KR101892550B1 - Nuclear power plant having intermediate heat sink cooling device - Google Patents

Abstract

The present invention relates to a refrigerator comprising: a cooling water storage portion disposed inside a compartment, configured to store a cooling water for suppressing a pressure increase inside the compartment and for removing heat; A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel; And a cooling water discharge unit connected to the cooling water storage unit and the spent fuel storage unit to receive high temperature cooling water from the cooling water storage unit and the spent fuel storage unit by natural circulation, And an external cooling water storage part for supplying cooling water of low temperature to the cooling water storage part and the spent fuel storage part.

Description

BACKGROUND OF THE INVENTION 1. Field of the Invention [0001] The present invention relates to a nuclear thermal power plant,

The present invention relates to a nuclear power plant having cooling facilities for intermediate thermal deposition.

A nuclear reactor is a separate reactor (eg commercial reactor: domestic) in which major equipment (steam generator, pressurizer, pump, etc.) is installed outside the reactor vessel depending on the installation position of the main equipment Yes, SMART reactor: Domestic).

In addition, reactors are divided into active reactors and passive reactors depending on how safety systems are implemented. An active reactor is a reactor that uses active equipment such as a pump operated by an electric power such as an emergency generator to drive the safety system. The passive reactor is operated by gravity or gas pressure to drive the safety system It is a reactor that uses passive devices. Passive safety systems in passive reactors are built into the system without an AC source of safety grade, such as an operator action or emergency diesel generator, for more than the time (72 hours) required by regulatory requirements in the event of an accident. It is a system in which the safety system maintains the nuclear reactor safely with only the natural force and after 72 hours, the safety system can be assisted by the operator measures or the non-safety system.

The containment structure (containment buildings, reactor buildings, containment vessels, safety protection vessels, etc.) serving as the final barrier to prevent leakage of radioactive materials from the reactor to the external environment is made of reinforced concrete according to the material constituting the pressure boundary. It is divided into a building (or reactor building) and a containment vessel consisting of steel containers and a safety protection vessel. The containment vessel is a large vessel designed to be low pressure like a containment building, and the safety vessel is a small vessel designed to be small by increasing the design pressure.

Various types of active and passive systems such as a compartment sprinkler system, a compartment cooling system, a decompression tank or a decompression tank are used to reduce the pressure and temperature inside the compartment and the concentration of the radioactive material.

In the event of an accident, a large amount of cooling water is pumped by a pump in case of an accident, and the cooling water is recovered by an internal recharge water tank or pump, The temperature, and the concentration of the radioactive material. The Active Spillage Sprinkler System is capable of long term water spill function, but it must be able to use the power system for pump and pump drive.

(CANDU Canada, etc.) system has a cooling water storage tank on the upper part of the compartment, and discharges a large amount of cooling water in case of an accident, thereby lowering the pressure, temperature and concentration of the radioactive material inside the compartment. The passive sprinkler system has a characteristic that it can not operate for a certain period of time because of the limitation of the storage capacity of the cooling water. Therefore, in order to use the passive sprinkler system for a long time, there is a characteristic that the power system for the pump and the pump must be available since the cooling water storage tank must be supplemented periodically by using the pump.

The decompression tank (suppression tank, commercial BWR, CAREM: Argentina, IRIS: Westinghouse Inc.) system uses the pressure difference in the compartment and the decompression tank to direct the vapor discharged into the compartment to the decompression tank, And functions to lower the pressure, temperature and concentration of radioactive material inside the compartment. The decompression tank system operates only until the pressure inside the compartment is higher than the pressure inside the decompression tank.

In the cooling system of the equipotential cooling system, the heat exchanger and the cooling water tank are installed inside or outside the containment vessel, and the steam inside the containment vessel is condensed by using the heat exchanger to lower the pressure, temperature and radioactive substance concentration inside the compartment do. As compared with the active sprinkler system, the cooling system of the coin-driven dispensing system uses the natural circulation inside the compartment, and the pressure, temperature, and radioactive material abatement capacity are relatively reduced.

In addition, as a part of the cooling system of the equipotential cooling system, a steel containment vessel is applied, the outer wall is cooled (sprayed and aired), the steam inside the containment vessel is condensed on the inner wall of the containment vessel and the pressure, temperature and concentration (AP1000: Westinghouse). This method has the characteristic that the pressure, temperature and radioactive material abatement ability are relatively reduced as compared with the active sprinkling system because natural circulation inside the compartment is used in the same manner as the dispensary dispensing cooling system.

Most of these systems have very good performance in reducing the pressure and temperature inside the containment vessel. However, the radioactive material that can maximize the diffusion of radioactive material to the external environment during a nuclear accident is iodine and iodine is mostly dissolved when it comes in contact with water (solubility 0.029g / 100g (20 ℃)). Therefore, the best performance for lowering the concentration of internal radioactive materials in the compartmental safety system is that the active pump, which has the largest contact area with water, is used to spray a large amount of cooling water and recirculate the cooling water for a long time Active pour water sprinkling system (domestic commercial reactor adoption system).

On the other hand, the radioactive iodine dissolved in the cooling water is collected in the water storage tank of the storage portion and exists in the form of anion. However, the amount of radioactive iodine is greatly increased when the pH of the dissolved cooling water is low. This is because when the pH is less than 7, the amount of dissolved radioactive iodine converted into the volatile iodine (I2) is greatly increased. In addition, the amount of conversion to small-size iodine is related to the temperature of the dissolved cooling water and the iodine concentration in the solution. The converted small iodine is re-volatilized into the atmosphere according to the separation factor defined by the iodine concentration in the cooling water and the iodine concentration in the atmosphere. On the other hand, according to the related regulation requirements, when the pH of the dissolution cooling water is 7.0 or more, the amount of conversion is drastically reduced and the re-volatilization can be ignored. In general, trisodium phosphate is widely used for pH control.

On the other hand, in the active safety system, emergency AC power must be supplied in order to operate active devices such as a pump in case of a nuclear accident, so that there is a growing demand for a passive safety system with relatively high safety. However, in general, the active safety system that can consume a large amount of water is superior to the radioactive material reduction performance in case of a nuclear accident. Therefore, when the passive safety system is adopted as a safety system for the storage part, . For the safety of the general public, the Exclusion Area Boundary (EAB) is established and the residence of the general public is limited by assuming a nuclear accident. Therefore, safety of the nuclear power plant can be relatively increased when the passive safety system is applied compared to the active safety system. However, it is necessary to secure a relatively limited EAB in case of a nuclear accident . Expansion of the restricted area boundary can result in a disadvantage of significantly increasing the construction cost of the nuclear power plant.

Accordingly, a large water tank or a tank (similar to a conventional reservoir built-in water storage tank) is provided in the inside of the compartment, and a radioactive material abatement facility capable of realizing a low pressure design is provided. A radioactive material abatement facility has been proposed in which most of the radioactive material, except for some limited leakage from the system, is injected into the large water tank through the injection part of the abatement facility. (Korean Patent No. 10-1538932) In the prior art, a low-pressure boundary is formed so as to surround the outside of the reactor coolant system, and the inside of the reduction facility and the inside of the compartment are connected to the lower portion of the large water tank , Thereby improving the radioactive material abatement capacity. However, in the conventional technology related to the radioactive material abatement facility, detailed information on the final heat sink is not presented.

On the other hand, the passive residual heat removal system performs an important function of removing the residual heat released from the reactor core and the sensible heat of the reactor coolant system by operating in the event of an accident. The cooling water circulation system of the passive residual heat removal system is a system of cooling the reactor by directly circulating the reactor primary cooling water (AP1000: Westinghouse, USA) and a method of cooling the reactor by circulating the secondary cooling water by using the steam generator : Republic of Korea) are mainly used, and a method of directly condensing the primary cooling water into the tank (CAREM: Argentina) is partially used.

In the case of using the secondary cooling water circulation system, the pressurized supplementary tank is applied and the steam piping and the water supply pipe of the passive residual heat removal system in the normal operation are separated from each other by the isolation valve (Korean Patent Laid-Open Publication No. 2002-0037105 ) And gravity water supplemen- tary tanks are used, and only one direction of the drain of the passive residual heat removal system is isolated by isolation valves (IRIS: US Westinghouse, SMART Reactor: Republic of Korea).

Cooling the outside of the heat exchanger (condensation heat exchanger) in the passive residual heat removal system includes water-cooled (AP1000) and air-cooled (WWER 1000: Russia) And a hybrid-IMR (Japan) system is used. The heat exchanger of the passive residual heat removal system transfers the heat transferred from the reactor to the outside (atmosphere) through an emergency cooling tank (heat sink) or the like. In the heat exchanger system, the condensation heat Exchange system is widely used.

Generally, an emergency cooling water storage system is installed in the water-cooling type residual heat removal system. When the driven residual heat removal system receives heat from the driven residual heat removal system during operation, the temperature of the cooling water in the emergency cooling water storage portion rises and then evaporates. . However, since the capacity of the emergency cooling water storage portion is limited, the cooling water in the emergency cooling water storage portion should be replenished periodically if the cooling water is insufficient.

On the other hand, the nuclear fuel generates residual heat even after the nuclear power plant is stopped, and the residual heat gradually decreases with time. As a result, the spent fuel generated after replacing the nuclear fuel in the nuclear power plant also has a considerable amount of residual heat. Therefore, the spent fuel storage unit for storing the spent nuclear fuel is installed before the nuclear plant, and the spent nuclear fuel storage unit is also required to be continuously cooled at the time of the nuclear accident, so that a cooling system for the accident is installed. Active cooling system is applied. However, the passive safety concept should be applied to the cooling system of the spent fuel storage unit at the nuclear power plant where the passive safety system is applied. For this purpose, introducing a separate passive safety system can lead to an increase in the cost of the nuclear power plant.

It is an object of the present invention to provide a nuclear power plant having a final heat sink integrated in one.

To achieve these and other advantages and in accordance with the purpose of the present invention, as embodied and broadly described herein, there is provided a nuclear power plant comprising: a cooling water reservoir disposed inside a compartment for storing cooling water for suppressing an increase in pressure inside the compartment and for removing heat; A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel; And a cooling water discharge unit connected to the cooling water storage unit and the spent fuel storage unit to receive high temperature cooling water from the cooling water storage unit and the spent fuel storage unit by natural circulation, And an external cooling water storage unit for supplying cooling water of low temperature to the cooling water storage unit and the spent fuel storage unit.

The nuclear power plant may further include a radioactive material abatement facility disposed inside the compartment and configured to lower a concentration of the radioactive material discharged into the compartment when an accident occurs, To remove heat.

The spent nuclear fuel storage unit may be disposed inside the compartment.

Wherein the nuclear power plant further comprises an emergency cooling water storage section configured to store cooling water for removing sensible heat of the reactor coolant system and residual heat of the core, and a part of the cooling water stored in the external cooling water storage section can be supplied to the emergency cooling water storage section Lt; / RTI >

The nuclear power plant is cooled by air cooling and is disposed above the outer cooling water storage part. The cooling water is cooled and recovered from the cooling water storage part and the spent fuel storage part and supplied to the external cooling water storage part Equipment.

Wherein the recovered cooling water cooling facility includes a recovery flow passage through which the cooling water recovered from the cooling water storage portion and the spent fuel storage portion flows; And a duct part formed to surround the recovery flow path and configured to increase the stack effect by a difference in density between inside and outside, so as to increase the flow rate of the air to be heat-exchanged with the cooling water flowing in the recovery flow path. have.

The external cooling water storage unit may be disposed at a higher position than the cooling water storage unit and the spent fuel storage unit.

The nuclear power plant includes a first cooling water storage cooling system heat exchanger disposed inside the cooling water storage unit; And a second cooling water storage cooling system heat exchanger disposed inside the external cooling water storage and connected to the first cooling water storage cooling system heat exchanger for heat exchange.

The nuclear power plant includes a first spent fuel storage unit cooling system heat exchanger disposed inside the spent nuclear fuel storage unit; And a second spent fuel storage unit cooling system heat exchanger disposed in the external cooling water storage unit and connected to the first spent fuel storage unit cooling system heat exchanger for heat exchange.

At least one of the first connection passage formed between the first and second cooling water storage section cooling system heat exchangers or the second connection passage formed between the first and second spent fuel storage section cooling system heat exchangers, A supplementary tank configured to control the pressure of the first connection passage or the second connection passage may be provided.

In order to absorb pressure fluctuations of the first connection passage or the second connection passage or to supplement the cooling water, cooling water may be stored in the supplementary tank, and at least a part of the cooling water may be an empty space.

The nuclear power plant further includes a first cooling water storage cooling system heat exchanger disposed inside the cooling water storage unit, wherein the external cooling water storage unit is divided into a first external cooling water tank and a second external cooling water tank Wherein the first external cooling water tank is configured to inject the stored fluid into the first cooling water storage cooling system heat exchanger and the second external cooling water tank is configured to inject the stored fluid from the first cooling water storage cooling system heat exchanger May be configured to be stored.

The nuclear power plant may further include a first spent fuel storage unit cooling system heat exchanger disposed inside the spent nuclear fuel storage unit, wherein the external cooling water storage unit is divided into a first external cooling water tank and a second external cooling water tank, Wherein the first external cooling water tank is configured to inject the stored fluid into the first spent fuel storage unit cooling system heat exchanger and the second external cooling water tank is connected to the first spent fuel storage unit The cooling system can be configured so that the fluid discharged from the heat exchanger is stored.

The nuclear power plant may further include an emergency cooling water storage section configured to store cooling water for removing sensible heat of the reactor coolant system and residual heat of the core, and a part of the cooling water stored in the second external cooling water tank may be supplied to the emergency cooling water storage section .

According to another aspect of the present invention, there is provided a refrigerator comprising: a cooling water storage unit disposed inside a compartment and configured to store a cooling water for suppressing a pressure increase inside the compartment and for removing heat; A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel; And a cooling water discharge unit connected to the cooling water storage unit and the spent fuel storage unit to receive steam from the cooling water storage unit and the spent fuel storage unit by natural circulation to condense and cool the water, And an external cooling water storage part for supplying cooling water of low temperature to the cooling water storage part and the spent fuel storage part.

According to the present invention, there is provided a fuel cell system comprising: a cooling water storage unit disposed inside a compartment and suppressing a pressure rise inside a compartment; a spent fuel storage unit configured to remove residual heat of the spent fuel; And an external coolant storage unit connected to the coolant storage unit and the spent fuel storage unit to cool the delivered high temperature coolant and then supply the cooled low temperature coolant to the coolant storage unit and spent fuel storage unit. Accordingly, since the final heat sink for the spent fuel storage unit and the cooling water storage unit need not be separately constructed, a compact nuclear power plant can be realized and the duration of other safety systems connected to the external cooling water storage unit can be extended.

Further, the heat exchanger for cooling the external cooling water storage portion is constructed by a water-cooled type, so that the size of the heat exchanger can be greatly reduced and the heat exchange efficiency can be increased as compared with the air cooling type. Further, it is possible to secure a sufficient water source for the operation of the driven residual heat elimination system by utilizing the cooling water located at the upper portion of the external cooling water storage portion having a relatively high temperature without separately providing a re-filling source of the driven residual heat elimination system have.

FIG. 1A is a conceptual diagram illustrating a normal operation of a nuclear power plant having an intermediate thermal sink cooling facility according to an embodiment of the present invention.
FIG. 1B is a conceptual view showing an accident of a nuclear power plant having the intermediate thermal sink cooling facility shown in FIG. 1A.
FIG. 2 is a conceptual diagram showing a normal operation of a nuclear power plant having an intermediate thermal sink cooling facility according to another embodiment of the present invention.
3 is a conceptual diagram illustrating a normal operation of a nuclear power plant having an intermediate thermal sink cool-down facility according to another embodiment of the present invention.
FIG. 4 is a conceptual diagram showing a normal operation of a nuclear power plant having an intermediate heat sink cooling facility according to another embodiment of the present invention.
FIG. 5 is a conceptual diagram illustrating a normal operation of a nuclear power plant having an intermediate thermal sink cooling facility according to another embodiment of the present invention.
FIG. 6A is a conceptual diagram showing a normal operation of a nuclear power plant having an intermediate thermal sink cooling facility according to another embodiment of the present invention. FIG.
FIG. 6B is a conceptual view showing an accident of a nuclear power plant having the intermediate thermal sink cooling facility shown in FIG. 6A.
FIG. 7A is a conceptual diagram illustrating a normal operation of a nuclear power plant having an intermediate heat sink cooling system according to another embodiment of the present invention. FIG.
7B is a conceptual view showing a side view and a plan view of the recovered cooling water cooling equipment shown in FIG. 7A.

Hereinafter, a nuclear power plant having an intermediate thermal sink cooling facility according to the present invention will be described in detail with reference to the drawings.

The singular expressions include plural expressions unless the context clearly dictates otherwise.

In other respects, the same or similar reference numerals are given to the same or similar components to those of the previous embodiment, and a duplicate description thereof will be omitted.

In the following description of the embodiments of the present invention, a detailed description of related arts will be omitted when it is determined that the gist of the embodiments disclosed herein may be obscured.

It is to be understood that both the foregoing general description and the following detailed description are exemplary and explanatory and are intended to provide further explanation of the invention as claimed. It should be understood that it includes water and alternatives.

FIG. 1A is a conceptual diagram illustrating a normal operation of a nuclear power plant 100 having an intermediate thermal sink cooling facility according to an embodiment of the present invention. FIG. 1B is a schematic view of a nuclear power plant 100) according to an embodiment of the present invention.

Referring to FIGS. 1A and 1B, a nuclear power plant 100 includes a cooling water storage unit 110, a spent nuclear fuel storage unit 120, and an external cooling water storage unit 130.

A nuclear reactor 10 is disposed inside a compartment 101 of a nuclear power plant 100 and a core 10a is accommodated in the interior of the nuclear reactor 10. In addition, the heat generated in the core 10a is converted to a high-pressure steam through the steam generator 11 to generate electricity. In the present invention, the containment building, the reactor building, the containment vessel, or the safety protection vessel are collectively referred to as the storage unit 101.

In addition, the nuclear power plant 100 may include a passive safety infusion system 12. The safety infusion system 12 is configured to inject coolant into the reactor 10 to maintain the water level of the reactor 10. The safety infusion system 12 can include a core replenishment tank 12a and a safety infusion tank 12b as shown in these figures and a description of the core replenishment tank 12a and the safety infusion tank 12b Which is a conventional technique, will be omitted.

The cooling water storage portion 110 is disposed inside the compartment portion 101 and is configured to store the cooling water for suppressing an increase in pressure inside the compartment portion 101 and for removing heat. For example, the cooling water storage portion 110 may be configured in the form of a tank or a water tank. The first cooling water storage portion cooling system heat exchanger 111 may be installed inside the cooling water storage portion 110. The first cooling water storage portion cooling system heat exchanger 111 may include an external cooling water storage portion 130, So that heat exchange with the cooling water stored in the external cooling water storage unit 130 can be performed. The first cooling water storage cooling system heat exchanger 111 and the external cooling water storage 130 may be configured such that a heat exchange fluid flows through the first connection flow path 114, Is connected to the first cooling water storage cooling system heat exchanger 110 through the first cooling water storage cooling system heat exchanger 111 and the first cooling water storage cooling system heat exchanger 110 from the external cooling water storage unit 130, And a discharge pipe 110b through which the fluid moving to the unit 111 flows.

The spent nuclear fuel storage unit 120 accommodates and disposes spent nuclear fuel 120c therein. The spent fuel storage unit 120 is formed to store cooling water for removing residual heat generated in the spent nuclear fuel 120c accommodated therein. The first spent fuel storage unit cooling system heat exchanger 121 may be installed in the spent fuel storage unit 120. The first spent fuel storage unit cooling system heat exchanger 121 may be installed in the outside And may be connected to the cooling water storage unit 130 to exchange heat with the cooling water stored in the external cooling water storage unit 130. The first spent fuel storage unit cooling system heat exchanger 121 and the external cooling water storage unit 130 may be configured such that a heat exchange fluid flows through the second connection flow path 124, The first piping 124 is connected to the first piping 120a through which the fluid moves from the first spent fuel storage unit cooling system heat exchanger 121 to the external cooling water storage unit 130 and the second piping 120b through the external cooling water storage unit 130, And a discharge pipe 120b through which the fluid moving to the heat exchanger 121 of the nuclear fuel storage unit cooling system flows. In the present invention, the spent fuel storage unit 120 cooling system used during normal operation of the nuclear power plant 100 is not separately described.

The external cooling water storage part 130 is disposed outside the compartment part 101 and is connected to the cooling water storage part 110 and the spent fuel storage part 120 to be circulated through the cooling water storage part 110 And the spent fuel storage unit 120 to cool the high temperature cooling water and supply the cooled low temperature cooling water to the cooling water storage unit 110 and the spent fuel storage unit 120 again. The external cooling water storage part 130 is disposed at a position higher than the cooling water storage part 110 and the spent fuel storage part 120 so that the movement of the stored cooling water can be performed by natural circulation using the gravity head due to the density difference And so on. Meanwhile, the external cooling water storage unit 130 may be configured as an open type that is exposed to the outside as shown in the drawing, or an open type that is installed in the underground although not shown in the drawing. In addition, when the temperature of the nuclear power plant 100 rises or the cooling water becomes insufficient, the cooling water is cooled by the heat transfer between the outside atmosphere and the structure of the external cooling water storage unit 130, Appendicitis can be configured to occur.

The external cooling water storage unit 130 receives the steam from the cooling water storage unit 110 and the spent fuel storage unit 120 to condense and cool the water and then uses the low temperature cooling water condensed and cooled with the cooling water storage unit 110 To the spent fuel storage unit 120. The piping connected to the cooling water storage unit 110 and the spent fuel storage unit 120 is configured to be located in the vapor space of the cooling water storage unit 110 and the spent fuel storage unit 120.

The nuclear power plant 100 may further include a radioactive material abatement facility 140.

The radioactive material abatement facility 140 is disposed inside the compartment 101 to lower the concentration of the radioactive material discharged into the compartment 101 from inside the radioactive material abatement facility 140 during an accident. Meanwhile, the conventional technique described in the background art of the present invention can be applied to the radioactive material abatement facility 140, and a detailed description thereof will be omitted. (Korean Patent No. 10-1538932) Herein, the cooling water storage unit 110 provided in the nuclear power plant 100 of the present invention may be configured to remove heat radiated from the radioactive material abatement facility 140.

The nuclear power plant 100 may further include an emergency cooling water storage unit 150.

The emergency cooling water storage part 150 is connected to the reactor coolant system 10 so as to store the sensible heat of the reactor coolant system 10 and the coolant for removing residual heat of the core 10a. Here, the nuclear power plant 100 may be configured to be capable of supplying a part of the cooling water stored in the external cooling water storage unit 130 to the emergency cooling water storage unit 150. For this, a re-sucking pump 153 may be installed on the flow path formed between the emergency cooling water storage part 150 and the external cooling water storage part 130 for the flow of cooling water as shown in the figure.

Hereinafter, the operation of the external cooling water storage unit 130 will be described with reference to FIGS. 1A and 1B.

First, the cooling water temperature inside the cooled cooling water reservoir 100 is continuously increased by the steam emitted from the inside of the radioactive material abatement facility 140. When the isolation valve 110a 'of the cooling system of the cooling water storage part 110 is opened by the related signal, the first cooling water storage cooling system heat exchanger 111 is moved from the external cooling water storage part 130 to the injection pipe 110a, The cooling water is injected.

Next, the cooling water injected into the first cooling water storage portion cooling system heat exchanger 111 rises in temperature due to heat transfer with the high temperature cooling water in the cooling water storage portion 110, and the high temperature cooling water whose temperature rises flows along the discharge pipe 110b And is then transmitted to the cooling water storage unit 130 again. The cooling water in the cooling water storage part 100 and the cooling water in the external cooling water storage part 130 are not mixed with each other since they use the other (shell or tube) flow path of the first cooling water storage cooling system heat exchanger 111. This natural circulation is continued while the density difference due to the temperature difference between the cooling water storage part 110 and the external cooling water storage part 130 is maintained.

Next, when the operation of the cooling system of the spent nuclear fuel storage unit 120 is stopped due to the accident, the cooling system of the spent fuel storage unit 120 operates according to the related signal. It may be configured to be integrated with no separate dedicated for normal operation and accident. The temperature of the internal cooling water of the spent fuel storage unit 120 gradually increases due to the residual heat released from the spent nuclear fuel 120a. Next, when the cooling system of the spent fuel storage unit 120 operates, the cooling water is supplied from the external cooling water storage unit 130 to the first spent fuel storage unit cooling system heat exchanger 121 along the injection pipe 120a .

The first spent fuel storage unit cooling system cooling water injected into the heat exchanger 121 is heated by the high temperature cooling water of the spent fuel storage unit 120 and the hot cooling water whose temperature rises is discharged through the discharge pipe 120b And then transmitted to the external cooling water storage unit 130 again. Since the cooling water of each of the spent fuel storage unit 120 and the external cooling water storage unit 130 uses the different (shell or tube) flow path of the first spent fuel storage unit cooling system heat exchanger 121, It does not. Also, the natural circulation is continued while the density difference due to the temperature difference between the spent fuel storage unit 120 and the external cooling water storage unit 130 is maintained.

When the cooling water in the emergency cooling water storage part 150 is insufficient, the recharge system isolation valve 150a of the emergency cooling water storage part 150 is opened and the re-filling pump 153 is started, 130 to the emergency cooling water storage part (150).

In addition, when the cooling water temperature of the external cooling water storage part 130 rises and the cooling water is needed or the cooling water is insufficient, the nuclear power plant 100 replenishes or cools the cooling water from external resources (for example, fire engine) The ice can be supplied and cooled.

According to the present invention described above, the cooling water storage part 110 disposed inside the compartment part 101 and suppressing the pressure rise inside the compartment part 101, the use of which the residual heat of the spent fuel 120c is removed The cooling water storage unit 110 and the spent fuel storage unit 120 to cool the high temperature cooling water transferred from the cooling water storage unit 110 and the spent fuel storage unit 120, And an external cooling water storage unit 130 for supplying the spent fuel to the spent fuel storage unit 120. Accordingly, the final heat sink for the spent nuclear fuel storage unit 10 and the cooling water storage unit 110 need not be separately constructed. Therefore, it is possible to realize a compact nuclear power plant 100, Lt; RTI ID = 0.0 > other safety systems. ≪ / RTI >

Also, since the heat exchanger for cooling the external cooling water storage part 130 is water-cooled, the size of the heat exchanger can be greatly reduced and the heat exchange efficiency can be increased as compared with the air cooling type. Further, it is possible to secure a sufficient water source for the operation of the driven residual heat removal system by utilizing the cooling water located above the external cooling water storage part 130 having a relatively high temperature without separately providing a re-filling source of the driven residual heat removal system .

Hereinafter, a nuclear power plant 100 having an intermediate thermal sink cooling facility according to other embodiments of the present invention will be described. In the following description, the same or similar components as those of the nuclear power plant 100 described above will not be described in detail.

FIG. 2 is a conceptual diagram showing a normal operation of the nuclear power plant 100 provided with the intermediate thermal sink cooling system according to another embodiment of the present invention.

Referring to FIG. 2, the nuclear power plant 100 may further include a first cooling water storage cooling system heat exchanger 111 and a second cooling water storage cooling system heat exchanger 112.

The first cooling water storage portion cooling system heat exchanger 111 is disposed inside the cooling water storage portion 110.

The second cooling water storage portion cooling system heat exchanger 112 is disposed inside the external cooling water storage portion 130 disposed outside the compartment portion 101 and connected to the first cooling water storage portion cooling system heat exchanger 111 Exchanged with the first cooling water storage portion cooling system heat exchanger 111. In the case of adopting such a configuration, although the cost is increased, in the case where breakage occurs between the first cooling water storage section cooling system heat exchanger 111 and the second cooling water storage section cooling system heat exchanger 112, The pressure boundary of the pressure vessel 101 can be maintained.

FIG. 3 is a conceptual diagram showing a normal operation of the nuclear power plant 100 provided with the intermediate heat sink cooling system according to another embodiment of the present invention.

Referring to FIG. 3, the boundary of the storage unit 101 may be configured to include spent fuel storage unit 120.

Meanwhile, FIG. 4 is a conceptual diagram showing a normal operation of the nuclear power plant 100 provided with an intermediate thermal sink cooling facility according to another embodiment of the present invention.

Referring to FIG. 4, the nuclear power plant 100 may further include a first spent fuel storage unit cooling system heat exchanger 121 and a second spent fuel storage unit cooling system heat exchanger 122.

The first spent fuel storage unit cooling system heat exchanger 121 is disposed inside the spent fuel storage unit 120.

The second spent fuel storage unit cooling system heat exchanger 122 is disposed inside the external cooling water storage unit 130 and connected to the first spent fuel storage unit cooling system heat exchanger 121, 1 spent fuel storage unit cooling system heat exchanger 121. In this case, If the spent nuclear fuel storage unit 120 is located within the boundary of the compartment 101, the cost is increased, but the first spent fuel storage cooling system heat exchanger 121 and the second spent fuel storage cooling system heat exchanger The pressure boundary of the compartment 101 can be maintained without the operation of the isolation valve in the case where breakage between the partition wall 122 and the partition wall 122 occurs.

The first connection passage 114 formed between the first and second cooling water storage section cooling system heat exchangers 111 and 112 or the first and second spent fuel storage unit cooling system heat exchangers 121 and 122 At least one of the second connection flow paths 124 may be provided with supplementary tanks 115 and 125 configured to control the pressures of the first connection path 124 or the second connection path 124. In order to absorb pressure fluctuations of the first connection passage (114) or the second connection passage (124) or to supplement the cooling water, cooling water is stored in the supplementary tanks (115, 125) So as to perform the function of the pusher.

Meanwhile, FIG. 5 is a conceptual diagram showing a normal operation of the nuclear power plant 100 provided with the intermediate heat sink cooling system according to another embodiment of the present invention.

Referring to FIG. 5, spent fuel storage unit 120 may be disposed inside compartment 101. That is, the boundary of the compartment 101 may be configured to include the spent fuel storage unit 120, similar to the compartment 101 of the nuclear power plant 100 shown in Fig.

FIG. 6A is a conceptual view showing a normal operation of the nuclear power plant 100 provided with the intermediate heat sink cooling system according to another embodiment of the present invention, FIG. 6B is a view showing a state in which the intermediate heat sink cooling system shown in FIG. FIG. 1 is a conceptual diagram showing an accident of a nuclear power plant 100 according to an embodiment of the present invention.

6A and 6B, the external cooling water storage part 130 may include a first external cooling water tank 131 and a second external cooling water tank 132 which are separated from each other and formed as independent spaces.

Here, the first outer cooling water tank 131 is configured to inject the stored fluid into the first cooling water storage cooling system heat exchanger 111, and the second outer cooling water tank 132 is configured to cool the first cooling water storage cooling The fluid discharged from the system heat exchanger 111 may be configured to be stored.

Also, as shown in the figure, the first external cooling water tank 131 is configured to inject the stored fluid into the first spent fuel storage unit cooling system heat exchanger 121, and the second external cooling water tank 132 is configured to inject The first spent fuel storage unit cooling system can be configured so that the fluid discharged from the heat exchanger 121 is stored.

The nuclear power plant 100 may be configured to supply high temperature cooling water injected into the second external cooling tank 132 to the emergency cooling water storage unit 150. For this purpose, the emergency cooling water storage unit 150 and the second A re-sucking pump 153 for the flow of cooling water may be installed on the flow path formed between the outer cooling water tanks 132 as shown in FIG. When this configuration is applied, it is possible to separate the low temperature cooling water before heating and the high temperature cooling water after heating.

7A is a conceptual diagram illustrating a normal operation of the nuclear power plant 100 provided with the intermediate thermal sink cooling system according to another embodiment of the present invention. FIG. 7B is a schematic view of the recovered cooling water cooling system 160 shown in FIG. FIG. 7 is a conceptual view showing a side view and a plan view of FIG.

Referring to FIGS. 7A and 7B, the nuclear power plant 100 may further include a recovered cooling water cooling facility 160.

The recovered cooling water cooling system 160 is cooled by an air-cooling type that is heat-exchanged with the outside atmosphere. The recovered cooling water cooling system 160 is disposed above the external cooling water storage unit 130 and is installed in the cooling water storage unit 110 and the spent fuel storage unit 120, The cooling water recovered from the cooling water is cooled and supplied to the external cooling water storage part 130 disposed at the lower part.

In addition, the recovered cooling water cooling system 160 may include a recovery flow path 161 and a duct portion 163.

The recovery flow path 161 forms a flow path so that the cooling water recovered from the spent fuel storage unit 110 and the spent fuel storage unit 120 flows. The flow distribution portion 160a may be formed on the inlet side of the recovery flow path 161 so as to distribute the high temperature cooling water discharged from the discharge piping 110b and 120b to each flow path of the recovery flow path 161. [

The duct portion 163 is formed so as to surround the recovery flow path 161 so as to increase the flow rate of the air to be heat-exchanged with the cooling water flowing through the recovery flow path 161, and has a stack effect by a density difference between the inside and the outside. May be increased. The chimney effect means that the air in the chimney is buoyantly increased when the temperature of the inside of the chimney is higher than the outside temperature and the density is low. With this configuration, the flow rate of the cooling water in the external cooling water storage part 130 can be maintained for a long time.

100: Nuclear power plant 110: Cooling water storage section
120: Spent fuel storage unit 130: External cooling water storage unit
131: first outside cooling water tank 132: second outside cooling water tank
140: Radioactive material abatement facility 150: Emergency cooling water storage unit
160: Recovery cooling water cooling facility

Claims (16)

A cooling water storage unit disposed inside the compartment and configured to store the cooling water for suppressing a pressure increase inside the compartment and for removing heat;
A first cooling water storage cooling system heat exchanger installed in the cooling water storage unit;
A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel;
A first spent fuel storage unit cooling system heat exchanger installed inside the spent nuclear fuel storage unit; And
A first cooling water storage cooling system heat exchanger and a first cooling water storage cooling system heat exchanger disposed outside the compartment and connected to the first cooling water storage cooling system heat exchanger and the first spent fuel storage cooling system heat exchanger, The cooling water having a high temperature from each of the spent fuel storage unit cooling system heat exchanger is cooled and cooled by the cooling water in the first cooling water storage unit cooling system heat exchanger and the cooling system of the first spent fuel storage unit cooling system, An external cooling water storage unit for supplying the cooling water storage unit and the spent fuel storage unit, respectively; And
And a recovered cooling water cooling device that is provided above the external cooling water storage part and cools the cooling water recovered from the cooling water storage part and the spent fuel storage part and supplies the cooled cooling water to the external cooling water storage part Nuclear power plant. The method according to claim 1,
Further comprising a radioactive material abatement device disposed inside the compartment and configured to lower a concentration of radioactive material discharged into the compartment when an accident occurs,
Wherein the cooling water storage unit is configured to remove heat generated in the radioactive material abatement facility. 3. The method of claim 2,
And the spent nuclear fuel storage unit is disposed inside the compartment. The method according to claim 1,
Further comprising an emergency cooling water storage portion configured to store cooling water for removing sensible heat of the reactor coolant system and residual heat of the core,
And a part of the cooling water stored in the external cooling water storage part can be supplied to the emergency cooling water storage part. A cooling water storage unit disposed inside the compartment and configured to store the cooling water for suppressing a pressure increase inside the compartment and for removing heat;
A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel; And
The cooling water storage portion and the spent fuel storage portion are connected to the cooling water storage portion and the spent fuel storage portion, and the high-temperature cooling water is received from the cooling water storage portion and the spent fuel storage portion by natural circulation, And an external cooling water storage unit for supplying cooling water of the spent fuel storage unit to the cooling water storage unit and the spent fuel storage unit,
Cooling cooling water is provided in the external cooling water storage portion and cooled to cool the cooling water recovered from the cooling water storage portion and the spent fuel storage portion and supplied to the external cooling water storage portion . 6. The method of claim 5,
The recovered cooling water cooling system includes:
A recovery flow passage through which the cooling water recovered from the cooling water storage section and the spent fuel storage section flows; And
And a duct part which is formed to surround the recovery flow path and increases a stack effect by a density difference between inside and outside so as to increase the flow rate of the air to be heat-exchanged with the cooling water flowing in the recovery flow path Nuclear power plant. The method according to claim 1,
Wherein the external cooling water storage portion is disposed at a higher position than the cooling water storage portion and the spent fuel storage portion. A cooling water storage unit disposed inside the compartment and configured to store the cooling water for suppressing a pressure increase inside the compartment and for removing heat;
A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel; And
The cooling water storage portion and the spent fuel storage portion are connected to the cooling water storage portion and the spent fuel storage portion, and the high-temperature cooling water is received from the cooling water storage portion and the spent fuel storage portion by natural circulation, And an external cooling water storage unit for supplying cooling water of the spent fuel storage unit to the cooling water storage unit and the spent fuel storage unit,
A first cooling water storage cooling system heat exchanger disposed inside the cooling water storage; And
Further comprising a second cooling water storage cooling system heat exchanger disposed inside the external cooling water storage and connected to the first cooling water storage cooling system heat exchanger for heat exchange. A cooling water storage unit disposed inside the compartment and configured to store the cooling water for suppressing a pressure increase inside the compartment and for removing heat;
A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel; And
The cooling water storage portion and the spent fuel storage portion are connected to the cooling water storage portion and the spent fuel storage portion, and the high-temperature cooling water is received from the cooling water storage portion and the spent fuel storage portion by natural circulation, And an external cooling water storage unit for supplying cooling water of the spent fuel storage unit to the cooling water storage unit and the spent fuel storage unit,
A first spent fuel storage unit cooling system heat exchanger disposed inside the spent nuclear fuel storage unit; And
And a second spent fuel storage unit cooling system heat exchanger disposed inside the external cooling water storage unit and connected to the first spent fuel storage unit cooling system heat exchanger for heat exchange. 9. The method of claim 8,
Wherein a supplementary tank configured to control a pressure of the first connection passage is provided in a first connection passage formed between the first and second cooling water storage section cooling system heat exchangers. 11. The method of claim 10,
Wherein the cooling water is formed in the replenishing tank so as to absorb the pressure fluctuation of the first connection channel or to supplement the cooling water, and at least a part of the cooling water is formed as an empty space. A cooling water storage unit disposed inside the compartment and configured to store the cooling water for suppressing a pressure increase inside the compartment and for removing heat;
A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel; And
The cooling water storage portion and the spent fuel storage portion are connected to the cooling water storage portion and the spent fuel storage portion, and the high-temperature cooling water is received from the cooling water storage portion and the spent fuel storage portion by natural circulation, And an external cooling water storage unit for supplying cooling water of the spent fuel storage unit to the cooling water storage unit and the spent fuel storage unit,
And a first cooling water storage cooling system heat exchanger disposed inside the cooling water storage,
Wherein the external cooling water storage part comprises a first external cooling water tank and a second external cooling water tank which are separated from each other and formed as independent spaces,
Wherein the first external cooling water tank is configured to inject the stored fluid into the first cooling water storage cooling system heat exchanger,
And the second external cooling water tank is configured to store the fluid discharged from the first cooling water storage cooling system heat exchanger. A cooling water storage unit disposed inside the compartment and configured to store the cooling water for suppressing a pressure increase inside the compartment and for removing heat;
A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel; And
The cooling water storage portion and the spent fuel storage portion are connected to the cooling water storage portion and the spent fuel storage portion, and the high-temperature cooling water is received from the cooling water storage portion and the spent fuel storage portion by natural circulation, And an external cooling water storage unit for supplying cooling water of the spent fuel storage unit to the cooling water storage unit and the spent fuel storage unit,
And a first spent fuel storage unit cooling system heat exchanger disposed in the spent fuel storage unit,
Wherein the external cooling water storage part comprises a first external cooling water tank and a second external cooling water tank which are separated from each other and formed as independent spaces,
Wherein the first external cooling water tank is configured to inject the stored fluid into the first spent fuel storage unit cooling system heat exchanger,
And the second external cooling water tank is configured to store the fluid discharged from the first spent fuel storage unit cooling system heat exchanger. The method according to claim 12 or 13,
Further comprising an emergency cooling water storage portion configured to store cooling water for removing sensible heat of the reactor coolant system and residual heat of the core,
And a part of the cooling water stored in the second external cooling water tank is supplied to the emergency cooling water storage unit. A cooling water storage unit disposed inside the compartment and configured to store the cooling water for suppressing a pressure increase inside the compartment and for removing heat;
A first cooling water storage cooling system heat exchanger installed in the cooling water storage unit;
A spent fuel storage unit configured to receive spent fuel and store cooling water for removing residual heat of the spent fuel;
A first spent fuel storage unit cooling system heat exchanger installed inside the spent nuclear fuel storage unit;
A first cooling water storage cooling system heat exchanger and a first cooling water storage cooling system heat exchanger disposed outside the compartment and connected to the first cooling water storage cooling system heat exchanger and the first spent fuel storage cooling system heat exchanger, Cooling water which has been condensed and cooled by receiving steam from each spent fuel storage unit cooling system heat exchanger is condensed and cooled through the first cooling water storage cooling system heat exchanger and the first spent fuel storage unit cooling system heat exchanger An external cooling water storage unit configured to supply the cooling water storage unit and the spent fuel storage unit, respectively; And
And a recovered cooling water cooling device that is provided above the external cooling water storage part and cools the cooling water recovered from the cooling water storage part and the spent fuel storage part and supplies the cooled cooling water to the external cooling water storage part Nuclear power plant. 10. The method of claim 9,
Wherein a supplementary tank configured to control a pressure of the second connection passage is provided in a second connection passage formed between the first and second spent fuel storage unit cooling system heat exchangers.

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