end is inserted into the cooling water storage portion through the upper portion of the cooling water storage portion and the other end is inserted into the cooling water storage portion through the upper portion of the cooling water storage portion so that the cooling water in the cooling water storage portion is supplied to the circulation flow passage when the pressure of the storage portion rises above the reference pressure. As shown in FIG.

According to the present invention having the above-described structure, the cooling water does not flow into the circulation flow path including the first heat exchanger, the second heat exchanger and the circulation pipe during the normal operation of the nuclear power plant, and the inside of the circulation flow path is filled with air, The present invention can greatly reduce the necessity of maintenance of the inside of the circulation channel.

According to the present invention, cooling water flows into the circulating flow path by natural force in response to an increase in pressure inside the compartment when an accident occurs in a nuclear power plant, and the pressure rise inside the compartment through heat exchange in the first heat exchanger and the second heat exchanger .

Further, since the present invention utilizes natural forces, the possibility of malfunction is very small, and the overall safety of the nuclear power plant can be improved.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1A is a conceptual diagram illustrating a normal operation of a nuclear power plant with a coinage charging system according to an embodiment of the present invention; FIG.
FIG. 1B is a conceptual diagram showing a virtual accident of a to-be-poured cooling system shown in FIG. 1A and a nuclear power plant having the same. FIG.
FIG. 2A is a conceptual diagram showing a normal operation of a nuclear power plant with a coinage charging system according to another embodiment of the present invention; FIG.
FIG. 2B is a conceptual diagram showing a virtual accident of the to-be-poured cooling system shown in FIG. 2A and a nuclear power plant having the cooling system. FIG.
FIG. 3A is a conceptual diagram showing a normal operation of a nuclear power plant with a coinage charging system according to another embodiment of the present invention; FIG.
FIG. 3B is a conceptual view showing a virtual accident of a to-be-poured cooling system shown in FIG. 3A and a nuclear power plant having the same. FIG.
FIG. 4A is a conceptual diagram showing a normal operation of a nuclear power plant with a coinage charging system according to another embodiment of the present invention. FIG.
FIG. 4B is a conceptual view showing a cool-down system of the to-be-poured cooling system shown in FIG.
FIG. 5A is a conceptual diagram showing a normal operation of a nuclear power plant having the same-padded cooling system according to another embodiment of the present invention; FIG.
FIG. 5B and FIG. 5C are conceptual diagrams showing a virtual accident of the to-be-poured cooling system shown in FIG. 5A and a nuclear power plant having the cooling system.
FIG. 6A is a conceptual view showing a normal operation of a nuclear power plant with a coinage charging system according to another embodiment of the present invention; FIG.
FIG. 6B is a conceptual diagram showing a virtual accident of a nuclear power plant including the same and a coinage cooling system shown in FIG. 6A. FIG.
FIG. 7A is a conceptual diagram showing a normal operation of a nuclear power plant with a coinage charging system according to another embodiment of the present invention; FIG.
FIG. 7B is a conceptual diagram showing a virtual accident of the to-be-poured cooling system shown in FIG. 7A and a nuclear power plant having the cooling system. FIG.
FIG. 8A is a conceptual view showing a normal operation of a nuclear power plant with a coinage charging system according to another embodiment of the present invention; FIG.
FIG. 8B is a conceptual view showing a case of a coinage cooling system shown in FIG. 8A and a case of a nuclear accident involving the same. FIG.
FIG. 9A is a conceptual diagram showing a normal operation of a nuclear power plant having the same to-be-poured cooling system according to still another embodiment of the present invention; FIG.
FIG. 9B is a conceptual view showing a virtual accident of the to-be-poured cooling system shown in FIG. 9A and a nuclear power plant having the same. FIG.

BEST MODE FOR CARRYING OUT THE INVENTION Hereinafter, a coated copper cooling system and a nuclear power plant having the same according to the present invention will be described in detail with reference to the drawings. In the present specification, the same reference numerals are given to the same components in different embodiments, and the description thereof is replaced with the first explanation. As used herein, the singular forms "a", "an" and "the" include plural referents unless the context clearly dictates otherwise.

FIG. 1A is a conceptual view showing a normal operation of an as-received payment cooling system 100 and a nuclear power plant 10 having the same according to an embodiment of the present invention. FIG. 1B is a conceptual view showing a virtual accident of the to-be-poured cooling system 100 shown in FIG. 1A and a nuclear power plant 10 having the same. The left side of FIG. 1B shows the beginning of an accident when a virtual accident occurs in the nuclear power plant 10, and the right side of FIG. 1B shows the middle or late of an accident.

The reactor coolant system 10 is a coolant system that transports thermal energy generated by nuclear fission of nuclear fuel in the core 11a. The core 11a is installed inside the reactor coolant system 10 and the chamber 12 is installed outside the reactor coolant system 10. [ A piping 13 for the normal operation of the nuclear power plant 10 is connected to the reactor coolant system 10. Among the isolation valves 13a provided in the piping 13, (See FIG. 1A), and is closed by a related signal when an accident occurs in the nuclear power plant 10 (see FIG. 1B).

The compartment 12 surrounds the reactor coolant system 10 to prevent leakage of radioactive material during an accident. The compartment 12 is the last means for preventing leakage of radioactive material to the external environment. The compartment 12 is collectively referred to as a containment building, a reactor building, a containment vessel, and a safety protection vessel, and may be formed of any one of a containment building, a nuclear reactor building, a containment vessel, and a safety protection vessel according to necessity of the nuclear power station 10.

The coinage cooling system 100 is a system for preparing for the accident of the nuclear power plant 10. The coinage cooling system 100 suppresses the pressure inside the compartment 12 from rising due to the steam emitted from the reactor coolant system 10 or the piping 13 connected to the reactor coolant system 10 at the time of an accident . To this end, the to-be-poured cooling system 100 includes a cooling water storage unit 110, a first heat exchanger 120, a second heat exchanger 130, and a connection pipe 140. The coinage cooling system 100 further includes an emergency cooling water storage unit 150, a circulation pipe 160, a pressure equalization pipe 170, a discharge pipe 180, and various valves installed in the respective pipes .

The cooling water storage unit 110 may be installed in a space inside the compartment 12 or outside the compartment 12. [ The configuration of the cooling water storage unit 110 or the configuration of the pipe connected to the cooling water storage unit 110 may be changed according to the installation position of the cooling water storage unit 110. [ The cooling water storage portion 110 shown in FIGS. 1A and 1B is installed in the inner space of the storage portion 12. As shown in FIG.

The cooling water storage unit 110 is formed to store cooling water therein. The cooling water storage unit 110 may be formed in the form of a storage tank or a storage tank. The structure of the storage tank and the storage tank may vary depending on the installation position of the cooling water storage unit 110.

For example, if a storage tank is installed inside the compartment 12, the storage tank may be configured to include: i) an open structure with the top open completely, ii) a partially open structure with the top partially open, iii) 170) to communicate with the inner space of the compartment (12). In contrast, when the storage tank is provided outside the compartment 12, it can be formed in a structure communicating with the internal space of the compartment 12 by the pressure equalizing pipe 170.

When the storage tank is provided inside the compartment 12, the compartment 12 may be formed of any one of i) an open structure with the top open completely, and ii) a partial open structure with the top partially open . In contrast, when the storage tank is provided outside the compartment 12, it can be formed in a structure that communicates with the internal space of the compartment 12 by the pressure equalization pipe 170.

The cooling water storage portion 110 shown in Figs. 1A and 1B is formed in the form of a storage tank and is structured to communicate with the internal space of the compartment 12 by the pressure equalization pipe 170. [

The first heat exchanger 120 is installed inside the compartment 12 and the second heat exchanger 130 is installed outside the compartment 12. [ The second heat exchanger (130) is installed at a higher position than the first heat exchanger (120) for circulating the cooling water. The emergency cooling water storage part 150 is formed to store the cooling water therein, and is installed outside the storage part 12. The second heat exchanger 130 may be installed inside the emergency cooling water storage part 150 and may be immersed in the cooling water of the emergency cooling water storage part 150. The emergency cooling water storage part (150) evaporates the cooling water inside and emits heat transferred from the second heat exchanger (130).

The types of the first heat exchanger 120 and the second heat exchanger 130 may be selected from at least one of a shell and tube type heat exchanger and a plate type heat exchanger. The shell-and-tube heat exchanger implements heat exchange by passing different fluids through each of the flow paths separated by the shell and the tube. The plate-type heat exchanger includes a plate-type heat exchanger and a plate-type heat exchanger. The plate-type heat exchanger is formed by diffusion bonding and has a dense flow path by a photochemical etching technique. The plate heat exchanger is formed by extruding a plate to form a flow path and joining the plates to each other by at least one bonding technique such as gasketing, welding, or brazing.

The first heat exchanger 120, the second heat exchanger 130, and the circulation pipe 160 form a circulation flow path for circulating the heat exchange fluid. More specifically, the heat exchange fluid continuously circulates along a part of the flow path of the first heat exchanger 120, a part of the flow path of the second heat exchanger 130, and the circulation path formed by the circulation pipe 160.

In the present invention, the inside of the circulation flow path is filled with air during normal operation of the nuclear power plant 10, and the cooling water does not pass through the circulation flow path. When the pressure inside the compartment 12 rises above the reference pressure due to an accident or the like, the cooling water passes through the circulation passage. This is accomplished by connecting piping 140, which will be described in more detail below.

The connection pipe 140 is formed to supply the cooling water of the cooling water storage part 110 to the circulation channel when the pressure of the compartment part 12 rises above the reference pressure. Specifically, one end of the connection pipe 140 is inserted into the cooling water storage part 110 through the upper part of the cooling water storage part 110, and the other end is extended from the one end to be connected to the circulation flow path. More specifically, the first heat exchanger 120 and the second heat exchanger 130 have a plurality of flow paths, and a part of the plurality of flow paths forms a circulation flow path. The other end of the connection pipe 140 may be connected to a flow path of the circulation flow path of the first heat exchanger 120 and the second heat exchanger 130. The other end of the connection pipe 140 may be connected to the circulation pipe 160. 1A and 1B, the other end of the connection pipe 140 is connected to the lower portion of the first heat exchanger 120. However, if it is possible to supply the cooling water to the circulation channel, the connection pipe 140 and the circulation channel connection The position is not limited.

If the pressure of the compartment 12 becomes higher than the reference pressure by the pressure of the compartment 12 as a reference for occurrence of an accident in the nuclear power plant 10, .

The connecting pipe 140 includes a rising passage portion 140a and a falling passage portion 140b.

The upward flow path portion 140a extends to a predetermined height to prevent the formation of a flow of cooling water from the cooling water storage portion 110 in the normal operation pressure range of the nuclear reactor 10. [ As shown in Figs. 1A and 1B, the lower end of the ascending channel portion 140a is immersed in the cooling water, and the upper end of the ascending channel portion 140a extends to a position higher than the water level of the cooling water.

Referring to FIG. 1A, the cooling water storage unit 110 and the circulation flow path maintain a pressure balance of the atmospheric pressure level between the connection pipe 140 and the cooling water storage unit 110 during normal operation of the nuclear power plant 10. The siphon break phenomenon is maintained by the height difference H of the cooling water and the upper end of the rising passage portion 140a even if the internal pressure of the compartment portion 12 fluctuates within the range of the reference pressure or less, 140). The height difference H may be determined according to the time point at which the operation of the as-dispensed cooling system 100 is requested and at what point after the occurrence of the accident.

During normal operation of the nuclear power plant 10, the cooling water is stored in the cooling water storage part 110, and cooling water is not supplied to the circulation flow path. However, if the interior of the circulation flow path is filled with air during the normal operation of the nuclear power plant 10 as in the present invention, the first heat exchanger 120, the second heat exchanger 130, It is possible to reduce the necessity of maintenance of the circulation pipe 160, thereby making maintenance work easier.

When the pressure of the compartment portion 12 rises above the reference pressure and the flow of the cooling water is formed above the height of the ascending channel portion 140a, the descending channel portion 140b supplies the cooling water to the circulating channel And is bent in the upward flow path portion 140a to extend downward. The fact that the pressure in the compartment 12 has risen above the reference pressure means that an accident has occurred in the compartment 12 and the pressure of the compartment 12 has exceeded the normal operating pressure range. For example, as shown in FIG. 1B, when a break occurs in the piping 13 connected to the reactor coolant system 10, steam is discharged through the break portion 13b, and the pressure inside the compartment 12 is It may increase and exceed the reference pressure.

When the pressure in the compartment portion 12 exceeds the reference pressure, the pressure equalizing pipe 170 forms a pressure balance between the cooling water storage portion 110 and the compartment portion 12. The pressure equalizing pipe 170 is formed to extend from the cooling water storage portion 110 to the inner space of the compartment 12. [ The pressure equalizing pipe 170 provides a flow path for introducing the atmosphere inside the compartment portion 12 into the cooling water storage portion 110 so as to form a pressure balance between the compartment portion 12 and the cooling water storage portion 110.

When the atmosphere of the compartment portion 12 flows into the cooling water storage portion 110 through the pressure equalizing pipe 170, the pressure inside the cooling water storage portion 110 gradually increases. As the pressure inside the cooling water storage part 110 continuously increases, the cooling water is further drawn into the upflow channel part 140a, and the water level inside the upflow channel part 140a gradually increases. The siphon break phenomenon is eliminated and the connection pipe 140 is cooled by the siphon phenomenon and the cooling water stored in the cooling pipe 140a Thereby transferring the cooling water of the unit 110 to the circulation channel. In order to use the siphon phenomenon, the cooling water storage unit 110 should be installed at a position higher than the connection position of the circulation flow path with the connection pipe 140.

The first heat exchanger 120 allows only the atmosphere inside the compartment 12 to pass through the internal flow path during normal operation of the nuclear power plant 10 and exchanges the cooling water supplied through the connection piping 140 with the atmosphere . The second heat exchanger 130 is formed to remove the heat of the fluid (steam or cooling water) transferred from the first heat exchanger 120. The method of cooling the fluid in the second heat exchanger 130 may be implemented by at least one of a water-cooled type, an air-cooled type, or a mixed type in which the water-cooled type and the air-cooled type are mixed.

The first heat exchanger 120 and the second heat exchanger 130 are connected to each other by a circulation pipe 160 so as to circulate cooling water in the event of an accident. Part of the flow path of the first heat exchanger 120, part of the flow path of the second heat exchanger 130, and the circulation pipe 160 form a circulation flow path. For example, at least one of the first heat exchanger 120 and the second heat exchanger 130 may be formed as a shell-and-tube heat exchanger, wherein some of the flow paths refer to either the shell side or the tube side.

The compartment 12 can be cooled by the cooling water circulating through the circulation channel. When the temperature difference between the first heat exchanger 120 and the second heat exchanger 130 is insufficient (for example, when the temperature difference between the first heat exchanger 120 and the second heat exchanger 130 is not sufficient), the circulation of the cooling water uses the density difference generated by the difference in temperature or phase, And the temperature of the compartment 12 is within the normal operating pressure range), the circulation of the fluid is limited.

The circulation pipe 160 includes a first circulation pipe 161 and a second circulation pipe 165.

The first circulation pipe 161 is connected to the upper portion of the first heat exchanger 120 and the upper portion of the second heat exchanger 130 so as to transfer the cooling water that has been heated or evaporated while passing through the first heat exchanger 120 to the second heat exchanger 130. [ Respectively. The second circulation pipe 165 is connected to the lower portion of the second heat exchanger 130 and the lower portion of the first heat exchanger 130 so as to transfer the cooled or condensed cooling water to the first heat exchanger 120 while passing through the second heat exchanger 130. [ (Not shown).

The coined payment cooling system 100 may further include a discharge piping 180 and a sparger 185 for the discharge of non-condensable gases or vapors. The first heat exchanger 120, the second heat exchanger 130 and the circulation pipe 160 form a circulation channel and the discharge pipe 180 is connected to the circulation pipe (not shown) to discharge non-condensable gas or vapor in the circulation channel. 160). As shown in FIGS. 1A and 1B, the discharge pipe 180 is branched from the first circulation pipe 161 to transfer the non-condensable gas to the cooling water storage unit 110, and is inserted into the cooling water storage unit 110 . The discharge pipe 180 may be provided with an air discharge valve 181 and a check valve 182. The atmospheric release valve 181 may be provided in plural or in parallel, and is opened at a pressure higher than a predetermined value and closed at a pressure lower than a predetermined value. The check valve 182 passes only the flow toward the cooling water storage. The sparger 185 may be installed at the end of the discharge line 180 to inject the non-condensable gas into the cooling water reservoir 110.

The isolation valves 141, 162, 166 and 171 or the check valves 142 and 182 are connected to the connection pipe 140, the first circulation pipe 161, the second circulation pipe 165 and the pressure equalization pipe 170, At least one of them is installed. The isolation valves 141, 162, 166 and 171 are provided at a time when the maintenance work of the to-be-matched cooling system 100 is required or when the isolation of the storage compartment 12 is required It can be closed manually. The isolation valves 141, 162, 166 and 171 may be kept open during normal operation of the nuclear power plant 10. [ The check valves 142 and 182 prevent backflow of the cooling water or non-condensable gas.

Since the normal operation of the nuclear power plant 10 has been described above, the operation of the coinage cooling system 100 during the occurrence of a virtual accident of the nuclear power plant 10 will be described below with reference to FIG.

First, the initial stage of the accident of the nuclear power plant 10 is referred to the left side of FIG. 1B.

When breakage occurs in the piping 13 connected to the reactor coolant system 10, the isolation valves 13a provided in the piping 13 are closed by the related signal. When steam is discharged into the compartment 12 through the rupturing portion 13b, the pressure inside the compartment 12 gradually rises. When the temperature or pressure reaches an operation reference value of the relevant safety system due to an accident, various safety systems installed in the nuclear reactor 10 start operating. The conditions under which the safety systems start to operate may differ from each other.

The passive safety injection system 14 injects the coolant into the reactor coolant system 10 to maintain the level of the reactor coolant system 10. The driven residual heat eliminating system 15 removes the sensible heat of the reactor coolant system 10 and the residual heat of the core 11a.

The to-be-poured cooling system (100) suppresses the pressure rise of the compartment (12).

As the pressure of the compartment 12 gradually increases, air or steam in the compartment 12 flows into the interior of the cooling water reservoir 110 through the pressure equalization pipe 170, Is gradually increased. The cooling water stored in the cooling water storage part 110 flows into the upward flow path part 140a of the connection pipe 140 and the water level in the upward flow path part 140a gradually increases.

When the pressure inside the compartment 12 rises above the reference pressure, the water level of the cooling water exceeds the upflow channel portion 140a, and the siphon break phenomenon is eliminated. The cooling water is supplied to the circulation channel through the connection pipe 140. The supply of the cooling water continues until a pressure equilibrium state is formed between the cooling water storage portion 110 and the circulating flow passage.

The cooling water supplied to the first heat exchanger 120 passes through the first heat exchanger 120 and is heat-exchanged with the atmosphere inside the relatively high-temperature compartment 12. The cooling water and the atmosphere pass through different flow paths of the first heat exchanger 120, and the heat is transferred from the atmosphere to the cooling water. Since the fluid ascends or falls depending on the density, the atmosphere cooled while passing through the first heat exchanger 120 is lowered, and the fluid heated or evaporated while passing through the first heat exchanger 120 rises.

The atmosphere inside the compartment 12 can be cooled and condensed by the heat exchange process in the first heat exchanger 120. A portion of the cooling water can be evaporated and the fluid (steam formed by evaporation of cooling water or cooling water) flows through the first circulation pipe 161 connected to the upper portion of the first heat exchanger 120, Lt; / RTI >

The second heat exchanger 130 shown in Figs. 1A and 1B is formed to implement a water cooling type cooling system. The second heat exchanger 130 is completely immersed in the cooling water of the emergency cooling water storage part 150. The cooling water flowing through the first circulation pipe 161 and the cooling water of the emergency cooling water storage part 150 pass through the second heat exchanger 130 in the opposite directions. The heat is transferred from the cooling water circulating in the circulation flow path to the cooling water in the emergency cooling water storage part 150. Referring to the flow inside the second heat exchanger 130, the fluid introduced through the first circulation pipe 161 is lowered and the fluid in the emergency cooling water storage part 150 is raised.

The cooled or condensed cooling water in the circulating flow passage is again transferred to the first heat exchanger 120 through the second circulation pipe 165. Then, the refrigerant passes through the first heat exchanger (120) and exchanges heat with the atmosphere inside the compartment (12). As long as the temperature gradient is maintained between the cooling water inside the circulation channel and the atmosphere inside the compartment, the cooling water circulates in the circulation channel and repeats the heat exchange process.

The cooling water in the emergency cooling water storage part 150 receives heat from the second heat exchanger 130 and is heated. The emergency cooling water storage unit 150 discharges heat to the environment through the heat of evaporation. Specifically, the cooling water in the emergency cooling water storage part 150 is evaporated by the temperature rise, and is discharged to the outside through the opening part 151.

The non-condensable gas or vapor in the circulation channel flows into the cooling water storage unit 110 through the discharge pipe 180 branched from the first circulation pipe 161 and flows into the cooling water storage unit 110 through the sparger 185 . The steam is condensed and the non-condensable gas is collected inside the cooling water storage part 110.

Next, the middle or late period of the nuclear power plant 10 is referred to the right side of FIG. 1B.

The water level of the cooling water storage part 110 is gradually lowered as the cooling water is continuously supplied to the first heat exchanger 120 from the cooling water storage part 110 through the connection pipe 140. The cooling water supplied from the cooling water storage unit 110 continuously circulates through the circulation channel.

The pressure (first pressure) due to the water head difference between the cooling water storage portion 110 and the first heat exchanger 120 is gradually reduced. The injection of the cooling water stops when the first pressure and the pressure inside the circulating flow passage (second pressure) are in equilibrium. The cooling water existing in the downflow channel portion 140b may flow backward but the downflow channel portion 140b is provided with the check valve 142 to prevent the backflow of the cooling water.

 Since the aspirated dispensing cooling system 100 condenses the vapor inside the compartment 12, the pressure rise inside the compartment 12 can be suppressed and the mechanical integrity of the compartment 12 can also be maintained. The to-be-poured cooling system 100 reduces the concentration of the radioactive material inside the compartment 12 as well. The plurality of equipotential cooling systems 100 may be provided.

Hereinafter, another embodiment of the coinage cooling system 100 and the nuclear power plant 10 having the same will be described.

FIG. 2A is a conceptual view showing normal operation of the to-be-poured cooling system 200 and the nuclear power plant 20 having the same according to another embodiment of the present invention. FIG. 2B is a conceptual view showing a virtual accident of the to-be-poured cooling system 200 shown in FIG. 2A and the nuclear power plant 20 having the same.

The structure of the coined-bed cooling system 200 shown in FIGS. 2A and 2B is similar to the coined-bed cooling system 100 described in FIGS. 1A and 1B. However, the to-be-poured cooling system 200 shown in Figs. 2A and 2B further includes a reservoir pipe 211 and an isolation valve 212 that can be prepared for malfunction or non-operation.

The storage pipe 211 is connected to the lower part of the cooling water storage part 210 and the first heat exchanger 220. Specifically, the reservoir pipe 211 is connected to the flow path of the circulation flow path of the first heat exchanger 220. 2A and 2B, the other end of the connection pipe 240 is connected to the first heat exchanger 220. However, if it is possible to supply the cooling water to the circulation channel, the connection position between the connection pipe 240 and the circulation channel is It is not limited.

As shown in FIGS. 2A and 2B, the reservoir pipe 211 can join the downflow channel 240b of the connection pipe 240. The isolation valve 212 is installed in the reservoir piping 211 and can be opened and closed manually in case of an accident in preparation for the inactivation of the system. Therefore, as shown in FIG. 2A, the isolation valve 212 installed in the reservoir pipe 211 during the normal operation of the nuclear reactor 10 is closed. The cooling water of the cooling water storage part 210 is not supplied to the first heat exchanger 220 during normal operation of the nuclear power plant 20. [

The right side of FIG. 2B shows the normal operation state of the coinage cooling system 200, and the right side of FIG. 2B is an isolation valve (not shown) installed in the storage pipe 211 when the coin- 212 are manually opened.

Referring to the left side of FIG. 2B, the cooling water in the cooling water storage unit 210 is supplied to the first heat exchanger 220 through the connection pipe 240, and circulates through the circulation channel. The operation mechanism of the coined pay cooling system 200 is as described in FIG. However, since the to-be-poured cooling system 200 operates normally, the isolation valve 212 provided in the storage portion piping 211 does not need to be opened.

Next, referring to the right side of FIG. 2B, the cooling water of the cooling water storage unit 210 is not normally supplied to the first heat exchanger 220. The isolation valve 212 provided in the storage pipe 211 is manually opened by the operator and the cooling water in the cooling water storage 210 is supplied to the first heat exchanger 220 through the storage pipe 211. The circulation process of the cooling water in the circulation channel and the heat exchange process between the first heat exchanger 220 and the second heat exchanger 230 are replaced with those described in FIG.

Since the present invention utilizes natural forces, the reliability of the system is high. However, in industries where safety is a top priority, such as the nuclear power plant 20, there is a need to eliminate any possibility of malfunction or malfunction even with a small probability. In this embodiment, a coin-toothed cooling system (200) is proposed, which not only utilizes natural forces but also provides a facility for malfunction or malfunction. Therefore, the present invention can contribute to the overall safety improvement of the nuclear reactor 20.

Hereinafter, another embodiment of a coinage cooling system and a nuclear power plant having the coinage cooling system will be described in order.

FIG. 3A is a conceptual view showing normal operation of the to-be-poured cooling system 300 and the nuclear power plant 30 having the same according to another embodiment of the present invention. FIG. 3B is a conceptual view showing a virtual accident of the to-be-poured cooling system 300 shown in FIG. 3A and the nuclear power plant 30 having the same. The left side of FIG. 3B shows the beginning of an accident when a virtual accident occurs in the nuclear power plant 30, and the right side of FIG. 3B shows the middle or late of the accident.

In this embodiment, the discharge pipe 380 is not inserted into the cooling water storage portion 310, unlike the above-mentioned coinage cooling system 300 described above. The discharge line 380 is branched from the first circulation line 361 to extend into the interior space of the compartment 32 to discharge non-condensable gas or vapor into the interior of the compartment 32.

Referring to the left side of FIG. 3B, when the pressure of the circulation flow path rises above a predetermined value of the atmosphere discharge valve 381 installed in the discharge pipe 380, the atmosphere discharge valve 381 is opened and the non- The gas or vapor is discharged into the inner space of the compartment 32. Then, when the pressure of the circulating flow passage is lowered to a predetermined value or less of the atmosphere discharge valve 381, the atmosphere discharge valve 381 is closed.

The discharge piping 380 may be provided with a check valve 382 as well as an atmosphere discharge valve 381 and the check valve 382 may be used to circulate air or steam inside the compartment 32 through the discharge piping 380 Thereby blocking the flow into the flow path.

FIG. 4A is a conceptual view showing normal operation of the to-be-poured cooling system 400 and the nuclear power plant 40 having the same according to another embodiment of the present invention. FIG. 4B is a conceptual view showing a virtual accident of the to-be-poured cooling system 400 shown in FIG. 4A and the nuclear power plant 40 having the same. The left side of FIG. 4B shows the beginning of the accident when a virtual accident occurs in the nuclear power plant 40, and the right side of FIG. 4B shows the middle or late of the accident.

The coined payload cooling system 400 is formed to implement an air cooling type cooling system. More specifically, the emergency cooling water storage unit 450 is removed from the to-be-poured cooling system 400, and the second heat exchanger 430 is installed in the air outside the compartment 42. The cooling efficiency of the air-cooled type is lower than that of the water-cooled type, so that the size of the second heat exchanger 430 can be relatively larger than that of the above-described embodiments.

Referring to FIG. 4B, the fluid circulating through the circulation channel and the air outside the compartment 42 pass through the second heat exchanger 430. Heat is transferred from the fluid to the air, the fluid is cooled or condensed and falls, and the air heats up.

FIG. 5A is a conceptual view showing a normal operation of the to-be-poured cooling system 500 and the nuclear power plant 50 having the same according to another embodiment of the present invention. FIGS. 5B and 5C are conceptual diagrams showing a virtual accident of the to-be-poured cooling system 500 shown in FIG. 5A and the nuclear power plant 50 having the same. The left side of FIG. 5B shows an initial state of an accident when a virtual accident occurs in the nuclear power plant 50, and the right side of FIG. 5B shows a state between an initial state and an intermediate state of an accident. The left side of FIG. 5C shows the state between the middle and late phases of the accident, and the right side of FIG. 5C shows the end of the accident. When the virtual accident occurs in the nuclear power plant 50, the left and right sides of FIG. 5B and the left and right sides of FIG. 5C show the operating state of the coinage cooling system 500 in a time series order.

In this embodiment, the second heat exchanger 530 is formed so as to implement the heat exchange method in the order of the water-cooling type, the mixing type, and the air-cooling type over time. Specifically, the second heat exchanger 530 extends to a position higher than the water level of the emergency cooling water storage portion 550, and includes a flow passage for passing the cooling water of the emergency cooling water storage portion 550 and a flow passage for passing the air Respectively. Accordingly, the heat exchange system of the second heat exchanger 530 is changed according to the water level reduction of the emergency cooling water storage unit 550.

Hereinafter, the operation of the as-dispensed cooling system 500, which is implemented as a mixed-type heat exchange system, will be described in time series.

Referring to the left side of FIG. 5B, the pressure inside the chamber 52 rises as the steam is released from the rupture portion 53b. Air or steam in the compartment 52 flows into the interior of the cooling water reservoir 510 through the pressure equalization pipe 570. When the pressure of the cooling water storage portion 510 rises above the reference pressure, the cooling water in the cooling water storage portion 510 is supplied to the circulation flow path through the connection pipe 540.

In the first heat exchanger (520), the cooling water and the atmosphere inside the compartment (52) exchange heat. The fluid that has been heated while passing through the first heat exchanger 520 (steam formed by evaporating cooling water or cooling water) is transferred to the second heat exchanger 530 through the first circulation pipe 561.

A part of the second heat exchanger 530 is immersed in the cooling water of the emergency cooling water storage part 550 and the rest is exposed to the air. The second heat exchanger 530 has at least three separate flow passages. The first flow path is a flow path for passing the cooling water supplied from the first circulation pipe 561. The second flow path is a path through which the cooling water of the emergency cooling water storage unit 550 is passed. The third channel is the air or steam passage. Each of the flow paths may be formed in plural.

The fluids pass through the three flow paths and are heat-exchanged with each other, thereby realizing a water-cooling type and an air-cooling type heat exchange type. The heat is transferred from the fluid supplied from the first circulation pipe 561 to the cooling water of the emergency cooling water storage unit 550, and the second heat exchanger 530 implements a water-cooling type heat exchange method. Also, the heat is transferred from the fluid supplied from the first circulation pipe 561 to air or steam, and the second heat exchanger 530 implements an air-cooling type heat exchange method.

The heat exchange mode of the second heat exchanger 530 may be changed according to the progress of the accident. Referring to the left side of FIG. 5B, in the second heat exchanger 530, a water-cooling type heat exchange system is dominant. Referring to the right side of FIG. 5B, the water level of the cooling water storage unit 510 and the emergency cooling water storage unit 550 decreases with time after the occurrence of an accident. However, as in the initial stage of the accident (left side in FIG. 5B), the water-cooled type and the air-cooled type heat exchange system are simultaneously used in the second heat exchanger 530 (mixed type).

Referring to the left side of FIG. 5C, the water level of the emergency cooling water storage portion 550 further decreases. The dominant heat exchange method in the second heat exchanger 530 is changed from the water-cooling type to the air-cooling type.

Finally, referring to the right side of FIG. 5C, the cooling water of the emergency cooling water storage unit 550 is completely evaporated and exhausted, and only the air-cooled heat exchange system is used in the second heat exchanger 530. If the cooling water is replenished into the emergency cooling water storage part 150, the heat exchange method of the second heat exchanger 530 can be changed to the water cooling type or the mixed type again. The cooling water storage portion 510 and the first heat exchanger 520 maintain a pressure balance state in the to-be-poured cooling system 500 shown on the left and right sides of FIG. 5B on the right side of FIG. 5C.

FIG. 6A is a conceptual view showing a normal operation of a to-be-poured cooling system 600 and a nuclear power plant 60 having the same according to another embodiment of the present invention. FIG. 6B is a conceptual view showing a virtual accident of the to-be-poured cooling system 600 shown in FIG. 6A and the nuclear power plant 60 having the same. The left side of FIG. 6B shows the beginning of an accident when a virtual accident occurs in the nuclear power plant 60, and the right side of FIG. 6B shows the middle or late of the accident.

The cooling water storage portion 610 is formed in the form of a storage tank, and is installed in the internal space of the storage portion 62. The storage tank is formed with a partially open structure in which a part of the upper part is opened. The connection pipe 640 is inserted into the storage tank through the upper portion of the storage tank.

The coined pay cooling system 600 does not have a separate pressure balanced pipe 670. 6B, the atmosphere inside the compartment 62 is introduced into the storage tank through the opened top of the storage tank, so that the compartment 62 and the cooling water storage 610 are connected to each other through a pressure balance .

FIG. 7A is a conceptual view showing normal operation of the to-be-poured cooling system 700 and the nuclear power plant 70 having the same according to another embodiment of the present invention. Fig. 7B is a conceptual view showing a virtual accident of the to-be-poured cooling system 700 shown in Fig. 7A and the nuclear power plant 70 having the same. The left side of FIG. 7B shows the beginning of an accident when a virtual accident occurs in the nuclear power plant 70, and the right side of FIG. 7B shows the middle or late of the accident.

The cooling water storage portion 710 is provided outside the compartment 72.

The downflow channel portion 740b of the connection pipe 740 passes through the storage portion 72 and continues to be connected to the first heat exchanger 720. The pressure equalizing pipe 770 passes through the compartment 72 and extends from the cooling water reservoir 710 to the inner space of the compartment 72. [ The discharge line 780 extends from the second heat exchanger 730 to the interior of the cooling water reservoir 710.

Referring to FIG. 7B, steam is discharged from the rupture portion 73b due to the fracture of the pipe 73 connected to the reactor coolant system 70. As shown in FIG.

Referring to the left side of FIG. 7B, the atmosphere inside the compartment 72 flows into the cooling water storage 710 through the pressure equalization pipe 770, and the pressure inside the cooling water storage 710 rises. When the pressure of the cooling water storage portion 710 rises above the reference pressure, the flow of cooling water from the cooling water storage portion 710 to the first heat exchanger 720 is formed. The cooling water supplied to the first heat exchanger 720 circulates through a circulation channel formed by the first heat exchanger 720, the second heat exchanger 730, and the circulation pipe 760. The atmosphere inside the compartment 72 is cooled or condensed while passing through the first heat exchanger 720 and the pressure rise of the compartment 72 is suppressed. The cooling water in the emergency cooling water storage part 750 is heated while passing through the second heat exchanger 730 and some cooling water is evaporated and discharged out of the emergency cooling water storage part 750 through the opening part 751.

Referring to the right side of FIG. 7B, the cooling water storage unit 710 maintains an equilibrium state with time after the occurrence of an accident. The fluid in the circulating flow path maintains the circulating flow. The cooling water in the emergency cooling water storage part 750 continuously evaporates. Circulating flow and evaporation may continue as long as the temperature difference is maintained between the inside and outside of the compartment 72.

FIG. 8A is a conceptual view showing normal operation of the to-be-poured cooling system 800 and the nuclear power plant 80 having the same according to another embodiment of the present invention. FIG. 8B is a conceptual view showing a virtual accident of the to-be-poured cooling system 800 shown in FIG. 8A and the nuclear plant 80 having the same. The left side of FIG. 8B shows the beginning of an accident when a virtual accident occurs in the nuclear power plant 80, and the right side of FIG. 8B shows the middle or late of the accident.

In this embodiment, the pressure equalizing pipe 870 is provided with the check valve 872 as well as the isolation valve 871. The check valve 872 is made to pass only the flow in one direction and to block the flow in the opposite direction. Accordingly, when the compartment 82 is at a higher pressure than the cooling water storage 810, the atmosphere inside the compartment can pass through the check valve 872 and into the interior of the cooling water storage 810. On the contrary, when the cooling water storage portion 810 is at a higher pressure than the storage portion 82, the atmosphere inside the cooling water storage portion 810 is blocked by the check valve 872 and can be discharged to the inside of the storage portion 82 none.

Referring to the left side of FIG. 8B, as the pressure inside the compartment 82 rises, the atmosphere inside the compartment 82 flows into the cooling water storage 810 through the pressure equalizing pipe 870. When the pressure of the cooling water storage portion 810 rises above the reference pressure, the cooling water is supplied to the first heat exchanger 820 and circulated in the circulation flow passage. Non-condensable gases or vapors are introduced into the cooling water reservoir 810 via the discharge line 880.

Referring to the right side of FIG. 8B, the pressure rise of the chamber 82 is suppressed by the operation of the matched cooling system 800 after occurrence of an accident. However, the atmosphere of the cooling water storage portion 810 is blocked by the check valve 872 and is not discharged into the storage portion 82, and the cooling water storage portion 810 maintains the high pressure state at the initial stage of the accident. The cooling water is no longer supplied from the cooling water storage portion 810 to the first heat exchanger 820 and the inside of the connection pipe 840 is maintained in an equilibrium state. The fluid in the circulating flow path maintains the circulating flow.

FIG. 9A is a conceptual view showing normal operation of the to-be-poured cooling system 900 and the nuclear power plant 90 having the same according to another embodiment of the present invention. FIG. 9B is a conceptual view showing a virtual accident of the to-be-poured cooling system 900 shown in FIG. 9A and the nuclear power plant 90 having the same. The left side of FIG. 9B shows the beginning of an accident when a virtual accident occurs in the nuclear power plant 90, and the right side of FIG. 9B shows the middle or late of the accident.

In this embodiment, the cooling water storage portion 910 is installed higher than the uppermost portion of the circulation flow path including the first heat exchanger 920, the second heat exchanger 930, and the circulation pipe 960. Phase cooling water circulates in the circulation flow path. In the case of using the phase change, circulation flow due to evaporation occurs when the temperature inside the compartment 92 is maintained at a high temperature (atmospheric pressure: 100 ° C or more), but when the single phase flow phenomenon is used, The circulating flow can be formed.

9B, as the pressure inside the compartment 92 rises, the atmosphere inside the compartment 92 flows into the cooling water storage 910 through the pressure equalization pipe 970. As shown in FIG. When the pressure of the cooling water storage portion 910 rises above the reference pressure, the cooling water is supplied to the circulating flow path including the first heat exchanger 920, the second heat exchanger 930 and the circulation pipe 960, Fill continuously. Non-condensable gases or vapors are introduced into the cooling water reservoir 910 through the discharge line 980. [

Referring to the right side of FIG. 9B, the pressure rise of the compartment 92 is suppressed by the operation of the matched cooling system 900 after occurrence of an accident. The cooling water is continuously supplied from the cooling water storage portion 910 and the circulation flow path is filled with the cooling water. As time passes after the accident, the cooling water is no longer supplied to the first heat exchanger 920 from the cooling water storage portion 910, and the inside of the connection pipe 940 maintains an equilibrium state. The cooling water in the circulation channel maintains the circulating flow.

The present invention is formed such that cooling water does not flow into the circulation flow path formed by the first heat exchanger, the second heat exchanger, and the circulation pipe during normal operation of the nuclear power plant. Therefore, it is possible to prevent the occurrence of problems such as internal corrosion or contamination of the circulation channel by the cooling water. Further, the maintenance work of the circulation flow path becomes easier.

Further, the present invention is a passive-type equipment formed to utilize natural forces. The present invention starts operation when the pressure of the storage portion rises above the reference pressure even though there is no separate operation signal. Therefore, the present invention has a very low probability of malfunction and high reliability of the system.

It should be noted that the above-described equivalent payload cooling system and the nuclear power plant having the same are not limited to the configuration and the method of the embodiments described above, but the embodiments may be modified so that all or some of the embodiments are selectively And may be configured in combination.

10: Nuclear reactor 11: Reactor coolant system
12: Palletizing part 100: Pelletizing part cooling system
110: cooling water storage unit 120: first heat exchanger
130: Second heat exchanger 140: Connection piping
150: Emergency cooling water storage unit 160: Circulation piping
170: pressure equalization piping 180: discharge piping

Claims (14)

A cooling water storage unit configured to store cooling water therein;
Wherein when the pressure inside the compartment rises above a reference pressure, the refrigerant is supplied to the inside of the compartment by heat exchange of the cooling water supplied from the compartment, A first heat exchanger and a second heat exchanger for suppressing a pressure rise inside the compartment; And
Wherein one end is inserted into the cooling water storage portion through the upper portion of the cooling water storage portion and the other end is inserted into the circulation flow passage so that the cooling water in the cooling water storage portion is supplied to the circulation flow passage when the pressure of the storage portion rises above the reference pressure And a connection piping to be connected. The method according to claim 1,
The connection piping includes:
An upward flow path portion extending to a predetermined height so as to prevent a flow of cooling water from the cooling water storage portion in a normal operating pressure range of the nuclear power plant; And
When the pressure of the storage portion rises above the reference pressure and the flow of the cooling water is formed to be higher than the height of the rising passage portion, And a descending flow path portion extending from the upper surface of the lower portion of the lower surface of the lower surface of the lower surface portion. The method according to claim 1,
A pressure equalizing pipe extending from the cooling water storage part to the internal space of the compartment and providing a flow path for introducing the atmosphere inside the compartment to the cooling water storage part so as to form a pressure balance between the compartment part and the cooling water storage part Characterized in that the cooling system comprises a cooling system. The method according to claim 1,
Wherein the first heat exchanger is installed in an internal space of the compartment and is configured to heat-exchange the cooling water supplied through the connection pipe with an atmosphere inside the compartment in the event of an accident. The method according to claim 1,
Wherein the second heat exchanger is installed outside the compartment and is configured to remove heat from the fluid transferred from the first heat exchanger. The method according to claim 1,
Further comprising an emergency cooling water storage part formed to store cooling water inside the storage part and installed outside the storage part,
The second heat exchanger is arranged so that at least a portion thereof is immersed in the cooling water stored in the emergency cooling water storage portion,
Wherein the emergency cooling water storage part evaporates the cooling water inside and discharges heat transferred from the second heat exchanger to the outside. The method according to claim 6,
The second heat exchanger may include a flow path extending at least partially to a position higher than the level of the emergency cooling water storage part and passing the cooling water of the emergency cooling water storage part, Respectively, of the first and second cooling units. The method according to claim 1,
The circulation piping includes:
A first circulation pipe connected to an upper portion of the first heat exchanger and an upper portion of the second heat exchanger, respectively, so as to transfer the heated or evaporated fluid to the second heat exchanger while passing through the first heat exchanger; And
And a second circulation pipe connected to a lower portion of the second heat exchanger and a lower portion of the first heat exchanger so as to transfer the cooled or condensed fluid to the first heat exchanger while passing through the second heat exchanger, Cooling system to be matched. 9. The method of claim 8,
Further comprising a discharge pipe branched from the circulation passage to discharge the non-condensable gas inside the circulation passage. 10. The method of claim 9,
The discharge pipe is inserted into the cooling water storage portion to transfer the non-condensable gas to the cooling water storage portion and is immersed in the cooling water,
Further comprising a sparger installed at an end of the discharge pipe to spray the non-condensable gas to the cooling water storage. 10. The method of claim 9,
And the discharge pipe is branched from the first circulation pipe to extend into the internal space of the storage part to discharge the non-condensable gas into the inside of the storage part. The method according to claim 1,
Wherein the cooling water reservoir is installed at a position higher than a lower end of the first heat exchanger to supply cooling water to the circulation flow passage using a siphon phenomenon. The method according to claim 1,
A storage portion piping connected to a lower portion of the cooling water storage portion and the circulation flow passage; And
Further comprising an isolation valve installed in the storage pipe and formed to be openable and closable in case of an accident in case of an accident. Reactor coolant system;
A compartment for enclosing the reactor coolant system to prevent leakage of the radioactive material during an accident;
And a counterbalanced cooling system for preventing a pressure inside the storage compartment from rising due to steam emitted from the reactor coolant system or the secondary system at the time of an accident,
The to-be-matched-bed cooling system includes:
A cooling water storage unit configured to store cooling water therein;
Wherein when the pressure inside the compartment rises above a reference pressure, the refrigerant is supplied to the inside of the compartment by heat exchange of the cooling water supplied from the compartment, A first heat exchanger and a second heat exchanger for suppressing a pressure rise inside the compartment; And
Wherein one end is inserted into the cooling water storage portion through the upper portion of the cooling water storage portion and the other end is inserted into the circulation flow passage so that the cooling water in the cooling water storage portion is supplied to the circulation flow passage when the pressure of the storage portion rises above the reference pressure And a connecting pipe connected thereto.

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