KR101505475B1 - Passive containment cooling system and nuclear power plant having the same - Google Patents

Abstract

The present invention provides a passive containment cooling system which includes a first heat exchanger which is arranged in a containment and reduces pressure in the containment, a second heat exchanger which is arranged outside the containment and transmits fluid to the first heat exchanger after receiving the fluid which is evaporated or heated in the first heat exchanger and cooling or condensing the received fluid, a circulation pipe which is connected to the first heat exchanger and the second heat exchanger to provide a circulation path of the fluid between the first and second heat exchangers by a density difference, and a cooling water supply unit which supplies cooling water to the circulation path. The cooling water supply unit includes a cooling water storage unit which is formed to store the cooling water inside, a connection pipe which includes one end connected to the cooling water storage unit and the other end connected to the circulation path and supplies the cooling water stored in the cooling water storage unit to the circulation path by a siphon phenomenon if the temperature of the containment rises over a reference temperature, and a discharge pipe which is branched from the circulation path, is connected to the cooling water storage unit, and moves non-condensable gas from the circulation path to the cooling water storage unit by a pressure difference generated between the circulation path and the cooling water storage unit.

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 pseudo-pneumatic cooling system and a nuclear power plant having the pseudo-pneumatic cooling system that operate by natural circulation by gravity head and density difference when an accident occurs, and reduce the pressure by condensing the steam inside the compartment.

Nuclear 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. On the other hand, a separate type reactor (eg, domestic pressurized light water reactor) in which main devices (steam generator, pressurizer, pump impeller, etc.) are installed outside the reactor (eg, domestic pressurized light water reactor) Yes, 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 "

Cooling water or steam is discharged from various reactors including integrated reactors due to the occurrence of a coolant loss accident or a steam pipe breakage in the cooling industry of the nuclear power industry (such as the cooling system of the passive containment building or the cooling system of the containment building) It is often used as a system for condensing the steam and cooling the internal atmosphere to maintain the integrity of the compartment when the internal pressure and temperature rise. In the method used for similar purposes to the cooling system, the system uses a suppression tank (a commercial BWR, CAREM: Argentina, IRIS: Westinghouse, USA) which uses a decompression tank (SW1000: France Pramatom ANP, AHWR: India, SBWR: USA GE), which uses a steel containment vessel to cool (spray and air) the outer wall (AP1000: Westinghouse USA) . A shell and tube type heat exchanger or a condenser (SBWR: American GE, etc.) is mainly applied to the compartment cooling system heat exchanger related 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.)

[0001] The present invention relates to an as-dispensed cooling system, which is operated by natural circulation by gravity head and density difference, such as a driven residual heat removal system, and condensing the vapor discharged into the compartment using a heat exchanger, ≪ / RTI >

In connection with the present invention, the compartment cooling system (Korean Patent Registration No. 10-1242746, Korean Patent Registration No. 10-1242743, Korean Patent Registration No. 10-1224023) The valve is exposed to the cooling water, or the valve is opened or the pump is driven according to the operation signal. Accordingly, it is difficult to periodically check the inside of the heat exchanger in which the maintenance work is very difficult in the system in which the inside of the heat exchanger is exposed to the cooling water. In the system operated according to the operating signal, There is a possibility that the system function is lost due to malfunction of the pump or the like.

The present invention is to provide a coinage cooling system and a nuclear power plant having the same, wherein the inside of the heat exchanger is not exposed to cooling water during normal operation of the nuclear power plant.

In addition, the present invention is to provide a counterbalanced cooling system for removing non-condensable gas existing on a circulating flow path of a heat exchanger using natural forces generated in a nuclear accident, and a nuclear power plant having the same.

In addition, the present invention uses a natural force generated at the time of an accident of a nuclear power plant to remove a non-condensable gas existing on a circulating flow path of a heat exchanger, and to prevent the leakage of cooling water in the heat exchanger circulating flow path, And a nuclear power plant having the same.

According to another aspect of the present invention, there is provided a pneumatic dispensing system including a first heat exchanger disposed inside a compartment and lowering a pressure inside the compartment, And a second heat exchanger disposed in the first heat exchanger and adapted to cool or condense the fluid heated or evaporated in the first heat exchanger and transfer the fluid to the first heat exchanger, A circulating pipe connected to the first and second heat exchangers to provide a circulating flow path for the fluid, and a cooling water supply unit for supplying the cooling water to the circulation channel, wherein the cooling water supply unit includes a cooling water supply unit A storage portion, one end connected to the cooling water storage portion, and the other end connected to the circulation flow path, and the temperature inside the storage portion rises above a reference temperature A connection pipe for supplying cooling water stored in the cooling water storage unit to the circulation channel by a siphon phenomenon in a lower surface of the circulation channel and branched from the circulation channel and connected to the cooling water storage unit, And a discharge pipe for moving the non-condensable gas inside the circulation channel to the cooling water storage portion by a pressure difference between the discharge pipe and the discharge pipe.

However, in the present invention, the circulation flow path includes a circulation pipe installed between the first and second heat exchangers, and a flow path on the circulation pipe side of the first and second heat exchangers.

According to an embodiment of the present invention, each of the first and second heat exchangers and the cooling water storage portion is provided with a plurality of cooling water reservoirs, respectively, for preventing the fluid circulating in the cooling water storage portion and the first and second heat exchangers from leaking to the outside. They can be connected to each other in a closed circuit in a closed circuit.

According to another embodiment of the present invention, the cooling water storage unit includes a first compartment formed to store cooling water therein, and a second compartment disposed below the first compartment and connected to the first compartment by the connection pipe, And a second compartment for supplying cooling water to the circulation channel through an injection pipe connected to the circulation channel, wherein the second compartment is formed to receive air in order to increase a pressure difference with the first compartment have.

The to-be-poured cooling system may be configured to discharge the air contained in the second compartment by a pressure difference (water head) when the flow of the cooling water from the first compartment to the second compartment is generated, into the first compartment And a discharge pipe connecting the inside of the first and second compartments.

The cooling water reservoir may be formed such that the first and second compartments are partitioned from each other by a boundary plate so as to constitute the cooling water reservoir in a single tank or a water tank.

According to another embodiment of the present invention, the connection pipe includes a rising passage portion extending to a predetermined height to prevent a flow of cooling water from the cooling water storage portion during normal operation of the nuclear power plant including maintenance, and When the temperature of the compartment rises above the reference temperature and the flow of the cooling water occurs more than the height of the ascending channel portion, the refrigerant is bent in the upward flow path portion to supply the cooling water to the circulation channel by the water head difference, And a downflow channel portion.

According to another embodiment of the present invention, the circulation pipe may include an upper portion of the first heat exchanger and a portion of the second heat exchanger to transfer the heated or evaporated fluid to the second heat exchanger through the first heat exchanger, A first circulation pipe connected to the upper portion of the first heat exchanger, and a second circulation pipe connected to the lower portion of the first heat exchanger and the lower portion of the second heat exchanger to transfer the cooled or condensed fluid flowing in the second heat exchanger to the first heat exchanger, And a second circulation pipe connected to the second circulation pipe.

The discharge pipe may be branched from the circulation flow path and extend into the cooling water storage part so as to transfer non-condensable gas of the circulation flow path to the cooling water storage part.

According to another aspect of the present invention, there is provided a refrigeration system for a refrigerator, comprising: a refrigeration system that is disposed outside the compartment and is configured to store cooling water therein to cool the circulation channel fluid of the second heat exchanger, And the second heat exchanger is arranged to be immersed in at least a part of the second heat exchanger to exchange heat with the circulating flow medium fluid.

The second heat exchanger may include a flow passage for passing the cooling water of the emergency cooling water storage section and a flow passage for passing the outside air so as to be cooled by a mixture of the water-cooling type and the air-cooling type.

According to another embodiment of the present invention, the discharge pipe is inserted into the cooling water storage part so that the steam transferred to the cooling water storage part through the discharge pipe can be condensed by the cooling water, And a sparger disposed at an end immersed in the cooling water to spray the steam.

According to another embodiment of the present invention, the cooling water reservoir is disposed at a lower end of the circulation channel so that the cooling water can be supplied to the circulation channel by the head of the water when the cooling water flows in the connection pipe by the siphon phenomenon It can be installed in a high position.

According to another embodiment of the present invention, the connection pipe is provided with a connection pipe for selectively supplying the cooling water of the cooling water storage portion to the first heat exchanger during normal operation of the nuclear power plant including maintenance, And may include an isolation valve that opens and closes.

According to another embodiment of the present invention, the to-be-poured cooling system includes an air discharge pipe branched from the discharge pipe and connected to the inside of the storage unit, and an air discharge valve Wherein the atmospheric release valve is opened to communicate with the inside of the compartment when the pressure inside the circulation passage rises above a reference pressure to release the non-condensable gas, It may be sealed so as to be intercepted from the inside of the compartment.

According to another embodiment of the present invention, the second heat exchanger may include a flow passage for passing outside air so as to cool the circulation flow fluid in an air-cooling manner.

According to another embodiment of the present invention, the cooling water storage part may be disposed outside the storage part according to a space condition in which the cooling water storage part is installed.

Further, in order to realize the above-mentioned problem, the present invention proposes a nuclear power plant equipped with a coin-driven cooling system. The nuclear power plant includes a reactor coolant system, a compartment for enclosing the reactor coolant system to prevent leakage of the radioactive material during an accident, a cooling water or steam discharged from the reactor coolant system or the secondary system at the time of an accident, And a second heat exchanger disposed inside the compartment and lowering the pressure inside the compartment; a second heat exchanger disposed outside the compartment; A second heat exchanger that receives the fluid heated or evaporated in the first heat exchanger to cool or condense the fluid, and then transfers the fluid to the first heat exchanger, a circulation of the fluid between the first and second heat exchangers A circulation pipe connected to the first and second heat exchangers to provide a flow path, The cooling water supply unit includes a cooling water storage unit configured to store cooling water therein, one end connected to the cooling water storage unit, the other end connected to the circulation flow path, A connection pipe for supplying cooling water stored in the cooling water storage unit to the circulation channel by a siphon phenomenon, and a connection pipe branched from the circulation channel and connected to the cooling water storage unit, And a discharge pipe for moving the non-condensing gas in the circulation channel to the cooling water storage part by a pressure difference generated in the cooling water storage part.

The effect of the coin-driven dispensing cooling system and the nuclear power plant having the same dispensing system according to the present invention will be described below.

According to at least one of the embodiments of the present invention, in the first and second heat exchangers, when air is circulated during normal operation of the nuclear power plant and the temperature inside the compartment rises above the reference temperature, And cooling water is supplied from the storage portion to flow. Accordingly, the time required for the circulating flow path in the first and second heat exchangers to be exposed to the cooling water is reduced, thereby reducing the need for maintenance.

In addition, according to at least one embodiment of the present invention, when the first and second heat exchangers and the cooling water storage portion constituting the to-be-poured cooling system are connected to each other by an open circuit to constitute an open circuit, an excessive pressure rise or an irregular fluctuation It is possible to eliminate the possibility that the fluid of the circulating flow path is lost by the circulating flow path cooling system and the function of the cooling system to be poured can be lowered.

Also, the non-condensable gas present in the circulating flow path of the fluid formed between the first and second heat exchangers is configured to be guided to the upper portion of the cooling water storage portion through the discharge pipe, so that the heat exchange performance of the first and second heat exchangers Can be improved.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1A is a conceptual diagram showing 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 the initial phase of a fictitious accident of a nuclear power plant having the same-poured cooling system shown in FIG. 1A; FIG.
FIG. 1C is a conceptual view showing the second half of a virtual accident of a nuclear power plant having the same-poured cooling system shown in FIG. 1A; FIG.
FIG. 2A is a conceptual view showing a normal operation of a nuclear power plant with a coinage charging system according to another embodiment of the 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 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. 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 with a coinage charging system according to another embodiment of the present invention. FIG.
FIG. 5B is a conceptual diagram showing the initial phase of a fictitious accident of a nuclear power plant having the coinage cooling system shown in FIG. 5A; FIG.
FIG. 5C is a conceptual view showing the second half of a virtual accident of a nuclear power plant having the same-padded cooling system shown in FIG. 5A; FIG.
FIG. 6A is a conceptual diagram showing a normal operation of a nuclear power plant having a coinage cooling 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 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. 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 with a coinage charging system according to 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.
FIG. 10A 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. 10B is a conceptual diagram showing a virtual pour cooling system shown in FIG. 10A and a virtual accident of a nuclear power plant having the same. FIG.
FIG. 11 is a conceptual diagram showing a normal operation of a nuclear power plant with a coinage cooling system according to another embodiment of the present invention. FIG.
FIG. 12 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.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a perspective view of a cooling system of a copper plating system according to an embodiment of the present invention; FIG.

In the present specification, the same reference numerals are given to the same or similar embodiments, and the same reference numerals are given to similar components. As used herein, the singular forms "a", "an" and "the" include plural referents unless the context clearly dictates otherwise.

FIG. 1A is a conceptual diagram illustrating a normal operation of a coinage cooling system 100 and a nuclear power plant 10 having the coinage cooling system 100 according to an embodiment of the present invention. FIG. 1B is a schematic view of the coinage cooling system 100 1C is a conceptual diagram showing a second half of a virtual accident of a coinage cooling system 100 and a nuclear power plant 10 having the coinage system cooling system 100 shown in FIG. 1A . The left side of FIG. 1B shows a time point when a virtual accident occurs in the nuclear power plant 10 and the driven bill cooling system 100 operates. The right side of FIG. 1B shows the initial state of the accident Respectively. The left side of FIG. 1C shows the second half of the accident after the right side of FIG. 1B, and the right side of FIG. 1C shows the second half of the accident after the left side of FIG. 1C.

Referring to FIGS. 1A to 1C, the reactor coolant system 11 is a system for transporting thermal energy generated by nuclear fission of nuclear fuel in the core 11a. The core 11a is installed inside the reactor coolant system 11 and the chamber 12 is installed outside the reactor coolant system 11. [ Various piping 13 for operating the nuclear power plant 10 are connected to the reactor coolant system 11 and isolation valves 13a are installed in the piping 13 and the operation of the nuclear power plant 10 during normal operation is required The pipes are open (see FIG. 1A) and closed by a related signal in the event of an accident of the nuclear power plant 10 (see FIGS. 1B and 1C).

The compartment 12 surrounds the reactor coolant system 11 to prevent leakage of radioactive material during an accident. The compartment 12 is the last means for preventing the radioactive material from leaking 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 is connected to the reactor coolant system 11 or the reactor coolant system 11 by means of cooling water (vaporization) or steam emitted from a piping 13 or a secondary system piping (not shown) So that the pressure inside the pouring portion 12 is prevented from rising.

To this end, the coined-bed cooling system 100 includes a first heat exchanger 110, a second heat exchanger 120, a circulation pipe 130, and a cooling water supply unit 140.

Hereinafter, in the present invention, the circulation conduit 130 and the first and second heat exchangers 110 and 120 on the side of the circulation pipe 130 are collectively referred to as circulation conduits.

The first heat exchanger 110 is disposed inside the compartment 12 so as to lower the pressure inside the compartment 12 when the temperature inside the compartment 12 rises above the reference temperature. In the normal operation of the nuclear power plant 10, the inside of the first heat exchanger 110 is filled with air without cooling water flowing.

The second heat exchanger (120) is disposed outside the compartment (12). The second heat exchanger (120) receives the fluid heated or evaporated by heat exchange in the first heat exchanger (110) to cool or condense the fluid, (110). In the normal operation of the nuclear power plant 10, the inside of the second heat exchanger 120 is filled with air without cooling water flowing.

The dispensing cooling system 100 may further include an emergency cooling water storage unit 190 that receives heat from the second heat exchanger 120 and discharges the heat to the outside. Specifically, the emergency cooling water storage unit 190 is disposed outside the compartment 12, is configured to store cooling water therein, and is disposed so that at least a part of the second heat exchanger 120 is immersed in the cooling water stored therein . Then, the heat is transferred to the second heat exchanger circulation flow steam or the cooling water, and the cooling water stored therein is evaporated and discharged to the outside. The cooling water evaporated in the emergency cooling water storage unit 190 may be discharged to the outside through the opening 191 formed in the emergency cooling water storage unit 190.

The circulation pipe 130 is connected to the first and second heat exchangers 110 and 120, respectively, to provide a circulating flow path for the fluid such as steam or cooling water flowing between the first and second heat exchangers 110 and 120 by the density difference .

Meanwhile, the circulation pipe 130 may include a first circulation pipe 131 and a second circulation pipe 135. The first circulation pipe 131 is connected to the upper portion of the first heat exchanger 110 and the upper portion of the second heat exchanger 110 to transfer the heated or evaporated fluid to the second heat exchanger 120 through the circulation channel of the first heat exchanger 110. [ (Not shown). The second circulation pipe 135 is connected to the lower portion of the second heat exchanger and the first heat exchanger 110 so as to transfer the cooled or condensed fluid to the first heat exchanger 110 through the circulation channel of the second heat exchanger 120 110, respectively. Further, the first and second circulation pipes 131 and 135 may be provided with isolation valves for opening and closing the oil passage during maintenance work or accident, respectively.

Hereinafter, the structure of the cooling water supply unit 140 for supplying cooling water to the first heat exchanger 110 in the event of an accident of the nuclear power plant 10 will be described.

The cooling water supply unit 140 includes a cooling water storage unit 150, a connection pipe 160, and a discharge pipe 170.

The cooling water storage unit 150 is formed to store cooling water therein. In addition, the cooling water storage unit 150 may be formed such that the inner space in which the cooling water is stored is blocked from the outside. In addition, although the cooling water storage part 150 is shown as being disposed inside the storage part 12 in Figs. 1A to 1C, it may be disposed outside the storage part 12. Fig.

When the temperature inside the compartment 12 rises above the reference temperature, the cooling water storage part 150 generates cooling water in the circulation channel by the head of the water when the cooling water flows in the connection pipe 160 by the siphon phenomenon It can be installed at a position higher than the lower end of the circulating flow path.

The cooling water storage unit 150 may include a first compartment 151 and a second compartment 153 that are formed in an isolated form from each other.

The first compartment 151 is formed to store cooling water therein.

The second compartment 153 is disposed below the first compartment 151 and is connected to the inside of the first compartment 151 by the connection pipe 160. The second compartment 153 is connected to the first heat exchanger 110, (156) to the first heat exchanger (110). In addition, the second compartment 153 has a receiving space having a constant volume to receive air therein so as to increase the pressure difference with the first compartment 151.

Specifically, the pressure and the volume have an inverse relationship with each other. Therefore, unlike the first compartment 151 where the internal pressure of the nuclear power plant 10 is increased, the volume of the second compartment 153 is increased to increase the volume of the first compartment 151 and the second compartment 151 153 can be maintained for a long time, so that the cooling water flowing from the first compartment 151 to the second compartment 153 can be smoothly flowed. Hereinafter, the flow mechanism of the cooling water generated by the pressure difference between the first and second compartments 151 and 153 will be described in detail with reference to the description of the connection pipe 160 and the discharge pipe 170.

Further, the coined pay cooling system 100 may further include a discharge pipe 180.

The discharge piping 180 is configured such that when the flow of cooling water from the first compartment 151 to the second compartment 153 occurs, the air discharged from the second compartment 153 by the pressure difference (water head) And the inside of the first and second compartments 151 and 153 are connected to discharge the inside of the first compartment 151. The discharge pipe 180 is installed in the discharge pipe 180 so as to prevent the air inside the first compartment 151 from flowing into the second compartment 153 and transferring the pressure to the inside of the first compartment 151, And a check valve 181 for passing only the flow directed toward the outlet port 182. [ The discharge pipe 180 may be provided with an orifice 182 for controlling the discharge flow rate of air flowing from the inside of the second compartment 153 to the inside of the first compartment 151. The orifice 182 prevents the flow formation through the connecting pipe 160 from being degraded by leakage of the discharge pipe 180 including the check valve 181 in the event of an accident.

In addition, the cooling water storage part 150 may be formed such that the first and second compartments 151 and 153 are partitioned from each other by the boundary plate 155. Specifically, the boundary plate 155 is for realizing the first and second compartments 151 and 153 with a single tank or a water tank, and simplifies the cooling water storage unit 150 and minimizes the space occupied by the cooling water storage unit 150 . The connection pipe 160 may be configured to move the cooling water stored in the cooling water storage unit 150 to the first heat exchanger 110 using a siphon phenomenon. More specifically, the connection pipe 160 may include a rising passage portion 160a and a falling passage portion 160b.

The ascending channel portion 160a is disposed so that at least a part thereof is immersed in the cooling water stored in the first compartment 151 and the cooling water flows into the second compartment 153 during normal operation of the nuclear power plant 10 including maintenance To a predetermined height. Specifically, during normal operation of the nuclear power plant 10, the cooling water storage unit 150 and the circulation flow path maintain a pressure equilibrium state at an atmospheric pressure level with the connection pipe 160 as a boundary. The siphon break phenomenon is maintained by the height difference H of the cooling water and the upper end of the rising passage portion 160a even if the internal temperature of the compartment portion 12 fluctuates within the range below the reference temperature, 160). 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.

When the temperature inside the storage portion 12 rises above the reference temperature and the flow of the cooling water is greater than the height of the upflow channel portion 160a, the downflow channel portion 160b causes the cooling water to flow into the second compartment 153 extending in the downward direction so as to be supplied to the first heat exchanger 110. 1A to 1C, when the cooling water storage portion 160 includes the first and second compartments 151 and 153, the upward flow passage portion 160a and the downward flow passage portion 160b are connected to the first and second compartments 151 and 153, respectively, And is connected to the compartment 151 and the second compartment 153, respectively.

Hereinafter, the structure of the discharge pipe 170 for generating the flow of the cooling water through the connection pipe 160 in the event of an accident of the nuclear power plant 10 will be described.

The discharge pipe 170 moves the non-condensable gas existing in the circulation channel to the cooling water storage part 150 by a pressure difference generated between the circulation channel and the cooling water storage part 150. More specifically, the discharge pipe 170 branches from the circulation pipe 130 and is connected to the cooling water storage part 150. When the pressure of the circulation flow path rises, (150).

When the temperature inside the compartment 12 rises, the temperature and the pressure of the air in the circulation channel rise through the first heat exchanger 110, and the temperature and the pressure are increased through the discharge pipe 170 to the cooling water storage part 150 To the first compartment 151 on the upper side. Accordingly, the temperature and the pressure of the first compartment 151 also increase, and as a result, the water level inside the connection pipe 160 gradually increases. When an accident occurs and the temperature inside the compartment 12 rises above the reference temperature, the pressure inside the first compartment 151 rises due to the air flowing into the inside of the cooling water storage part 160, The siphon brake phenomenon disappears as the water level in the water supply pipe 160 passes over the upward flow path portion 160a and the to-be-poured cooling system 100 starts operating.

The cooling water in the cooling water storage part 150 is supplied to the circulation channel through the connection pipe 160. As the cooling water starts to be supplied to the circulation channel, the heat transfer amount in the first heat exchanger 110 increases and steam starts to be formed. As the steam is formed, the temperature and the pressure of the circulation flow path further rise, and the air and the steam are moved to the first compartment 151 above the cooling water storage part 160 through the discharge pipe 170, Condensed and the air, that is, the non-condensable gas, is received in the upper portion of the first compartment 151. At this time, the supply of the cooling water is continued until a pressure equilibrium state is formed between the cooling water storage part 150 and the circulating flow path.

Meanwhile, the discharge pipe 170 is disposed in the cooling water storage unit so as to be immersed in the cooling water so that the steam delivered to the inside of the cooling water storage unit 150 can be condensed by the cooling water, And a sparger 175 configured to spray steam.

In order to prevent the fluid circulating through the first and second heat exchangers 110 and 120 and the cooling water storage unit 150 from leaking to the outside to be lost, the first and second heat exchangers 110 and 120, The cooling water storage units 110 and 120 and the cooling water storage unit 150 may be connected to each other in a closed circuit in a sealed state from the outside.

The first and second heat exchangers 110 and 120 and the cooling water storage part 150 are connected to each other by a closed circuit so that the first and second heat exchangers 110 and 120 and the cooling water storage part 150, The possibility of leakage of the cooling water other than the limited micro leakage can be greatly reduced and the reliability of the cooling performance of the to-be-poured cooling system 100 can be further improved.

The cooling water storage unit 150 is divided into a first compartment 151 and a second compartment 153. The second compartment 151 is connected directly to the first heat exchanger 110 during normal operation of the nuclear power plant 10, Air is filled in the inside of the first and second heat exchangers 110 and 120 and the cooling water is introduced into the first heat exchanger 110 during normal operation of the nuclear power plant 10, It is possible to further reduce the possibility that the "

During the normal operation of the nuclear power plant 10, the cooling water is stored in the cooling water storage part 150, and cooling water is not supplied to the circulation flow path. That is, since the inside of the circulation channel is filled with air, the maintenance work of the first and second heat exchangers 110 and 120 and the circulation pipe 130 can be more easily performed. In addition, since the heat transfer efficiency of air is relatively lower than the heat transfer efficiency of water, the heat loss through the in-line cooling system 100 during the steady operation of the nuclear power plant 10 is greatly reduced, thereby facilitating management.

Hereinafter, the operation of the to-be-poured cooling system 100 when a nuclear accident occurs in the nuclear power plant 10 will be described.

First, an initial accident of the nuclear power plant 10 is referred to FIG.

When breakage occurs in the piping 13 connected to the reactor coolant system 11, the isolation valves 13a provided in the piping 13 are closed by the related signal. When the steam is discharged into the compartment 12 through the rupturing portion 13b, the temperature and pressure inside the compartment 12 gradually rise. When the temperature inside the compartment 12 rises above the reference temperature, various safety systems installed in the nuclear power plant 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 11 to maintain the level of the reactor coolant system 11. The driven residual heat eliminating system 15 removes the sensible heat of the reactor coolant system 11 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 temperature of the compartment 12 gradually increases, the air inside the circulation channel flows into the cooling water storage part 150 through the discharge pipe 170, and the pressure of the cooling water storage part 150 gradually increases do. The cooling water stored in the cooling water storage part 150 flows into the upflow channel part 160a of the connection pipe 160 and the water level in the upflow channel part 160a gradually increases.

When the temperature inside the compartment 12 rises above the reference temperature, the level of the cooling water rises above the upflow channel portion 160a and the siphon break phenomenon is eliminated. The cooling water is supplied to the circulation channel through the injection pipe 156, and the cooling water stored in the cooling water storage unit 150 is sequentially supplied to the circulation channel by siphon development.

The cooling water supplied to the circulation channel passes through the first heat exchanger 110 and is heat-exchanged with the atmosphere inside the relatively high-temperature compartment 12. The circulating flow medium and the internal atmosphere of the compartment pass through different flow paths of the first heat exchanger 110, and the heat is transferred from the atmosphere to the circulating flow fluid. Since the fluid is ascended or descended by density, the atmosphere that is cooled while passing through the first heat exchanger 110 is lowered, and the fluid (cooling water or cooling water is evaporated) passing through the first heat exchanger 110 Formed steam) rises.

The atmosphere inside the compartment 12 can be cooled and condensed by the heat exchange process in the first heat exchanger 110. A part of the cooling water can be evaporated and the fluid (steam formed by evaporation of the cooling water or the cooling water) flows through the first circulation pipe 131 connected to the upper part of the first heat exchanger 110, Lt; / RTI >

The second heat exchanger 120 shown in Figs. 1A to 1C is formed to realize a water cooling type cooling system. The second heat exchanger (120) is completely immersed in the cooling water of the emergency cooling water storage part (190). The cooling water flowing through the first circulation pipe 131 and the cooling water of the emergency cooling water storage unit 190 pass through the second heat exchanger 120 in opposite directions to each other. The heat is transferred from the fluid circulating in the circulation passage (the cooling water or the vapor formed by evaporating the cooling water) to the cooling water of the emergency cooling water storage section 190. The fluid flowing through the first circulation pipe 131 (the cooling water or the vapor formed by evaporating the cooling water) descends and flows into the cooling water of the emergency cooling water storage unit 190 Lt; / RTI >

The cooled fluid (condensed water in which the cooling water or steam is condensed) in the circulation channel is again transferred to the first heat exchanger 110 through the second circulation pipe 135. Then, the refrigerant passes through the first heat exchanger (110) and exchanges heat with the atmosphere inside the compartment (12). While the temperature gradient is maintained between the fluid inside the circulation channel and the atmosphere inside the chamber 12, the fluid circulates through the circulation channel and repeats the heat exchange process.

The cooling water in the emergency cooling water storage unit 190 receives heat from the second heat exchanger 120 and is heated or evaporated. The emergency cooling water storage unit 190 discharges heat to the environment through the heat of evaporation. Specifically, the cooling water in the emergency cooling water storage portion 190 is evaporated by the temperature rise, and is discharged to the outside through the opening portion 191.

The non-condensable gas or vapor in the circulation channel flows into the cooling water storage unit 150 through the discharge pipe 170 branched from the circulation channel and is injected into the cooling water storage unit 150 through the sparger 175 . The non-condensable gas is collected in the upper space of the cooling water storage part 150, and the steam is condensed and collected in the cooling water storage part 150.

Next, the second half of the accident of the nuclear power plant 10 is referred to FIG.

The water level of the cooling water storage part 150 gradually decreases as the cooling water is supplied to the circulation channel from the cooling water storage part 150 through the second compartment 153 of the connection pipe 160. The cooling water supplied from the cooling water storage part 150 (or the steam formed by evaporating the cooling water) continuously circulates in the circulation flow path. The cooling water supplied to the first heat exchanger 110 (or the vapor formed by evaporating the cooling water) is circulated between the second heat exchanger 120 to lower the temperature inside the chamber 12.

Referring to the left side of FIG. 1C, after passing through a transient in the early stage of the accident, the water level of the cooling water storage part 150 is decreased, and the pressure is balanced between the circulating flow path and the cooling water storage part 150 So that the injection of cooling water from the cooling water storage part 150 is stopped.

Referring to the right side of FIG. 1C, when the pressure balance is changed due to temperature change or leakage of the circulating flow channel after pressure equalization, cooling water is injected from the cooling water storage unit 150 or the cooling water is injected through the discharge pipe 170 The fluid is discharged to the cooling water storage part 150 to form a pressure balance again.

The cooling water existing inside the injection pipe 156 may flow backward but the check valve 158 is provided in the injection pipe 156 to prevent the reverse flow of the cooling water. That is, in the latter half of the accident, the fluid circulates continuously in the circulating flow path of the first heat exchanger 110 and the second heat exchanger 120, thereby lowering the temperature inside the chamber 12.

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 structural 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. Also, a plurality of the coin-driven dispensing cooling systems 100 may be provided.

Hereinafter, other embodiments 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, and FIG. 2B is a conceptual view of the to- ) And a nuclear power plant 20 having the same. 2B shows the initial state in which a virtual accident occurred in the nuclear reactor 20, and the right side of FIG. 2B shows that the cooling water in the cooling water storage part 250 is not normally supplied to the circulation channel in the early stage of the accident And the isolation valve 257b is opened to operate.

Referring to the right side of FIG. 2B, the cooling water storage unit 250 and the injection pipe 256 for connecting the circulation flow passage include a first injection pipe 256a connecting the second compartment 253 and the circulation flow passage, And a second injection pipe 256b connecting the compartment 251 and the circulation channel. If the second injection pipe 256b is not provided with the cooling water through the first injection pipe 256a due to a malfunction or malfunction of the to-be-poured cooling system 200, (257b) can be installed.

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. Accordingly, the present invention can contribute to the overall safety improvement of the nuclear reactor 20.

FIG. 3A is a conceptual diagram showing a 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. 300 and a nuclear power plant 30 having the same. 3B shows the initial state in which a virtual accident occurred in the nuclear power plant 30. In the right side of FIG. 3B, the pressure inside the circulating flow passage rises above the reference pressure in the initial state of the accident, Is opened to release the fluid of the circulation passage into the compartment.

Referring to the right side of FIG. 3B, the to-be-poured cooling system 300 may further include an air discharge pipe 373 and an air discharge valve 374.

The air discharge pipe 373 may be branched from the circulation passage and connected to the inside of the compartment.

The air discharge valve 374 can be installed in the air discharge pipe 373 so as to be openable and closable. When the pressure inside the circulation flow path rises above the reference pressure, the atmosphere release valve 374 opens to communicate with the inside of the compartment 32 to discharge the fluid in the circulation flow path including the non-condensing gas, When the pressure falls below the reference pressure, it can be sealed so as to be intercepted from the inside of the compartment portion 32. Accordingly, the pressure of the closed circuit constituting the to-be-poured cooling system 100 is excessively increased to cause additional accidents or non-condensable gas is not smoothly discharged from the circulating flow path to the cooling water storage part 350, There is an advantage that the performance of the second heat exchangers 310 and 320 can be prevented from deteriorating.

FIG. 4A is a conceptual view showing the 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, and FIG. 4B is a conceptual view of the to- 400 and a nuclear power plant 40 having the same. The left side of FIG. 4B shows the initial state in which the virtual accident occurred in the nuclear power plant 40, and the right side of FIG. 4B shows the air in the second compartment 453 to the left of FIG. And the cooling water is injected from the cooling water storage part 450. [0051] As shown in FIG.

Referring to the right side of FIG. 4B, the second heat exchanger 420 may be provided with a flow passage for passing external air so as to cool or condense the circulation flow fluid in an air-cooling manner. The second heat exchanger 420 supplies the fluid cooled or condensed through the heat exchange with the outside air to the first heat exchanger 410 to heat the inside of the compartment 420 It can be effectively removed. Generally, the air-cooled heat exchanger has a drawback in that heat transfer efficiency is poor and it needs to be constructed in a large capacity. However, since there is no need for an external cooling water source, it can be selectively adopted depending on the size and characteristics of the nuclear power plant.

Hereinafter, the operation of the to-be-poured cooling system 500 implemented as a mixed-type heat exchange system will be described in a time-series sequence.

FIG. 5A is a conceptual view showing the normal operation of the to-be-poured cooling system 500 and the nuclear power plant 50 having the same, according to still another embodiment of the present invention. FIG. 5C is a conceptual diagram showing the second half of the virtual accident of the to-be-poured cooling system 500 shown in FIG. 5A and the nuclear power plant 50 having the same, to be. The left side of FIG. 5B shows a time point when a fictitious accident occurs in the nuclear power plant 50 and the driven poultice cooling system 500 operates, and the right side of FIG. 5B shows the initial state of the incident following the left side of FIG. Respectively. The left side of FIG. 5C shows the second half of the accident after the right side of FIG. 5B, and the right side of FIG. 5C shows the second half of the accident after the left side of FIG. 5C.

Referring to the left side of FIG. 5B, the temperature and the pressure inside the compartment 52 rise as the steam is released from the breaking portion 53b. As the temperature and pressure of the compartment 52 gradually increase, the air inside the circulation channel flows into the inside of the cooling water storage unit 550 through the discharge pipe 570, and the pressure of the cooling water storage unit 550 gradually increases . When the pressure of the cooling water storage portion 550 rises above the reference pressure, the cooling water stored in the first compartment 551 of the cooling water storage portion 510 is supplied to the circulation channel through the second compartment 553.

In the first heat exchanger (510), the circulating flow path fluid and the atmosphere (steam and air) inside the compartment (52) exchange heat. The fluid that has been heated while passing through the first heat exchanger 510 (steam formed by evaporating cooling water or cooling water) is transferred to the second heat exchanger 520 through the first circulation pipe 531.

A part of the second heat exchanger 520 is immersed in the cooling water of the emergency cooling water storage part 590, and the remainder is exposed to the air. The second heat exchanger (520) 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 531. The second flow path is a passage through which cooling water in the emergency cooling water storage section 590 passes. 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. Heat is transferred from the fluid supplied from the first circulation pipe 531 to air or steam, and the second heat exchanger 520 implements an air-cooling type heat exchange method. Also, the heat is transferred from the fluid supplied from the first circulation pipe 531 to the cooling water of the emergency cooling water storage unit 590, and the second heat exchanger 520 implements a water-cooling type heat exchange method.

The heat exchange mode of the second heat exchanger 520 may be changed according to the progress of the accident. Referring to the left side of FIG. 5B, in the second heat exchanger 520, a water-cooling type heat exchange system is dominant. Referring to the right side of FIG. 5B, the cooling water in the cooling water storage portion 550 is supplied to the circulation channel as time elapses after the occurrence of the accident, and the cooling water in the emergency cooling water storage portion 590 evaporates after the temperature rises, do. However, in the second heat exchanger 520, the water-cooling type and the air-cooling type heat exchange method are used at the same time (mixed type) as in the initial stage of the accident occurrence (left side of FIG. 5B).

Referring to the left side of FIG. 5C, the water level of the emergency cooling water storage portion 590 further decreases. Then, while the water level gradually decreases, the dominant heat exchange method in the second heat exchanger 520 gradually changes from the water-cooling type to the air-cooling type.

Finally, referring to the right side of FIG. 5C, the cooling water in the emergency cooling water storage portion 590

Completely evaporated and exhausted, and in the second heat exchanger 520, only the air-cooling type heat exchange system is utilized

do. If the cooling water is replenished into the emergency cooling water storage portion 590, the heat exchange method of the second heat exchanger 520 may be changed to the water cooling type or the mixed type again. In the to-be-poured cooling system 500 shown in the left side of FIG. 5C, the cooling water storage unit 550 and the first heat exchanger 510 maintain a pressure balance state.

Referring to the right side of FIG. 5C, when pressure balance is changed due to temperature change or leakage of the circulating flow channel after pressure equalization, cooling water is injected from the cooling water storage unit 550 or the cooling water is supplied through the discharge pipe 570 Is discharged to the cooling water storage part (550) to form a pressure balance again.

FIG. 6A is a conceptual diagram showing a normal operation of the to-be-poured cooling system 600 and a nuclear power plant 60 having the same, according to still another embodiment of the present invention. FIG. 600 and a nuclear power plant 60 equipped with the same. The left side of FIG. 6B shows the initial state in which a virtual accident occurred in the nuclear reactor 60, and the right side of FIG. 6B shows the air in the second compartment 653 after the left side of FIG. And then the cooling water is injected from the cooling water storage unit 650. [

Referring to the right side of FIG. 6B, the cooling water storage part 650 is formed in the form of a storage tank, and is disposed inside the storage part 62. The storage water tank 650 may be formed in a form blocked from the inside of the compartment 62, as shown in Figs. 6A and 6B.

FIG. 7A is a conceptual view showing the normal operation of the to-be-poured cooling system 700 and the nuclear power plant 70 having the same, according to still another embodiment of the present invention, and FIG. 700 and a nuclear power plant 70 having the same. The left side of FIG. 7B shows the initial state in which a virtual accident occurred in the nuclear power plant 70, and the right side of FIG. 7B shows the air in the second compartment 753 on the left side of FIG. And the cooling water is injected from the cooling water storage unit 750. [0051] As shown in FIG.

In this embodiment, the cooling water storage part 750 is installed outside the storage part 72.

7A or 7B, the cooling water storage unit 750 may be disposed outside the compartment 72 according to the spatial condition of the nuclear power plant 70. [ Accordingly, the space condition of the inside of the compartment 72 and the cooling water storage unit 750 can be alleviated. The operation process is similar to the process described above.

FIG. 8A is a conceptual diagram showing a normal operation state of a to-be-poured cooling system 800 and a nuclear power plant 80 having the same, according to still another embodiment of the present invention, and FIG. 800) and a nuclear power plant (80) having the same. 8B shows the initial state in which a virtual accident occurred in the nuclear power plant 80. In the right side of FIG. 8B, the air in the second compartment 853 follows the left side of FIG. 8B into the first compartment 851 And the cooling water is injected from the cooling water storage part 850. [

8A or 8B, at least a part of the connection pipe 860 may be formed so as to protrude into the inner space of the compartment 82. For example, the upflow channel portion 860a of the connection pipe 860 is formed so that at least a part of the upflow channel portion 860a of the connection pipe 860 is immersed in the cooling water stored in the first compartment 851 of the cooling water storage portion 850, The flow path portion 860b may be formed so as to protrude from the inner space of the compartment portion 82 and be connected to the inside of the second compartment 853.

The discharge pipe 880 for discharging the air in the second compartment 853 to the inside of the first compartment 851 when the flow of the cooling water occurs through the connection pipe 860 is connected to the compartment 82 And may be connected to the first compartment 851 and the second compartment 853, respectively. The operation process is similar to the process described above.

FIG. 9A is a conceptual view showing a normal operation state of a to-be-poured cooling system 900 and a nuclear power plant 90 having the same, according to another embodiment of the present invention. FIG. 900 and a nuclear power plant 90 having the same. The left side of FIG. 9B shows the initial state in which a virtual accident occurred in the nuclear power plant 90, and the right side of FIG. 9B shows the air in the second compartment 453 to the left of FIG. And the cooling water is injected from the cooling water storage part 450. [0051] As shown in FIG.

Referring to FIG. 9A or 9B, the first compartment 951 and the second compartment 953 constituting the cooling water storage 950 may be formed separately from each other, rather than being integrally formed. This structure facilitates detection of leakage of cooling water generated by cracks or the like at the boundary between the first compartment 951 and the second compartment 953, and at the same time, Can be performed more effectively. The first compartment 951 and the second compartment 953 are further reliably isolated to more reliably block the inflow of cooling water into the first and second heat exchangers 910 and 920 during normal operation of the nuclear reactor 90 There is an advantage that can be made. The operation process is similar to the process described above.

FIG. 10A is a conceptual view showing a normal operation of the to-be-poured cooling system 1000 and the nuclear power plants 1-10 having the same according to still another embodiment of the present invention, System 1000 and a nuclear power plant 1-10 equipped with the system 1000. FIG. The left side of FIG. 10B is a view showing a state of the initial state where a virtual accident occurred in the nuclear power plants 1-10, and the right side of FIG. 10B is a left side of FIG. 10B, FIG.

In the present embodiment, the inside of the cooling water storage portion 1050 is integrally formed without a separate space.

10A or 10B, the connection pipe 1060 is connected to the connection pipe 1060 so as to prevent the cooling water in the cooling water storage portion 1050 from flowing into the circulation channel during normal operation of the nuclear power plants 1-10 including maintenance, And an isolation valve 1057 for selectively opening and closing the flow path of the fuel cell 1060.

One end of the connection pipe 1060 is connected to the cooling water storage portion 1050, and the other end is connected to the circulation channel. The first and second heat exchangers 1010 and 1020 and the cooling water storage unit 1050 are formed of a closed circuit and air in the circulation flow path is delivered to the inside of the cooling water storage unit 1050 through the discharge pipe 1070 Accordingly, the flow of the cooling water occurs through the connection pipe 1060, and the cooling water is supplied to the circulation channel by the flow.

It is possible to replace the function of the second compartment 153 (see FIG. 1A) which provides a smooth flow to the connection piping 1060 in the event of an accident when the connection piping 1060 to the check valve 1058 has sufficient internal space have.

FIG. 11 is a conceptual diagram showing a normal operation of the to-be-poured cooling system 1100 and the nuclear power plant 1 - 20 having the same according to another embodiment of the present invention.

11, the connection pipe 1160 may include an upper air inflow pipe 1161 extending from a bending portion bent and connected to the upflow channel portion 1160a and the downflow channel portion 1160b. A flow is formed in the flow path leading from the ascending channel portion 1160a to the descending channel portion 1160b in the upper air inflow pipe 1161 due to malfunction during normal operation of the nuclear power plant 1-20, And may include an air inflow pipe isolation valve 1162 that opens the connection pipe 1160 to draw the atmosphere inside the compartment 1-22.

When the air inflow pipe isolation valve 1162 is opened, air is injected into the upper portion of the connection pipe 1160 to block the flow caused by the siphon phenomenon, thereby blocking the flow of the cooling water. In addition, the air inflow pipe isolation valve 1162 is opened during normal maintenance work on the to-be-poured cooling system 1100 or the nuclear plant 1-20 to prevent malfunction of the to-be-poured cooling system 1100 .

FIG. 12 is a conceptual diagram showing a normal operation of a to-be-poured cooling system 1200 and a nuclear power plant 1-30 having the same according to another embodiment of the present invention.

Referring to FIG. 12, the cooling water storage portion 1250 may be disposed at a higher position than the first and second heat exchangers 1210 and 1220. The cooling water cooled in the second heat exchanger 1220 is supplied to the lower portion of the first heat exchanger 1210 and the cooling water heated in the first heat exchanger 1210 is supplied to the lower portion of the second heat exchanger 1220. [ And the flow of the circulating flow medium circulating through the first and second heat exchangers 1210 and 1220 may be a single phase flow.

However, the scope of the present invention is not limited to the configuration and method of the embodiments described above, and all or some of the embodiments may be selectively combined so that various modifications may be made to the embodiments. In addition, the present invention can be applied to all equivalents of inventions, such as inventions that can be modified, added, deleted, or replaced at the level of those skilled in the art, It belongs to the scope is self-evident.

100: Plunging cooling system 110: First heat exchanger
120: second heat exchanger 130: circulation pipe
140: Cooling water supply part 150: Cooling water storage part
160: connection piping 170: discharge piping
180: exhaust pipe 190: emergency cooling water storage part

Claims (17)

A first heat exchanger disposed inside the compartment to lower the pressure inside the compartment;
A second heat exchanger disposed outside the compartment and receiving or circulating the fluid heated or evaporated in the first heat exchanger to cool or condense the fluid and transfer the fluid to the first heat exchanger;
A circulation conduit connected to the first and second heat exchangers, respectively, to provide a circulation flow of fluid between the first and second heat exchangers by a density difference; And
And a cooling water supply unit for supplying cooling water to the circulation channel,
The cooling water supply unit
A cooling water storage unit configured to store cooling water therein;
The cooling water stored in the cooling water storage part is discharged from the circulation flow path by a siphon phenomenon when the temperature inside the storage part rises above a reference temperature, A connecting pipe for supplying the water to the water tank; And
And a discharge pipe branched from the circulation channel and connected to the cooling water storage unit and moving the non-condensable gas inside the circulation channel to the cooling water storage unit by a pressure difference generated between the circulation channel and the cooling water storage unit Cooling system to be matched. The method according to claim 1,
The first and second heat exchangers and the cooling water storage part are respectively connected to each other by a closed circuit (not shown) in a sealed state from the outside so as to prevent the fluid circulating in the cooling water storage part and the first and second heat exchangers from leaking to the outside, ) Connected to each other. The method according to claim 1,
The cooling water storage unit
A first compartment formed to store cooling water therein; And
And a second compartment disposed below the first compartment and connected to the first compartment by the connection pipe and supplying cooling water to the circulation channel through an injection pipe connected to the circulation channel,
Wherein the second compartment is configured to receive air therein to increase the pressure differential with the first compartment. The method of claim 3,
A discharge port for discharging the air contained in the second compartment to the inside of the first compartment by a pressure difference when the flow of the cooling water from the first compartment to the second compartment is generated, Plumbing cooling system further comprising piping. 5. The method of claim 4,
Wherein the cooling water reservoir is formed such that the first and second compartments are partitioned from each other by a boundary plate so as to constitute the cooling water reservoir in the form of a single tank or a water tank. 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 during normal operation of the nuclear power plant including maintenance; And
When the temperature of the storage compartment rises above the reference temperature and the cooling water flows more than the height of the rising passage portion, the cooling water is bended in the upward passage portion to supply the cooling water to the circulation passage by the water head difference, And a downflow conduit extending from the lower conduit. 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 through the first heat exchanger to the second 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 flowing into the second heat exchanger to the first heat exchanger, Payment cooling system. 8. The method of claim 7,
Wherein the discharge pipe is branched from the circulation flow passage and extends into the cooling water storage portion so as to transfer non-condensable gas of the circulation passage to the cooling water storage portion. The method according to claim 1,
A second heat exchanger disposed outside the compartment and configured to store cooling water therein so as to cool the circulation flow fluid of the second heat exchanger and at least a part of the second heat exchanger is immersed in the cooling water stored therein And the second heat exchanger is heat-exchanged with the circulation channel fluid. 10. The method of claim 9,
Wherein the second heat exchanger is provided with a flow passage for passing the cooling water of the emergency cooling water storage section and a flow passage for passing the outside air so that the second heat exchanger is cooled by a mixture of the water cooling type and the air cooling type. The method according to claim 1,
The discharge piping is installed in the cooling water storage section so as to be immersed in the cooling water inserted in the cooling water storage section so that the steam transferred to the cooling water storage section through the discharge pipe can be condensed by the cooling water, An equivalence cooling system comprising a sparger that sprays steam. The method according to claim 1,
Wherein the cooling water storage unit is installed at a position higher than a lower end of the circulation flow channel so that cooling water can be supplied to the circulation flow channel by the head of the water when the flow of the cooling water is generated in the connection pipe by the siphon phenomenon, Payment cooling system. The method according to claim 1,
Wherein the connection pipe includes an isolation valve for selectively opening and closing the flow path of the connection pipe so as to prevent the cooling water of the cooling water storage part from flowing into the circulation flow path during normal operation of the nuclear power plant including maintenance, Cooling system. The method according to claim 1,
An air discharge pipe branched from the discharge pipe and connected to the inside of the compartment; And
Further comprising an atmospheric release valve that is openably and closably provided in the atmospheric release pipe,
Wherein the atmospheric release valve comprises:
When the pressure inside the circulating flow passage rises above a reference pressure, opens to communicate with the inside of the compartment, discharges the non-condensing gas,
And is sealed to be intercepted from the inside of the compartment when the pressure inside the compartment falls below a reference pressure. The method according to claim 1,
Wherein the second heat exchanger includes a flow passage for passing outside air so as to cool the circulation flow fluid in an air-cooling manner. The method according to claim 1,
Wherein the cooling water storage unit is disposed outside the compartment according to a space condition in which the cooling water storage unit is installed. Reactor coolant system;
A compartment for enclosing said reactor coolant system to prevent leakage of radioactive material during an accident;
And a counterbalanced cooling system for preventing the pressure inside the storage compartment from rising due to cooling water or 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 first heat exchanger disposed inside the compartment to lower the pressure inside the compartment;
A second heat exchanger disposed outside the compartment and receiving or circulating the fluid heated or evaporated in the first heat exchanger to cool or condense the fluid and transfer the fluid to the first heat exchanger;
A circulation conduit connected to the first and second heat exchangers, respectively, to provide a circulation flow of fluid between the first and second heat exchangers by a density difference; And
And a cooling water supply unit for supplying cooling water to the circulation channel,
The cooling water supply unit
A cooling water storage unit configured to store cooling water therein;
The cooling water stored in the cooling water storage part is discharged from the circulation flow path by a siphon phenomenon when the temperature inside the storage part rises above a reference temperature, A connecting pipe for supplying the water to the water tank; And
And a discharge pipe branched from the circulation channel and connected to the cooling water storage unit and moving the non-condensable gas inside the circulation channel to the cooling water storage unit by a pressure difference generated between the circulation channel and the cooling water storage unit Nuclear power plant.

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