KR101528223B1 - Passive safety facility and nuclear power plant having the same - Google Patents

Abstract

A passive safety facility is provided. The passive safety facility comprises: a cooling unit cooling first fluid discharged from a reactor coolant system or a vapor generator installed in the reactor coolant system and second fluid in a housing unit; a circulation inducing spraying unit spraying the first fluid discharged from the reactor coolant system or the vapor generator to the cooling unit, having a part partially opened toward the inside of the housing unit so that the second fluid is inserted by pressure drop generated when the first fluid is sprayed, and spraying the inserted second fluid along with the first fluid; and a filter unit connected with an outlet of the cooling unit to filter non-condensable gas discharged from the cooling unit and collecting a radioactive matter filtered from the non-condensable gas.

Description

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

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a passive safety device that enhances fluid circulation performance inside a compartment and improves the cooling performance and the performance of reducing radioactive materials inside a compartment by introducing filtration equipment and a nuclear power plant having the same.

Reactors are divided into separate reactors and integral reactors depending on the installation location of the main equipment. When major equipment (steam generator, pressurizer, pump, etc.) is installed outside the reactor vessel, it is divided into separate nuclear reactors (eg commercial reactor: domestic). When major equipment is installed inside the reactor vessel, it is divided into an integral reactor (eg SMART reactor: domestic).

Reactors are divided into active reactors and passive reactors depending on the implementation of the safety system. Active reactors use active devices, such as pumps operated by electric power, such as emergency generators, to drive safety systems. A passive nuclear reactor uses a driven unit operated by gravity or gas pressure to drive the safety system. Passive safety systems in passive reactors are designed to operate in a system without an AC source of safety grade such as an operator action or an emergency diesel generator for more than the time required for regulatory requirements (72 hours) The built-in power alone keeps the reactor safe. The passive safety system is a system that can be assisted by an operator or non-safety system after 72 hours. Passive safety systems are generally preferred to passive safety systems rather than active safety systems, since AC power or a source of safety can be maintained without operator intervention for a considerable amount of time after an accident.

In the prior art, a drift residual heat removal system and a cooling system of a passive containment building were constructed using a secondary side of a steel containment vessel and a steam generator (Patent Publication No. 10-2013-0047871). However, the steel containment vessel used in the conventional technology is in the form of a containment building using reinforced concrete due to difficulties in manufacture, maintenance and economical efficiency. Hereinafter, the driven residual heat elimination system and the as-dispensed cooling system will be described, respectively.

The passive residual heat removal system is employed as a system to remove the heat of the reactor coolant system (the sensible heat of the reactor coolant system and the residual heat of the core) in an accident in various reactors including an integrated reactor. As the cooling water circulation system of the passive residual heat removal system, the reactor coolant system is cooled by circulating the primary coolant of the reactor directly (AP1000: Westinghouse, USA) and the steam generator is used to circulate the secondary coolant to cool the reactor coolant system (SMART reactor: domestic) are mainly used, and a method of directly condensing the primary cooling water into the tank (CAREM: Argentina) is partially used.

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) (IMR: Japan) are used in combination. The heat exchanger of the passive residual heat removal system performs the function of transferring the heat transferred from the reactor coolant system to the outside (final heat sink) through the emergency cooling water storage unit or the like. In the heat exchanger system, a condensation heat exchanger having excellent heat transfer efficiency is often employed by utilizing vapor condensation phenomenon.

The isobaric cooling system is one of several safety systems that reduces the pressure, temperature and radioactive material concentration inside the compartment. The equipotential cooling system is employed as a system for suppressing the rise of pressure inside the accident chamber (reactor building, containment vessel, or safety protection vessel) and removing heat from various reactors including an integrated reactor. The method of constructing the cooling system is to use a suppression tank to decompress the steam released into the containment (commercial BWR, CAREM: Argentina, IRIS: Westinghouse Company, USA) (AP1000: Westinghouse, USA) and heat exchanger (SWR1000: France Pramatom ANP, AHWR: India, SBWR: US GE).

As described above, the passive residual heat removal system using the secondary side of the steam generator is generally constituted by installing a heat sink (emergency cooling water storage part) outside the compartment, supplying cooling water cooled by the condensing heat exchanger to the steam generator, And the steam which is formed while removing the steam is again circulated to the condensation heat exchanger (Patent Publication No. 10-2013-0047871). On the other hand, the coined-bed cooling system is generally used in a manner of removing heat inside the compartment by a natural circulation flow formed inside the compartment without a means for generating a separate flow. In addition, a system in which the driven residual heat elimination system and the to-be-poured cooling system are separately constructed is generally used.

The performance of the conventional coined pour cooling system was determined only by natural circulation flow without a separate device for forming the flow. In such a configuration, there is a problem that the heat transfer coefficient of the air (steam and air) flowing surface is small, and the size of the heat exchanger must be relatively increased if the flow is weak, especially in natural convection conditions. On the other hand, since the heat exchanger is a structure that forms the pressure boundary of the compartment, there is a problem that the possibility of damaging the pressure boundary increases when the size of the heat exchanger increases, which may lower the safety.

It is an object of the present invention to provide a passive safety equipment with improved performance for cooling the interior of a compartment by using a facility for improving circulation flow from a simple natural circulation flow and a nuclear power plant having the same.

It is another object of the present invention to provide a passive safety equipment capable of performing both functions of a conventional driven residual heat eliminating system and a passive containment building cooling system and releasing heat transferred from a reactor coolant system to an external environment, .

Another object of the present invention is to provide a passive safety device capable of improving heat transfer performance without increasing the size of a heat exchanger and a nuclear power plant having the same.

Another object of the present invention is to provide a passive safety equipment capable of reducing the concentration of radioactive material inside the compartment by improving the circulating flow inside the compartment and a nuclear power plant having the same.

It is still another object of the present invention to provide a passive safety equipment capable of reducing the concentration of radioactive materials in the compartment by collecting radioactive materials and a nuclear power plant having the same.

In order to accomplish the above object, according to one aspect of the present invention, there is provided a passive safety equipment comprising: a first fluid discharged from a reactor coolant system or discharged from a steam generator installed inside the reactor coolant system, A cooling unit configured to cool together with the second fluid therein; At least a part of which is formed to inject the first fluid discharged from the reactor coolant system or the steam generator to the cooling part and to draw the second fluid by a pressure drop caused by spraying the first fluid, A circulation induction injection mechanism that opens toward the inside of the pouring part and injects the second fluid that has been introduced together with the first fluid; And a filtration facility connected to an outlet of the cooling section to filter the non-condensable gas discharged from the cooling section, and collecting the radioactive material filtered from the non-condensable gas.

According to one embodiment of the present invention, the circulation induction injection mechanism includes a circulation induction injection mechanism connected to the reactor coolant system or the steam generator to receive the first fluid, Quasi; A second fluid inlet formed annularly around the first fluid injection portion to draw a second fluid inside the compartment; And a circulating fluid injecting section for surrounding the first fluid injecting section with a portion having an inner diameter larger than that of the first fluid injecting section to form the second fluid intake part and supplying the first fluid and the second fluid to the cooling part can do.

The first fluid ejection unit may include a nozzle for ejecting the first fluid to the circulating fluid ejection unit.

Wherein the circulating fluid ejection portion is formed with an inner diameter narrower than the circumference to cause a local pressure drop while injecting the first fluid; And a diffuser to guide the first fluid and the second fluid passing through the neck to the cooling section.

According to another embodiment of the present invention, the filtration facility comprises: a filter or adsorbent configured to separate the radioactive material from the non-condensable gas; A gas discharge unit configured to discharge the non-condensable gas filtered while passing through the filter or the adsorbent to the inside of the compartment; And gas piping connected to the outlet of the cooling section to supply the non-condensable gas to the filter or adsorbent.

According to another embodiment of the present invention, in the cooling unit, condensed water is formed by cooling of the first fluid and the second fluid, and the passive safety equipment includes cooling water to be injected into the reactor coolant system or the steam generator The cooling water storage unit may be installed at a lower portion of the cooling unit to collect the condensed water.

Wherein the cooling water storage unit comprises: a first cooling water storage unit for storing pure cooling water to be supplied to the steam generator to remove sensible heat in the reactor coolant system and residual heat of the core; And a second cooling water storage part for storing the boric acid water to be injected into the reactor coolant system to maintain the water level of the reactor coolant system; Or the like.

The passive safety equipment may further include an additive injection unit for injecting an additive for suppressing re-volatilization of condensed water collected in the cooling water storage unit into the condensed water, wherein the additive is made to maintain the pH of the condensed water at a predetermined value or higher .

The additive injection unit may be installed in the flow path from the cooling unit to the cooling water storage unit so as to inject the additive into the condensed water collected by the cooling water storage unit.

The cooling water storage part collects the condensed water in the first cooling water storage part. When the water level of the collected condensed water exceeds the reference water level, the cooling water storage part introduces the condensed water collected in the first cooling water storage part into the second cooling water storage part And the additive injection unit may be installed in the flow path leading from the first cooling water storage unit to the second cooling water storage unit so as to inject the additive into the condensed water flowing into the second cooling water storage unit.

Wherein the passive safety equipment further comprises a fluid circulation unit configured to circulate the cooling water in the cooling water storage unit to the circulation induction spray unit via the reactor coolant system or the steam generator, A fluid supply pipe connected to the reactor coolant system or the cooling water storage for supplying the steam coolant to the steam generator; And a steam discharge pipe connected to the reactor coolant system or the steam generator and the circulation induction injection mechanism to supply the reactor coolant system or the first fluid discharged from the steam generator to the circulation induction injector.

The cooling unit may include an emergency cooling water storage unit configured to store cooling water therein and installed outside the storage unit to discharge the heat received by evaporating the cooling water when the temperature rises due to heat transfer to the outside; And a cooling fluid passage connected to the emergency cooling water storage portion through a connection pipe that is installed in the inside of the compartment and passes through the compartment portion and passes the cooling water of the emergency cooling water storage portion, A heat exchanger for exchanging heat with the two fluids; And a casing enclosing the heat exchanger to at least partly protect the heat exchanger and configured to receive a first fluid and a second fluid that are injected from the circulation induction injection mechanism.

Wherein the connection pipe is connected to the emergency cooling water storage part and the heat exchanger so as to form a flow path for supplying the cooling water of the emergency cooling water storage part to the heat exchanger and for introducing cooling water of the emergency cooling water storage part into the heat exchanger 1 connection piping; A second connection pipe extending from the heat exchanger to the outside of the storage part to discharge the cooling water of the emergency cooling water storage part that has passed through the heat exchanger to the outside; Wherein the air discharged from the second connection pipe is supplied to the heat exchanger when the cooling water in the emergency cooling water storage part is exhausted, 3 connection piping; And a fourth connection pipe branched from the first connection pipe and extending to the outside of the compartment to discharge the heated air passing through the heat exchanger to the outside.

Wherein said passive safety equipment comprises a plurality of isolators which are respectively installed in said first connection pipe and said fourth connection pipe and are opened and closed by a predetermined signal so as to switch from said water cooling type cooling to said air cooling type cooling water when cooling water of said emergency cooling water storage part becomes exhausted, And may further include a valve.

The upper portion of the casing is opened to receive the first fluid and the second fluid from the circulation induction injection mechanism and the lower portion of the casing collects condensed water formed by cooling the first fluid and the second fluid .

The passive safety equipment may include a recovery pipe extending to the cooling water storage unit to supply the condensed water generated in the cooling process of the cooling unit to the cooling water storage unit

The recovery pipe includes a first recovery pipe connected to a lower portion of the casing to form a passage for condensed water collected in the casing; And a second recovery pipe connected to a lower portion of the filtration facility to form a passage for condensate collected in the filtration facility.

The cooling unit may include an emergency cooling water storage unit configured to store cooling water therein and installed outside the storage unit to discharge the heat received by evaporating the cooling water when the temperature rises due to heat transfer to the outside; And an emergency cooling water storage unit that is connected to a connection pipe that is installed in the emergency cooling water storage unit and passes through the storage unit and passes the first fluid and the second fluid flowing from the circulation induction injection mechanism through the connection pipe, And a heat exchanger for exchanging heat with cooling water. The filtration facility is installed inside the compartment and can be connected to the heat exchanger by the connection pipe to receive non-condensable gas and condensed water from the heat exchanger.

The cooling unit may include an emergency cooling water storage unit configured to store cooling water therein and installed outside the storage unit to discharge the heat received by evaporating the cooling water when the temperature rises due to heat transfer to the outside; A first heat exchanger installed inside the compartment to cool the first fluid and the second fluid injected from the circulation induction injection mechanism; And a heat exchanger connected to the first heat exchanger by a connection pipe passing through the compartment to form a waste oil path, the heat transferred to the fluid circulating the waste oil path is stored in the emergency cooling water storage And a second heat exchanger for transferring the cooling water to the inside of the cooling water.

The cooling section may further include a replenishing tank configured to store replenishing water therein, and the replenishing tank may be connected to the connecting pipe to supply the replenishing water to the waste oil passage or to receive the surplus water to the waste oil.

Further, in order to realize the above-mentioned problem, the present invention discloses a nuclear power plant equipped with passive safety equipment.

Nuclear reactors, reactor coolant system; A compartment for enclosing the reactor coolant system to prevent the radioactive material from leaking to the external environment; And a heat exchanger for circulating the fluid into the reactor coolant system so as to remove heat of the reactor coolant system and cooling the first fluid discharged from the reactor coolant system and the second fluid inside the chamber, Wherein the passive safety equipment includes a first fluid discharged from a reactor coolant system or a steam generator installed inside the reactor coolant system, A cooling part formed to co-operate with the cooling part; At least a part of which is formed so as to receive the first fluid from the reactor coolant system or the steam generator and to inject the second fluid by a pressure drop caused by spraying the first fluid, A circulation induction injection mechanism that opens toward the inside of the first fluid and injects the second fluid along with the first fluid; And a filtration device connected to the outlet of the cooling section to filter the non-condensable gas emitted from the cooling section and to collect the radioactive material filtered from the non-condensable gas.

According to the present invention, since the efficiency of cooling the inside of the compartment can be increased by promoting the natural circulation by using the circulation induction injection mechanism, it is possible to overcome the conventional technical limitations of the natural circulation inside the compartment .

In addition, since the second fluid inside the compartment can also be guided to the heat exchanger by the discharge flow of the first fluid, the present invention can increase the size, cost, and safety of the heat exchanger for cooling the compartment in the nuclear power plant. Can be solved.

Further, the present invention can lower the concentration of the radioactive material inside the compartment early by using the filtration facility of the present invention. The present invention can reduce the boundary zone boundary distance as the concentration of the radioactive material is lowered.

1 is a conceptual view showing a passive safety system according to an embodiment of the present invention and a normal operation of a nuclear power plant having the same.
FIG. 2 is a conceptual view of the circulation induction injection mechanism and the heat exchanger shown in FIG. 1 viewed from the front; FIG.
3 is a conceptual view of the circulation induction injection mechanism and the heat exchanger shown in FIG.
FIG. 4 is a conceptual diagram showing the passive safety system shown in FIG. 1 and a nuclear power plant having the same.
5 is a conceptual view showing a passive safety system according to another embodiment of the present invention and a normal operation of a nuclear power plant having the same.
Fig. 6 is an enlarged conceptual view of the circulation induction injection mechanism shown in Fig. 5; Fig.
FIG. 7 is a conceptual diagram showing the passive safety system shown in FIG. 5 and the occurrence of an accident of a nuclear power plant having the same.
8 is a conceptual diagram showing a passive safety system according to another embodiment of the present invention and a normal operation of a nuclear power plant having the same.
FIG. 9 is a conceptual diagram showing the passive safety system shown in FIG. 8 and the occurrence of an accident of a nuclear power plant having the same.
10 is a conceptual view showing a passive safety system according to still another embodiment of the present invention and a normal operation of a nuclear power plant having the same.
11 is a conceptual view showing the passive safety system shown in Fig. 10 and the occurrence of an accident of a nuclear power plant having the same.
12 is a conceptual view showing a passive safety system according to still another embodiment of the present invention and a normal operation of a nuclear power plant having the same.
FIG. 13 is a conceptual diagram showing the passive safety system shown in FIG. 12 and the occurrence of an accident of a nuclear power plant having the system.
FIG. 14 is a conceptual view showing a passive safety system according to still another embodiment of the present invention and a normal operation of a nuclear power plant having the same. FIG.
15 and 16 are conceptual diagrams showing the passive safety system shown in FIG. 14 and the occurrence of an accident of a nuclear power plant having the same.
17 is a conceptual view showing a passive safety system according to still another embodiment of the present invention and a normal operation of a nuclear power plant having the same.
18 is a conceptual view enlarging and showing a part of the passive safety system shown in Fig.
19 to 21 are conceptual views showing a circulating induction injection mechanism and a modification thereof.

Hereinafter, the passive safety equipment according to the present invention and the nuclear power plant having the same will be described in detail with reference to the drawings. In the present specification, the same or similar reference numerals are given to different embodiments in the same or similar configurations. As used herein, the singular forms "a", "an" and "the" include plural referents unless the context clearly dictates otherwise.

1 is a conceptual view of a passive safety equipment 100 and a nuclear power station 10 having the same according to an embodiment of the present invention.

The nuclear power plant 10 includes a compartment 12, a reactor coolant system 11, a core 11a, a steam generator 11b, a reactor coolant pump 11c and a pressurizer 11d. In addition to the components shown in FIG. 1, the nuclear power plant 10 may include systems for normal operation of the nuclear power plant 10 and various systems for securing the safety of the nuclear power plant 10.

The reactor coolant system (11) is installed inside the compartment (12). The reactor coolant system 11 is a coolant system for transferring and transporting thermal energy generated by nuclear fission in the core 11a. The inside of the reactor coolant system 11 is filled with the primary fluid. In the event of an accident such as a loss of coolant, steam may be discharged from the reactor coolant system 11, and the storage part 12 may block leakage of the radioactive material contained in the steam to the outside.

The steam generator 11b generates steam by using heat transmitted from the core. The lower inlet of the steam generator 11b is connected to the water supply system 13 by the water supply pipe 13a and the upper outlet of the steam generator 11b is connected to the turbine system 14 by the steam pipe 14a. The water supplied to the steam generator 11b through the water supply pipe 13a evaporates in the steam generator 11b to become steam. The steam is supplied to the turbine system 14 through the steam pipe 14a.

The reactor coolant pump 11c induces the circulation of the primary fluid and the pressurizer 11d maintains the pressurized state beyond the saturation pressure in order to suppress the boiling of the coolant in the core 11a of the pressurized water reactor.

The compartment 12 surrounds the reactor coolant system 11 to prevent the radioactive material from leaking to the external environment. The radioactive material may leak from the reactor coolant system 11 in the event of an accident such as a coolant loss accident or a loss of non-coolant accident. Therefore, the storage part 12 is provided outside the reactor coolant system 11, So as to prevent leakage of the radioactive material.

The compartment 12 serves as a final barrier to prevent leakage of the radioactive material from the nuclear power plant 10 to the external environment. The compartment 12 is divided into a containment building (or reactor building) made of reinforced concrete, a containment vessel made of a steel container, and a safety protection container, depending on the material constituting the pressure boundary. 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. Unless otherwise stated, the compartment 12 in the present invention is used to encompass both containment buildings, reactor buildings, containment vessels, or safety guard vessels.

There are various fluids in the compartment 12 for maintaining the safety of the nuclear power plant 10. The reactor coolant system 11 is filled with a fluid for maintaining the level of the coolant. In addition, fluids for various accidents are stored in the inside of the compartment 12. The fluid discharged from the reactor coolant system 11 is divided into the first fluid and the fluid present in the space between the reactor coolant system 11 and the compartment 12 And the second fluid. However, this distinction is not related to the nature of the fluid or to the material constituting the fluid. Thus, the first fluid and the second fluid may be the same kind of fluid. Then, the first fluid and the second fluid should be distinguished from the primary fluid and the secondary fluid. The primary fluid and the secondary fluid may be the first fluid or the second fluid.

Referring to FIG. 1, the passive safety apparatus 100 employs a method of circulating a secondary fluid using the steam generator 11b. Accordingly, in the passive safety equipment 100 shown in Fig. 1, both the first fluid and the second fluid refer to secondary fluid. If the passive safety system is such that the primary fluid is circulated, the first fluid and the second fluid will both refer to the primary fluid.

The passive safety facility 100 removes the sensible heat of the reactor coolant system 11 and the residual heat of the core 11a by using a circulating system of the primary fluid or a circulating system of the secondary fluid. When the primary fluid circulation system is used, the passive safety facility 100 circulates the primary fluid to the reactor coolant system 11. In the case of using the circulating system of the secondary fluid, the passive safety equipment 100 circulates the secondary fluid to the steam generator 11b. The passive safety facility 100 cools the first fluid discharged from the reactor coolant system 11 or the steam generator 11b and the second fluid inside the compartment 12 together to heat the inside of the compartment 12 to the outside To the environment. 1 shows a passive safety apparatus 100 using a circulating system of a secondary fluid.

The passive safety facility 100 utilizes a facility that is configured to promote circulation flow away from the conventional manner of using pure natural convection flow. The passive safety apparatus 100 is configured to increase the efficiency of reducing the heat and pressure inside the compartment 12 and the efficiency of removing the radioactive material in a passive manner.

1, the passive safety equipment 100 includes a cooling unit 110, a circulating induction injection mechanism 120, and a filtration facility 130. [

The cooling unit 110 is formed to cool the first fluid discharged from the steam generator 11b together with the second fluid inside the compartment 12. [ The cooling unit 110 discharges the heat transferred from the first fluid and the second fluid to the environment outside the compartment 12 as the first fluid and the second fluid cools.

The cooling section 110 includes an emergency cooling water storage section 111, a heat exchanger 112, a connection pipe 113 and an isolation valve 114.

The emergency cooling water storage unit 111 is formed to store cooling water therein. The cooling water filled in the emergency cooling water storage part 111 receives heat from the first fluid and the second fluid by the heat exchanger 112. When the temperature of the cooling water consumed in the emergency cooling water storage unit 111 rises, the cooling water evaporates and the heat transferred to the cooling water is released to the external environment. At least part of the upper portion of the emergency cooling water storage portion 111 is opened so that the cooling water can be evaporated to the external environment.

The heat exchanger 112 is configured to heat-exchange the cooling water of the emergency cooling water storage part 111 with the first fluid and the second fluid. The heat exchanger 112 may be installed inside the compartment 12 and may be connected to the emergency cooling water storage 111 by a connection pipe 113 passing through the compartment 12. [ The heat exchanger 112 passes the fluid flowing from the emergency cooling water storage part 111 through the connection pipe 113 to cool the first fluid and the second fluid.

An inlet header 112a is provided at an inlet of the heat exchanger 112 to distribute the cooling water supplied from the emergency cooling water storage unit 111 to the internal flow path of the heat exchanger 112. [ At the outlet of the heat exchanger (112), an outlet header (112b) for collecting the heated cooling water from the internal flow path of the heat exchanger (112) is provided.

The connection pipe 113 is connected to the heat exchanger 112 and the emergency cooling water storage unit 111 so as to form a circulation flow path of the cooling water stored in the emergency cooling water storage unit 111. The plurality of connection pipes 113 are connected to the inlet header 112a and the outlet header 112b of the heat exchanger 112, respectively. The connection pipe 113 penetrates at least a part of the compartment portion 12 and extends to the inside of the emergency cooling water storage portion 111.

At the end of the connection pipe 113, a sparger 113 'for spraying cooling water may be installed. The cooling water recovered from the heat exchanger 112 to the emergency cooling water storage part 111 by the connection pipe 113 can be injected into the emergency cooling water storage part 111 by the sparger 113 '.

An isolation valve 114 may be provided in each connection pipe 113. If the system is damaged at the time of an accident, the isolation valve 114 may be closed or isolated, or may be opened or closed at a time required for maintenance.

The cooling unit 110 may be divided according to an operation mechanism of the emergency cooling water storage unit 111 and the heat exchanger 112. 1, the heat exchanger 112 is connected to the emergency cooling water storage part 111 by the connection pipe 113, and the cooling water of the emergency cooling water storage part 111 is continuously connected to the heat exchanger 112 The circulation type cooling unit 110 can be divided into a circulation type. The circulating cooling part 110 uses a natural circulation based on the difference in density due to the difference in temperature or phase of the cooling water.

The cooling unit 110 may be divided into an immersion type or a submerged type in addition to the circulation type, and the constitution of the immersion type and the injection type will be described later.

The circulation induction injection mechanism 120 is formed to inject the first fluid discharged from the reactor coolant system 11 or the steam generator 11b to the cooling unit 110. [ When the first fluid is injected, a local pressure drop is induced in the circulating induction injection mechanism 120. At least a part of the circulation induction injection mechanism 120 is opened toward the inside of the compartment 12 so as to draw the second fluid by a pressure drop caused by ejecting the first fluid. The circulation inducing injection mechanism 120 injects the drawn second fluid together with the first fluid into the cooling part 110. [ The specific structure and operation mechanism of the circulation induction injection mechanism 120 will be described with reference to Figs. 2 and 3. Fig.

2 is a conceptual view of the circulation induction injection mechanism 120 viewed from the front. 3 is a conceptual view of the circulation induction injection mechanism 120 viewed from the side. Referring to FIG. 1, the remaining configuration not shown in FIG. 2 and FIG. 3 will be referred to.

The circulation induction injection mechanism 120 includes a first fluid injection part 121, a second fluid intake part 122b, and a circulating fluid injection part 122.

The first fluid injecting section 121 is connected to the reactor coolant system 11 or the steam generator 11b to inject the first fluid supplied from the reactor coolant system 11 or the steam generator 11b. The first fluid injecting unit 121 may be connected to the steam generator 11b to receive the first fluid from the steam generator 11b as shown in FIG.

The first fluid ejecting part 121 includes a nozzle 121a formed to eject the first fluid. As the first fluid discharged through the nozzle 121a passes through the neck 121a having a small flow path area, its velocity rapidly increases and the pressure decreases. Accordingly, a local pressure drop is induced in the circulation induction injection mechanism 120.

The second fluid inlet 122b is formed annularly around the first fluid jetting portion 121 to draw the second fluid inside the compartment. A pressure difference is formed between the inside and the outside of the circulation induction injection mechanism 120 by the pressure drop caused by the injection of the first fluid. Since the pressure inside the circulation induction injection mechanism 120 is lower than the external pressure, the second fluid existing outside the circulation induction injection mechanism 120 flows through the second fluid intake part 122b to the circulation induction injection mechanism 120).

The circulating fluid injecting portion 122 surrounds the first fluid injecting portion 121 with a portion having an inner diameter larger than that of the first fluid injecting portion 121 so as to form the second fluid receiving portion 122b. Accordingly, an annular second fluid inlet 122b is formed between the outer circumferential surface of the first fluid injecting section 121 and the inner circumferential surface of the circulating fluid injecting section 122.

The circulation induction injection mechanism 120 supplies the first fluid and the second fluid together to the cooling section 110 together. The circulation inducing injection mechanism 120 includes a neck 122a and a diffuser 122c.

The neck 122a is formed with an inner diameter narrower than the circumference to cause a local pressure drop upon ejection of the first fluid. 2 and 3, the neck 122a has a smaller inner diameter than the second fluid inlet 122b and the diffuser 122c.

The diffuser 122c naturally induces the first fluid and the second fluid to the cooling unit 110 without causing a large pressure loss in the first fluid and the second fluid passing through the neck 122a. If the flow of the first fluid and the second fluid that have passed through the neck 122a is not naturally diffused, the flow path resistance increases and the circulation flow rate can be reduced. The diffuser 122c naturally reduces the flow resistance by changing the static pressure to the static pressure so as to smoothly supply the first fluid and the second fluid to the cooling unit 110. [

As shown in FIGS. 2 and 3, the neck 122a and the diffuser 122c are sequentially connected. The inner diameter gradually decreases from the second fluid inlet 122b to the neck 122a and the inner diameter increases again from the neck 122a to the diffuser 122c.

The circulating fluid injecting section 122 injects the first fluid and the second fluid into the heat exchanger 112. The injected first fluid and the second fluid heat-exchange with the cooling water in the heat exchanger (112).

An inlet header 112a is provided at an inlet of the heat exchanger 112 to distribute the cooling water supplied from the emergency cooling water storage unit 111 to the internal flow path of the heat exchanger 112. [ At the outlet of the heat exchanger (112), an outlet header (112b) for collecting the heated cooling water from the internal flow path is provided. A tube 112c is provided between the inlet header 112a and the outlet header 112b and a casing 115 is installed around the tube 112c to protect the tube 112c from accidental debris do.

The circulation inducing injection mechanism 120 is formed to inject the first fluid and the second fluid onto the surface of the heat exchanger 112. However, the flow path between the shell and the tube may be changed according to the design characteristics of the nuclear power plant 10. The first fluid and the second fluid ejected from the circulation inducing injection mechanism 120 are heat-exchanged with the cooling water passing through the inner flow path of the heat exchanger 112 at the surface of the heat exchanger 112 to be cooled and condensed.

Due to the structural features of such a circulating inducing injection mechanism 120, the present invention overcomes the limitations of the prior art which relies on pure natural convection inside the compartment 12 and promotes the circulation of the first fluid and the second fluid The cooling efficiency inside the compartment 12 can be improved.

Referring again to FIG. 1, the casing 115 surrounds the heat exchanger 112 to protect the heat exchanger 112. The casing 115 is configured to receive the first fluid and the second fluid ejected from the circulation induction injection mechanism 120.

The upper portion 115a of the casing 115 is connected to the circulation induction injection mechanism 120. [ The lower portion 115b of the casing 115 is sealed except for the gas piping 173 and the recovery piping 160. [ The intermediate portion 115c connecting the upper portion 115a and the lower portion 115b of the casing 115 surrounds the heat exchanger 112. [

The condensed water formed by cooling the first fluid and the second fluid may be collected in the lower portion 115b of the casing 115.

The filtration facility 170 is connected to the outlet of the cooling section 110 to filter the non-condensable gas emitted from the cooling section 110. In the passive safety equipment 100 shown in FIG. 1, the outlet of the cooling unit 110 refers to the lower portion 115b of the casing 115. The filtration facility 170 collects the filtered radioactive material from the non-condensable gas.

The filtration equipment 170 includes a filter or adsorbent 171 and includes a gas discharge portion 172 and a gas piping 173.

The filter or adsorbent 171 is configured to separate the radioactive material from the non-condensable gas.

The filter can use a high efficiency particle filter (HEPA filter). The gaseous form of radioactive material contained in the non-condensable gas is removed as it passes through the filter. For example, if the radioactive material is iodine, iodine is converted to iodic silver by binding it with silver nitrate through the filter. iodic silver is a form that can be separated from non-condensable gases. The filter is made to form iodic silver by reacting silver nitrate with iodine contained in the non-condensable gas. The filter is then configured to remove the iodic silver from the fluid.

Activated carbon may be used as the adsorbent. The iodine organic compounds combine with the substances impregnated on activated carbon, converted into quaternary ammonium salt form, and adsorbed on activated carbon. The molecular form of iodine is bound to the activated carbon through chemical adsorption. Activated carbon is used as an adsorbent because its internal bonding area is large due to its porous structure. Thus, the adsorbent is made to remove the iodine contained in the non-condensable gas through chemical adsorption by the activated carbon.

However, the filter and the adsorbent described above are only examples, and the types of the filter and the adsorbent in the present invention are not limited thereto.

The gas discharge portion 172 is configured to discharge filtered non-condensable gas into the interior of the compartment 12 while passing through the filter or adsorbent 171. Since most of the radioactive material is collected by the filter or the adsorbent 171, there is almost no radioactive material in the non-condensable gas discharged from the gas discharge portion 172.

The gas piping 173 is connected to the outlet of the cooling unit 110 to supply non-condensable gas to the filter or adsorbent 171. 1, the gas piping may be connected to the lower portion 115b of the casing 115. [

The passive safety apparatus 100 may further include a cooling water storage unit 130, a fluid circulation unit 140, a recovery pipe 160, and an additive injection unit 180.

The cooling water storage part 130 is formed to store the cooling water to be injected into the reactor coolant system 11 or the steam generator 11b. The cooling water reservoir may be installed below the cooling water to collect condensate collected in the lower portion 115b of the casing 115. The cooling water storage unit 130 may be installed at a position higher than the reactor coolant system 11 or the steam generator 11b so that cooling water can be injected by the gravity head.

The cooling water stored in the cooling water storage unit 130 can be used for removing the sensible heat in the reactor coolant system 11 and the residual heat of the core 11a according to the design. The cooling water stored in the cooling water storage unit 130 may be used to be injected into the reactor coolant system 11.

Since the sensible heat and residual heat generated in the core 11a are present in the reactor coolant system 11 in the event of an accident, the sensible heat and residual heat must be removed to safely maintain the core 11a. In this embodiment, the method of circulating the cooling water through the steam generator 11b to remove sensible heat and residual heat is applied. The cooling water storage unit 130 may be connected to the water supply pipe 13a so as to use the cooling water stored therein for the removal of residual heat. This structure refers to the cooling water storage portion 130 shown on the right side of FIG.

Further, in case of an accident such as a loss of coolant, the water level of the reactor coolant system 11 is lowered. Therefore, cooling water should be injected into the reactor coolant system 11 to maintain the water level. The cooling water storage part 130 can be connected to the safety injection pipe 15a by the pipe 115 so as to use the cooling water stored therein for safety injection. This structure refers to the cooling water storage portion 130 shown in the left side of FIG.

The safety injection system 15, which is another safety system of the nuclear power plant 10, injects cooling water into the reactor coolant system 11 to maintain the level of the reactor coolant system 11. The safety infusion set 15 includes several tanks (not shown), a safety infusion line 15a, and a valve 15b, etc., for storing safety infusion water. The safety injection piping 15a connects the tanks to the reactor coolant system 11 and the valve 15b can be installed in the safety injection piping 15a. The cooling water storage part 130 may be connected to the safety injection pipe 15a for safety injection.

As shown in FIG. 1, the cooling water storage unit 130 includes a first cooling water storage unit 130a and a second cooling water storage unit 130b for separately storing pure cooling water to be used for residual heat removal and boric acid water to be used for safety injection, respectively 130b.

The first cooling water storage part 130a stores pure cooling water to be supplied to the steam generator 11b to remove sensible heat inside the reactor coolant system 11 and residual heat of the core 11a. The second cooling water storage part 130b stores the boric acid water to be injected directly into the reactor coolant system 11 so as to maintain the water level of the reactor coolant system 11. [

The fluid circulating part 140 is formed to circulate the cooling water of the cooling water storage part 130 to the circulation induction injection mechanism 120 through the reactor coolant system 11 or the steam generator 11b. The fluid circulating part 140 includes a fluid supply pipe 141 and a steam discharge pipe 142.

The fluid supply pipe 141 is connected to the coolant storage unit 130 to supply the coolant in the coolant storage unit 130 to the reactor coolant system 11 or the steam generator 11b. The fluid supply piping 141 may be connected to the reactor coolant system 11 directly or indirectly. For example, the fluid supply pipe 141 may be connected to the water supply pipe 13a to supply the cooling water to the steam generator 11b as shown in FIG. The fluid supply pipe 141 may be provided with an isolation valve 141a and a check valve 141b.

The steam discharge pipe 142 is connected to the reactor coolant system 11 or the steam generator 11b to circulate the first fluid discharged from the reactor coolant system 11 or the steam generator 11b to the circulation induction injection mechanism 120, Is connected to the induction injection mechanism (120). The steam discharge pipe 142 may be connected to the steam generator 11b to supply the first fluid discharged from the steam generator 11b to the circulation induction injection mechanism 120 as shown in the figure. The steam discharge pipe 142 may be provided with an isolation valve 142a.

The recovery pipe 160 extends from the casing 115 to the cooling water storage portion so as to supply the condensed water collected in the lower portion 115b of the casing 115 to the cooling water storage portion 130. [ The return pipe 160 may be provided with a flow regulator 161a for regulating the flow rate of the condensed water.

When the condensed water is recovered to the cooling water storage part 130 through the recovery pipe 160, the circulation of the cooling water starting from the cooling water storage part 130 is completed once. The fluid circulation does not end in a single cycle, because it induces circulation of the fluid in a passive manner by natural forces. The circulation of the fluid can be continuously continued as long as steam is generated in the reactor coolant system 11 or the steam generator 11b so that sufficient driving force for inducing the circulation of the fluid in the chamber 12 is maintained.

The additive injecting unit 180 injects an additive that suppresses re-volatilization of the condensed water collected in the coolant storage unit 130 into the condensed water. The additive is made to maintain the pH of the condensate above a predetermined value.

The radioactive iodine dissolved in the cooling water is present in the form of anion. Radioiodine can greatly increase the amount of re-volatilization when the pH of the dissolved cooling water is low. This is because, in cooling water having a pH of 7 or lower, the amount of radioactive iodine converted into the volatile form of small-sized iodine (I ₂ ) is greatly increased. In addition, the amount converted to small iodine is also related to the temperature of the dissolved cooling water and the iodine concentration in the solution. The converted primary iodine can be 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. According to the relevant regulatory requirements, when the pH of the dissolving coolant is 7.0 or higher, the amount converted to small-scale iodine is drastically reduced and the re-volatilization can be ignored.

The additive may be, for example, trisodium phosphate. Trisodium phosphate controls the pH of the cooling water to prevent corrosion inside the compartment 12 and re-volatilization of the radionuclide. However, the kind of the additive in the present invention is not necessarily limited thereto. The additive may be added with boric acid which suppresses the reactivity of the core 11a or other additives for suppressing the corrosion of the equipment so as to control the quality of the cooling water storage part 130 passively.

When the water level of the condensed water collected in the first cooling water storage part 130a exceeds the reference water level, the cooling water storage part 130 conveys the condensed water collected in the first cooling water storage part 130a to the second cooling water storage part 130b Respectively. For example, when the water level of the first cooling water storage part 130a gradually increases to exceed the reference water level due to the collection of the condensed water, the condensed water collected in the first cooling water storage part 130a overflows and the second cooling water storage part 130b, Lt; / RTI >

The additive injection unit 180 may be installed in the flow path from the first cooling water storage unit 130a to the second cooling water storage unit 130b to inject the additive into the condensed water flowing into the second cooling water storage unit 130b. Accordingly, the additive injection unit 180 can inject the additive into the condensed water flowing into the second cooling water storage unit 130b.

Hereinafter, the operation of the passive safety equipment when a virtual accident occurs in the nuclear power plant will be described with reference to FIG.

Fig. 4 is a conceptual diagram showing the accidental occurrence of the passive safety equipment 100 shown in Fig. 1 and the nuclear power plant 10 having the same.

The isolation valves 13b and 14b provided in the water supply pipe 13a and the steam pipe 14a are closed and the valves 15b provided in the safety injection pipe 15a are opened. Then, safety injection is performed to the reactor coolant system 11 by the safety injection equipment 15. [

The isolation valve 115a and the check valve 115b are installed in the pipe 115 connecting the second cooling water storage unit 130b and the safety injection pipe 15a. The valve 115b is also opened. Accordingly, when the pressure inside the reactor coolant system 11 decreases, boric acid stored in the second coolant storage unit 130b can be injected into the reactor coolant system 11 by gravity head. The borated water stored in the second cooling water storage part 130b serves to maintain the water level in the reactor coolant system 11 together with the safety injection facility 15. [

The isolation valve 141a and the check valve 141b provided in the fluid supply pipe 141 are also opened and the supply of the cooling water by the gravity head is started from the first cooling water storage part 130a. The cooling water is supplied to the lower inlet of the steam generator 11b through the water supply pipe 13a. The cooling water removes the sensible heat inside the reactor coolant system 11 and the residual heat of the core 11a at the steam generator 11b and is discharged to the upper outlet of the steam generator 11b.

The isolation valve 142a provided in the steam discharge pipe 142 is also opened and the first fluid discharged to the upper portion of the steam generator 11b evaporates through the steam discharge pipe 142. [ The first fluid is supplied to the circulation induction injection mechanism 120 and the circulation induction injection mechanism 120 is driven by the first fluid supplied through the steam discharge pipe 142 from the inside of the compartment 12 by the pressure drop And injects the second fluid into the interior of the casing 115.

The first fluid and the second fluid injected from the circulation induction injection mechanism 120 heat-exchange with the cooling water of the emergency cooling water storage part 111 in the heat exchanger 112. The cooling water in the emergency cooling water storage part 111 is supplied to the heat exchanger 112 through the connection pipe 113 and exchanges heat with the first fluid and the second fluid while passing through the internal flow path of the heat exchanger 112. The cooling water in the emergency cooling water storage part 111 continuously circulates through the connection pipe 113 to the emergency cooling water storage part 111 and the heat exchanger 112.

 The heat is transferred from the first fluid and the second fluid to the cooling water. The first fluid and the second fluid are cooled and condensed, and the cooling water is heated. The cooling water in the emergency cooling water storage part 111 evaporates when the temperature rises. As a result, heat is released to the external environment.

The condensed water formed by cooling and condensing the first fluid and the second fluid in the heat exchanger (112) is collected in the lower portion (115b) of the casing (115). The collected condensed water is guided through the recovery pipe 160 and is recovered to the first cooling water storage part 130a. The circulation of cooling water is continuous and continuous.

When the condensed water is continuously collected in the first cooling water storage part 130a, the water level of the first cooling water storage part 130a gradually increases. As the water level of the first cooling water storage part 130a rises, the condensed water flows into the second cooling water storage part 130b from the first cooling water storage part 130a. In this process, the additive injection unit 180 injects the additive into the condensed water. Accordingly, the re-volatilization of the condensed water flowing into the second cooling water storage part 130b can be suppressed.

The non-condensable gas discharged with the condensed water flows into the filtration facility 170 and is filtered. The non-condensable gas is supplied to the filter or adsorbent 171 through a flow path formed by the gas piping 173. A filter or adsorbent (171) separates the radioactive material from the non-condensable gas. The filtered non-condensable gas is discharged into the interior of the compartment 12 through the gas discharge portion 172.

The present invention has an effect that the concentration of the radioactive material inside the compartment 12 can be reduced early by the filtration equipment 170. [ For the safety of the general public, the Exclusion Area Boundary (EAB) has been set up and the residence of the general public is limited, assuming the accident of the nuclear power plant before the accident. The present invention can reduce the limiting zone boundary distance by the filtration facility (170).

Among the conventional technologies, there has been proposed a method of controlling the concentration of radioactive material in the reservoir and exhaust system (AREVA in France, Westinghouse in the United States, etc.) in order to prevent damage to the storage part in the event of an accident in which the pressure inside the storage part significantly increases, , Filtered Containment Ventilation System (FCVS). The containment and exhaust system is provided with a filtration facility at the boundary between the inside and the outside of the compartment and opens the boundary (using a rupture plate, a valve, etc.) when an accident occurs in which the pressure inside the compartment rises greatly, Of the air is discharged through the filtration equipment.

In the case of a nuclear power plant with conventional containment and ventilation systems, where an overriding design standard (where an overriding design standard means an accident where the internal pressure of the compartment rises significantly above the design pressure) occurs, A rupture plate or a valve installed between the facilities is opened and a flow is formed by a pressure difference formed between the inside and the outside of the compartment (difference between the high pressure formed inside the compartment and the atmospheric pressure outside the compartment). Then, the air (air and steam) inside the compartment is discharged to the outside of the compartment after passing through the filtration facility by this flow.

However, conventional containment and exhaust systems do not work on the occurrence of a design basis accident, where the design basis accident is an accident where the internal pressure of the compartment is within the design pressure range. Therefore, the conventional containment and exhaust system can not lower the concentration of the radioactive material inside the compartment during the occurrence of the design basis accident, so that the amount of radioactive material that leaks to the outside of the compartment can not be significantly suppressed.

Alternatively, the filtration plant 170 of the present invention is configured to operate upon occurrence of any accident, including design basis accident as well as design basis excess accident. The filtration facility 170 is configured to discharge non-condensable gas having a very low radioactive material concentration into the interior of the compartment 12. [ The radioactive material is collected in the filtration facility 170 while passing through the filter or adsorbent 171. The present invention can very effectively reduce the concentration of the radioactive material inside the compartment 12, and thus the amount of radioactive material leaking out of the compartment 12 can be significantly reduced. And, the present invention can reduce the boundary boundary distance.

Hereinafter, another embodiment of the present invention will be described.

5 is a conceptual view of a passive safety equipment 200 and a nuclear power station 20 having the same according to another embodiment of the present invention.

The emergency cooling water storage 211 is installed outside the compartment 22 and the cooling water is stored in the emergency cooling water storage 211.

The heat exchanger (212) is installed inside the emergency cooling water storage part (211). The inlet header 212a and the outlet header 212b of the heat exchanger 212 are connected to a connection pipe 213 passing through the compartment 22, respectively. The connection pipe 213 is connected to the circulation induction injection mechanism 220 to supply the first fluid and the second fluid injected from the circulation induction injection mechanism 220 to the heat exchanger 212. And the other connection piping 213 is connected to the filtration facility 270 to supply condensation water and non-condensable gas formed by the cooling of the first fluid and the second fluid to the filtration facility 270.

The heat exchanger 212 shown in Fig. 5 is immersed in the cooling water of the emergency cooling water storage part 211. Fig. In this respect, the cooling unit 210 of FIG. 5 can be divided into immersion. However, according to the characteristics of the nuclear power plant 20, it is possible to expose the heat exchanger 212 to the atmosphere and install a duct (not shown) without installing the emergency cooling water storage unit 211 The cooling unit 210 may be configured to be air-cooled.

The circulation inducing injection mechanism 220 is connected to the steam discharge pipe 242 to supply the first fluid from the steam generator 21b. The circulation inducing injection mechanism 220 is connected to the connection pipe 213 to inject the first fluid supplied from the steam discharge pipe 242 and the second fluid drawn by the pressure drop into the connection pipe 213.

The heat exchanger 212 passes the first fluid and the second fluid flowing through the connection pipe 213 through the inner flow path and exchanges heat with the cooling water of the emergency cooling water storage part 211.

The filtration facility 270 is installed inside the compartment 22. The compartment 22 is connected to the heat exchanger 212 by connection piping 213 to receive condensed water and non-condensable gas from the heat exchanger 212. The recovery pipe 260 extends from the lower portion of the filtration facility 270 to the first cooling water storage portion 230a to transfer the condensed water supplied to the filtration facility 270 to the first cooling water storage portion 230a.

FIG. 6 is an enlarged conceptual view of the circulation induction injection mechanism 220 shown in FIG.

The structure of the circulation induction injection mechanism 220 is the same as that described above.

When the first fluid is injected from the nozzle 221a of the first fluid injecting section 221, the first fluid passes through the neck 222a having a small flow path area, and the speed is rapidly increased and the pressure is decreased. A local pressure drop is induced in the circulating induction injection mechanism 220. [ A pressure difference is formed in the inside of the circulation induction injection mechanism (220) and the internal space of the compartment (22).

The second fluid is drawn into the interior of the circulation induction injection mechanism 220 from the internal space of the compartment 22 with a relatively high pressure through the second fluid inlet 222b. The first fluid and the second fluid are injected into the connection pipe 213 through the diffuser 222c. Since the circulation induction injection mechanism 220 and the connection pipe 213 are connected, the flow of the first fluid and the second fluid can be greatly increased as compared to the natural circulation.

FIG. 7 is a conceptual diagram showing the accidental occurrence of the passive safety facility 200 shown in FIG. 5 and the nuclear power plant 20 having the same.

When an accident occurs in the nuclear power plant 20, the isolation valves 23b and 24b provided respectively in the water supply pipe 23a and the steam pipe 24a are closed. The isolation valve 241a and the check valve 241b provided in the fluid supply pipe 241 are opened and the isolation pipe 241a and the check valve 241b provided in the pipe 215 connecting the second cooling water storage unit 230b and the safety injection pipe 25a are opened. The valve 215a and the check valve 215b are also opened.

The cooling water in the second cooling water storage portion 230b is safely injected into the reactor coolant system 21 together with the safety injection facility 25. [ The cooling water of the first cooling water storage part 230a is supplied to the steam generator 21b through the fluid supply pipe 241 to remove the sensible heat in the reactor coolant system 21 and the residual heat of the core 21a.

The isolation valve 242a of the vapor discharge pipe 242 is also opened. The first fluid discharged from the steam generator 21b evaporates through the steam discharge pipe 242 and is supplied to the circulation induction injection mechanism 220. [ The second fluid is introduced into the circulation induction injection mechanism 220 and is injected into the connection pipe 213 together with the first fluid. The first fluid and the second fluid are supplied to the heat exchanger (212) through the connection pipe (213). The first fluid and the second fluid are cooled and condensed by the cooling water of the emergency cooling water storage section 211 while passing through the internal flow path of the heat exchanger 212.

The condensed water and the non-condensable gas discharged from the heat exchanger 212 are supplied to the filtration facility 270 through another connection pipe 213. In the filtration facility 270, the condensed water is recovered to the first cooling water storage portion 240a through the recovery pipe 260. [ Non-condensable gas is filtered while passing through filter or adsorbent 271 at filtration facility 270. The filtered non-condensable gas is discharged into the interior of the compartment 22 through the gas discharge portion 272.

FIG. 8 is a conceptual view showing a normal operation of the passive safety equipment 300 and the nuclear power plant 30 having the same according to still another embodiment of the present invention. FIG. 9 is a conceptual diagram showing the accidental occurrence of the passive safety equipment 300 shown in FIG. 8 and the nuclear power plant 30 having the same.

The passive safety equipment 300 is distinguished from the previous embodiment in that it includes a first cooling water storage 330a and does not include a second cooling water storage. The passive safety facility 300 uses the secondary system to remove the sensible heat inside the reactor coolant system 31 and the residual heat from the core 31a. The pure cooling water of the first cooling water storage 330a is supplied to the steam generator 31b for the purpose of removing the residual heat.

The cooling unit 310 shown in FIGS. 8 and 9 is the same as the cooling unit 110 shown in FIG. 1, and thus can be divided into a circulation type. The remaining configuration and operation are the same as those described in Figs. 1 and 4.

FIG. 10 is a conceptual view showing a normal operation of the passive safety equipment 400 and the nuclear power station 40 having the same according to still another embodiment of the present invention. FIG. 11 is a conceptual diagram showing the accidental occurrence of the passive safety facility 400 shown in FIG. 9 and the nuclear power plant 40 having the same.

The passive safety system 400 uses a primary system.

The second cooling water storage part 430b stores the boric acid water to be injected into the reactor coolant system 41 to maintain the water level of the reactor coolant system 41. [ The second cooling water storage portion 430b is connected to the safety injection pipe 45a by the fluid supply pipe 441. [

The steam discharge pipe 442 is connected to the reactor coolant system 41 to supply the first fluid discharged from the reactor coolant system 41 to the circulating induction injection mechanism 420.

The additive injector 480 may be installed in the flow path from the lower portion 415b of the casing 415 to the coolant storage portion 430b to inject the additive into the condensed water collected in the second coolant storage portion 430b. For example, the additive injection unit 480 may be installed at the outlet of the recovery pipe 460. The additive injection unit 480 may inject the additive into the condensed water recovered through the recovery pipe 460 to the second coolant storage unit.

In this embodiment, when a coolant loss event occurs, the first fluid and the second fluid are both primary fluids. However, in case of a steam pipe breakage, the first fluid is the first fluid and the second fluid is the second fluid. The primary fluid circulates in the passive safety equipment 400 from the second cooling water storage part 430b until it is recovered to the second cooling water storage part 430b. The passive safety equipment 400 differs from the previously described embodiment in that it uses a primary system without using the steam generator 41b.

FIG. 12 is a conceptual diagram showing the passive safety equipment 500 according to still another embodiment of the present invention and the normal operation of the nuclear power plant 50 having the same. FIG. 13 is a conceptual diagram showing the accidental occurrence of the passive safety equipment 500 shown in FIG. 12 and the nuclear power plant 50 having the same.

The cooling unit 510 includes a first heat exchanger 512 'and a second heat exchanger 512' '.

The first heat exchanger 512 'is installed inside the compartment 52 to cool the first fluid and the second fluid injected from the circulation induction injection mechanism 520. In this embodiment, immersion is shown as an example. However, according to the characteristics of the nuclear power plant 50, the emergency cooling water storage unit 511 is not provided, the second heat exchanger 512 '' is exposed to the atmosphere, and a duct (not shown) The second heat exchanger 512 '' is installed inside the emergency cooling water storage unit 511. The connection pipe 513 connects the first heat exchanger 512 'and the second heat exchanger 512' to form a waste oil path. The isolation pipe 514 is connected to the isolation valve 514a or the check valve 514b, The second heat exchanger 512 'transfers the heat transferred to the fluid circulating the waste oil path to the cooling water inside the emergency cooling water storage unit 511.

When the first fluid and the second fluid are injected into the casing 515 in the circulating induction injection mechanism 520, the first fluid and the second fluid are cooled by the fluid circulating the waste oil of the first heat exchanger 512 ' And condensed. The condensed water formed by the condensation of the first fluid and the second fluid is collected in the lower portion 515b of the casing 515 and is recovered to the first cooling water storage portion 530a through the recovery pipe 560. [

The fluid in the waste oil passage, which has received heat from the first fluid and the second fluid, flows to the second heat exchanger 512 "through the connection pipe 513. In the second heat exchanger 512" And is transferred from the fluid to the cooling water of the emergency cooling water storage part (511). The emergency cooling water storage part evaporates the cooling water to release heat to the outside. The fluid continues to circulate through the waste oil path and receives the heat of the first fluid and the second fluid.

The cooling unit 510 may further include a replenishing tank 516. [

The replenishing tank 516 is formed to store the replenishing water. The supplementary tank 516 is connected to the connection pipe 513 to supply the makeup water to the waste oil furnace or to receive surplus water to the waste oil. An isolation valve 516b is provided in the pipe 516a that connects the supplementary tank and the connection pipe 513. The isolation valve 516b may be configured to be opened at the time when supply of the makeup water is required, or may be configured to be opened in advance. The fluid in the waste oil passage can be supplied with the replenishing water and can maintain a sufficient water level.

FIG. 14 is a conceptual diagram showing a passive safety facility 600 according to still another embodiment of the present invention and a normal operation of the nuclear power plant 60 having the same.

The emergency cooling water storage unit 611 is installed outside the compartment 62 and the heat exchanger 612 is installed inside the compartment 62. [ The connection pipe 613 includes a first connection pipe 613a to a fourth connection pipe 613d.

The first connection pipe 613a is connected to the emergency cooling water storage unit 611 and the heat exchanger 612 so as to form a flow path for supplying the cooling water of the emergency cooling water storage unit 611 to the heat exchanger 612. [ 14, the first connection pipe 613a indicates a portion extending from the lower portion of the emergency cooling water storage portion 611 to the inlet header 612a of the heat exchanger 612. [ The first connection pipe 613a introduces the cooling water of the emergency cooling water storage portion 211 into the heat exchanger 612 so as to realize the water cooling.

The second connection pipe 613b extends from the heat exchanger 612 to the outside of the compartment 62 to discharge the cooling water of the emergency cooling water storage unit 611 that has passed through the heat exchanger 612 to the outside. 14, the second connection pipe 613b indicates a portion extending from the outlet header 612b of the heat exchanger 612 to the outside of the compartment portion 22 and bending downwardly and extending continuously.

The third connection pipe 613c is branched from the second connection pipe 613b so as to form a flow path for supplying the atmosphere outside the compartment portion 62 to the heat exchanger 612. [ In Fig. 14, the third connection pipe 613c indicates a portion which is branched from the second connection pipe 613b and continues to extend to the outside of the compartment portion 62b. The third connection pipe 613c introduces the atmosphere of the compartment 62 to the heat exchanger 612 so as to realize the air-cooled cooling when the cooling water of the emergency cooling water storage unit 611 becomes exhausted.

The fourth connection pipe 613d is branched from the first connection pipe 613a and extends to the outside of the storage part 62 so as to discharge the heated atmosphere to the outside while passing through the heat exchanger 612. [ In Fig. 14, the fourth connection pipe 613d indicates a portion branched from the first connection pipe 613a and connected to the duct 617. [

The duct 617 is an air circulation system for discharging the atmosphere discharged from the heat exchanger 612.

At least one isolation valve 614a '. 614a', 614b ', 614b', 614c and 614d is installed in each of the connection pipes 613a, 613b, 613c and 613d. Depending on which of the isolation valves 614a '. 614a', 614b ', 614b', 614c and 614d is opened, the cooling medium flowing into the heat exchanger 612 is changed. The cooling method of the cooling unit 610 can be switched to either of the water cooling type and the air cooling type cooling mode according to the opening and closing of the isolation valves 614a '. 614a', 614b ', 614b', 614c and 614d. In this embodiment, the water-cooled type and the air-cooled type are mixed. However, the water-cooled type facility may be removed according to the characteristics of the nuclear power plant,

15 and 16 are conceptual diagrams showing the occurrence of an accident in the passive safety facility 600 shown in FIG. 14 and the nuclear power plant 60 having the same. The passive safety equipment 600 is subjected to the sequential operating procedures of Figs. 15 and 16. Fig.

Referring to FIG. 15, pure cooling water of the first cooling water storage portion 630a is supplied to the steam generator 61b as an accident occurs in the nuclear power plant. The first fluid discharged from the steam generator 61b is supplied to the circulation induction injection mechanism 620 through the steam discharge pipe 642. [ The circulating induction injection mechanism 620 injects the first fluid and the second fluid into the casing 615. [

The isolation valves 614a 'and 614b "provided in the first connection pipe 613a and the second connection pipe 613b are opened by an associated signal in the event of an accident. The first connection pipe 613a and the second connection The other isolation valve 614a '' 614b 'installed in the pipe 613b is opened and closed at a time required for maintenance and is set to be closed when it is necessary to isolate the storage part 62 due to breakage of the system at the time of an accident . The cooling water stored in the emergency cooling water storage unit 611 is injected into the heat exchanger 612 by the gravity head. The cooling water is injected into the heat exchanger 612 through the first connection pipe 613a.

The cooling water injected into the heat exchanger 612 receives heat from the first fluid and the second fluid in the heat exchanger 612. The cooling water is discharged to the outside of the compartment 62 through the second connection pipe 613b. The first fluid and the second fluid are cooled and condensed, and are collected in the lower portion of the casing 615. Non-condensable gases are filtered by filtration facility 670. The condensed water is returned to the first cooling water storage portion via the recovery pipe 660.

The cooling unit 610 shown in FIG. 14 to FIG. 16 may be classified into an injection type in that the cooling water stored in the emergency cooling water storage unit 611 is injected into the heat exchanger 612. The injection type can be divided into gravity injection type and gas injection type again. Gravity injection type injects cooling water based on gravity head. The gas injection type pressurizes the cooling water with the gas filled in the sealed emergency cooling water storage part 211 to inject the cooling water. The cooling unit 610 is divided into the gravity injection type in that the cooling water injection in Figs. 14 to 16 is performed by gravity.

Gravity injection cooling may continue until the cooling water in the emergency cooling water storage portion 611 becomes exhausted. The operation of the passive safety equipment 600 after the cooling water in the emergency cooling water storage unit 611 has been exhausted will be described with reference to FIG.

16, the isolation valve 614b "provided in the second connection pipe 613b is closed and the isolation valves 614c, 614d provided in the third connection pipe 613c and the fourth connection pipe 613d are opened. The air outside the compartment 62 is introduced into the heat exchanger 612 through the third connection pipe 613c. In the heat exchanger 612, The air having passed the heat from the second fluid flows again to the duct 617 through the fourth connection pipe 613d. The atmosphere is discharged to the outside through the duct 617. [

As described with reference to FIGS. 15 to 16, if the cooling is performed by the water-cooling type and the air-cooling type mixing type, the passive safety equipment 600 can more reliably prepare for an accident. In the early stage of an accident in which there is a lot of heat load, cooling is performed by a water-cooled type having a good cooling efficiency, and in the latter half of the accident where the thermal load is reduced, cooling can be continuously performed.

FIG. 17 is a conceptual diagram showing the passive safety equipment 700 and the operation of the nuclear power plant 70 including the same according to still another embodiment of the present invention. Fig. 18 is an enlarged conceptual view of a portion of the passive safety equipment 700 shown in Fig.

The recovery pipe 760 is connected to the lower portion of the casing 715 and extends from the lower portion 715b of the casing 715 to the first cooling water storage portion 730a. The return pipe 760 forms a flow path for the condensed water collected in the casing 715. The condensed water is recovered from the casing 715 through the recovery pipe 760 to the first cooling water storage portion 730a.

A recovery pipe 774 is connected to the lower portion of the filtration facility 770 in addition to the recovery pipe 760 connected to the lower portion 715b of the casing 715. [ The recovery pipe 760 connected to the casing 715 is referred to as a first recovery pipe 760 and the recovery pipe 774 connected to the lower portion of the filtration facility 770 Is divided into a second recovery water pipe 774. The second water supply pipe 774 is connected to the first water supply pipe 760.

The condensed water generated in the cooling process of the cooling unit 710 may be collected in the lower part of the casing 715, but a part of the condensed water may be introduced into the lower part of the filtration facility 770. The condensed water collected in the lower portion 715b of the casing 715 is recovered to the first cooling water storage portion 730a through the first recovery pipe 760. [ The condensed water collected at the lower portion of the filtration facility 770 is recovered to the first cooling water storage portion 730a through the second connection pipe 774.

Referring to FIG. 18, at least a part of the first recovery pipe 760 'forms a height difference from the other part. The use of the first recovery pipe 760 'having such a structure can prevent the discharge of air and prevent the non-condensable gas containing the radioactive material from being discharged through the first recovery pipe 760'.

Figs. 19 to 21 are conceptual diagrams showing the circulation induction injection mechanism 120 and modifications thereof (820, 920).

Fig. 19 shows the circulation induction injection mechanism 120 shown in Fig. 1, and the principle of the jet pump is applied. This is explained in the previous section.

20 and 21 are modifications of the circulation induction injection mechanisms 820 and 920 different from those of FIG. 19, applying the principle of a turbine pump, not a jet pump. The circulation induction injection mechanisms 820 and 920 are connected to the first fluid ejection sections 821 and 921, the second fluid entrances 822b and 922b, the circulating fluid ejection sections 822 and 922, the turbine blades 823 and 923, Pump impellers 924 and 924, respectively.

The turbine blades 823 and 923 and the pump impellers 824 and 924 are installed at the outlets of the first fluid ejecting portions 821 and 921. Using the rotational force of the turbine blades 823 and 923, Thereby promoting the circulation flow inside.

20, the turbine is disposed at a position spaced a predetermined distance from the outlet of the first fluid jetting section 821 and a relatively small turbine blade 823 disposed at the outlet of the first fluid jetting section 821, Lt; RTI ID = 0.0 > 824 < / RTI >

Referring to FIG. 21, the position of the pump impeller 924 is disposed closer to the turbine blade 923 than in the case of FIG.

In the circulating induction injection mechanisms 820 and 920 shown in Figs. 20 and 21, the turbine blades 823 and 923 induce smooth injection of the first fluid, and the pump impellers 824 and 924 induce smooth injection of the second fluid .

The present invention can increase the efficiency of cooling the inside of the compartment by promoting the circulation flow by using the circulation induction injection mechanism instead of merely relying on the natural circulation inside the compartment. It is possible not only to discharge the first fluid discharged from the reactor coolant system directly to the heat exchanger but to discharge the second fluid inside the compartment by the discharge flow of the first fluid, It is possible to increase the size of the heat exchanger for cooling the compartment of the nuclear power plant, increase the cost, and lower the safety.

In addition, the present invention filters non-condensed water by using a filtration facility without releasing it to the inside of the compartment. Therefore, the present invention can lower the concentration of the radioactive material inside the compartment early. The present invention can reduce the boundary zone boundary distance as the concentration of the radioactive material is lowered.

The passive safety equipment described above and the nuclear power plant having the same are not limited to the configuration and the method of the embodiments described above, but the embodiments may be modified such that all or some of the embodiments are selectively combined .

10, 20, 30, 40, 50, 60, 70: Nuclear power plant
11, 21, 31, 41, 51, 61, 71: reactor coolant system
11a, 21a, 31a, 41a, 51a, 61a, 71a: core
11b, 21b, 31b, 41b, 51b, 61b, 71b:
100, 200, 300, 400, 500, 600, 700: Passive safety equipment
110, 210, 310, 410, 510, 610, 710:
120, 220, 320, 420, 520, 620, 720:
130, 230, 330, 430, 530, 630, 730:
140, 240, 340, 440, 540, 640, 740:
160, 260, 360, 460, 560, 660, 760:
170, 270, 370, 470, 570, 670, 770: Filtration equipment
180, 280, 380, 480, 580, 680, 780:

Claims (21)

A cooling unit configured to cool a first fluid discharged from a steam generator discharged from a reactor coolant system or installed inside the reactor coolant system together with a second fluid inside the chamber;
At least a part of which is formed to inject the first fluid discharged from the reactor coolant system or the steam generator to the cooling part and to draw the second fluid by a pressure drop caused by spraying the first fluid, A circulation induction injection mechanism that opens toward the inside of the pouring part and injects the second fluid that has been introduced together with the first fluid; And
And a filtration facility connected to an outlet of the cooling section to filter the non-condensable gas discharged from the cooling section, and to collect the radioactive material filtered from the non-condensable gas. The method according to claim 1,
The circulation induction injection mechanism includes:
A first fluid ejection unit connected to the reactor coolant system or the steam generator to receive the first fluid and configured to eject the supplied first fluid;
A second fluid inlet formed annularly around the first fluid injection portion to draw a second fluid inside the compartment; And
And a circulating fluid ejection unit that encloses the first fluid ejection unit at a portion having an inner diameter larger than that of the first fluid ejection unit to form the second fluid intake unit and supplies the first fluid and the second fluid to the cooling unit Wherein the passive safety device comprises: 3. The method of claim 2,
Wherein the first fluid ejection portion includes a nozzle for ejecting the first fluid to the circulating fluid ejection portion. 3. The method of claim 2,
The circulating fluid jetting unit includes:
A neck formed with a smaller inner diameter than the periphery to cause a localized pressure drop while spraying the first fluid;
And a diffuser for guiding the first fluid and the second fluid passing through the neck to the cooling section. The method according to claim 1,
The filtration system comprises:
A filter or adsorbent configured to separate the radioactive material from the non-condensable gas;
A gas discharge unit configured to discharge the non-condensable gas filtered while passing through the filter or the adsorbent to the inside of the compartment; And
And a gas piping connected to an outlet of the cooling section to supply the non-condensable gas to the filter or the adsorbent. The method according to claim 1,
Wherein the cooling unit forms a condensed water by cooling the first fluid and the second fluid,
Wherein the passive safety equipment further comprises a coolant storage unit configured to store coolant to be injected into the reactor coolant system or the steam generator,
Wherein the cooling water storage portion is installed at a lower portion of the cooling portion to collect the condensed water. The method according to claim 6,
The cooling water storage unit
A first cooling water storage unit for storing pure cooling water to be supplied to the steam generator to remove sensible heat and nuclear residual heat in the reactor coolant system; And
A second cooling water storage part for storing the boric acid water to be injected into the reactor coolant system to maintain the water level of the reactor coolant system; Wherein the at least one of the first and second passages comprises at least one of: 8. The method of claim 7,
The passive safety equipment further comprises an additive injection unit for injecting an additive for suppressing re-volatilization of condensed water collected in the cooling water storage unit into the condensed water,
Wherein the additive is configured to maintain the pH of the condensed water above a predetermined value. 9. The method of claim 8,
Wherein the additive injection unit is installed in a flow path from the cooling unit to the cooling water storage unit to inject the additive into the condensed water collected by the cooling water storage unit. 9. The method of claim 8,
The cooling water storage part collects the condensed water in the first cooling water storage part. When the water level of the collected condensed water exceeds the reference water level, the cooling water storage part introduces the condensed water collected in the first cooling water storage part into the second cooling water storage part , ≪ / RTI >
Wherein the additive injection unit is installed in a flow path leading from the first cooling water storage unit to the second cooling water storage unit to inject the additive into the condensed water flowing into the second cooling water storage unit. The method according to claim 6,
Wherein the passive safety equipment further comprises a fluid circulation unit configured to circulate the cooling water of the cooling water storage unit to the circulation induction injector through the reactor coolant system or the steam generator,
Wherein the fluid circulation unit comprises:
A fluid supply pipe connected to the cooling water storage unit to supply cooling water in the cooling water storage unit to the reactor coolant system or the steam generator; And
And a steam discharge pipe connected to the reactor coolant system or the steam generator and the circulation induction injection mechanism to supply the reactor coolant system or the first fluid discharged from the steam generator to the circulation induction injector. Passive safety equipment. 6. The method of claim 5,
The cooling unit includes:
An emergency cooling water storage unit configured to store cooling water therein and installed outside the storage unit to discharge the heat received by evaporating the cooling water when the temperature rises due to heat transfer;
The first fluid and the second fluid injected from the circulation induction injection mechanism are connected to the emergency cooling water storage part by a connection pipe installed inside the compartment and passing through the compartment, A heat exchanger for exchanging heat with the second fluid; And
And a casing enclosing the heat exchanger so as to at least partially protect the heat exchanger and configured to receive the first fluid and the second fluid ejected from the circulation induction injection mechanism. 13. The method of claim 12,
The connection piping includes:
A first connection pipe connected to the emergency cooling water storage part and the heat exchanger so as to form a flow path for supplying cooling water of the emergency cooling water storage part to the heat exchanger and for introducing the cooling water of the emergency cooling water storage part to the heat exchanger so as to realize water cooling;
A second connection pipe extending from the heat exchanger to the outside of the storage part to discharge the cooling water of the emergency cooling water storage part that has passed through the heat exchanger to the outside;
Wherein the air is branched from the second connection pipe so as to form a flow path for supplying the air outside the compartment to the heat exchanger, and when the cooling water in the emergency cooling water storage part is exhausted, the air outside the compartment is introduced into the heat exchanger A third connecting pipe; And
And a fourth connection pipe branched from the first connection pipe and extending to the outside of the compartment so as to discharge the heated air passing through the heat exchanger to the outside. 14. The method of claim 13,
And a plurality of isolation valves provided respectively in the first connection pipe and the fourth connection pipe and being opened and closed by a predetermined signal so as to switch from the water cooling type cooling to the air cooling type cooling water when the cooling water in the emergency cooling water storage part becomes exhausted Wherein the passive safety device comprises: 13. The method of claim 12,
An upper portion of the casing is opened to receive the first fluid and the second fluid from the circulation induction injection mechanism,
Wherein the lower portion of the casing is configured to collect condensate formed by cooling of the first fluid and the second fluid. 16. The method of claim 15,
Wherein the passive safety equipment includes a recovery pipe extending to the cooling water storage unit to supply condensed water generated in the cooling process of the cooling unit to the cooling water storage unit. 17. The method of claim 16,
Wherein the recovery pipe
A first recovery pipe connected to a lower portion of the casing to form a passage for condensed water collected in the casing; And
And a second recovery pipe connected to a lower portion of the filtration facility to form a passage for condensed water collected in the filtration facility. 6. The method of claim 5,
The cooling unit includes:
An emergency cooling water storage unit configured to store cooling water therein and installed outside the storage unit to discharge the heat received by evaporating the cooling water when the temperature rises due to heat transfer; And
And a second fluid flowing from the circulation induction injection mechanism through the connection pipe to pass the second fluid and the second fluid to the emergency cooling water storage unit, And a heat exchanger for exchanging heat with the cooling water,
Wherein the filtration facility is installed inside the compartment and is connected to the heat exchanger by the connection pipe to receive non-condensable gas and condensed water from the heat exchanger. 6. The method of claim 5,
The cooling unit includes:
An emergency cooling water storage unit configured to store cooling water therein and installed outside the storage unit to discharge the heat received by evaporating the cooling water when the temperature rises due to heat transfer;
A first heat exchanger installed inside the compartment to cool the first fluid and the second fluid injected from the circulation induction injection mechanism; And
The emergency cooling water storage unit being connected to the first heat exchanger by a connection pipe passing through the storage unit to form a waste oil path, the heat transferred to the fluid circulating the waste oil path is stored in the emergency cooling water storage unit And a second heat exchanger for transferring the cooling water to the internal cooling water. 20. The method of claim 19,
Wherein the cooling section further comprises a supplementary tank formed to store supplemental water therein,
Wherein the supplemental tank is connected to the connection pipe to supply supplemental water to the waste oil passage or to receive surplus water to the waste oil. Reactor coolant system;
A compartment for enclosing the reactor coolant system to prevent the radioactive material from leaking to the external environment; And
Circulating the fluid inside the reactor coolant system to remove heat of the reactor coolant system and cooling the first fluid discharged from the reactor coolant system and the second fluid inside the chamber to heat the inside of the chamber, Including passive safety equipment emitting to the outside environment,
The passive safety equipment comprises:
A cooling unit configured to cool a first fluid discharged from a steam generator discharged from a reactor coolant system or installed inside the reactor coolant system together with a second fluid inside the chamber;
At least a part of the second fluid is introduced to the cooling unit by the pressure drop caused by the injection of the first fluid, A circulation induction injection mechanism that opens toward the inside of the pouring part and injects the second fluid that has been introduced together with the first fluid; And
And a filtration facility connected to an outlet of the cooling section to filter the non-condensable gas emitted from the cooling section, and to collect the radioactive material filtered from the non-condensable gas.

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