KR20130047871A - Device for residual heat removal of integrated reactor and its method - Google Patents

Abstract

PURPOSE: A residual heat removal apparatus of nuclear reactor is provided to improving cooling efficiency by reusing coolant for nuclear reactor. CONSTITUTION: A residual heat removal apparatus of nuclear reactor comprises a nuclear reactor, a coolant storage part(200), a steam exhaustion part(300), a first containment vessel(400), and a second containment vessel(500). The coolant storage part is connected to a steam generator to cool the nuclear reactor and disposed at a higher position than the nuclear reactor. The steam exhaustion part changes the steam from the steam generator into steam and exhausts the steam. The nuclear reactor and the coolant storage part are disposed within the first containment vessel. The second containment vessel is provided for cooling the first containment vessel. [Reference numerals] (820) Control unit; (AA) Open state; (BB) Closed state

Description

DEVICE FOR RESIDUAL HEAT REMOVAL OF INTEGRATED REACTOR AND ITS METHOD}

The present invention relates to a residual heat removal apparatus of a nuclear reactor, and more particularly, to a residual heat removal apparatus of a nuclear reactor which can be driven semi-permanently by reusing cooling water for cooling the reactor in the event of an accident.

In general, nuclear power plants are usually composed of more than 100 individual functions, which are largely nuclear reactors, such as a nuclear steam supply system and a steam turbine and generator that runs a generator. It is divided into system and other auxiliary equipment.

Here, when the reactor is stopped due to various accidents after the reactor is heated and the core is heated, there is a need to cool the residual heat of the core installed inside the reactor and the sensible heat of the reactor coolant system in order to prevent secondary accidents. .

However, if the reactor coolant system using the secondary system cannot be cooled due to an accident, in a reactor using passive means such as gravity, the core is removed through the residual heat removal device of the reactor, commonly referred to as the passive residual heat removal system. The remaining heat of and cooling the sensible heat of the reactor coolant system.

Here, referring to FIG. 1, the passive residual heat removal system is composed of an emergency cooling tank 10, a heat exchanger 20, a connecting pipe 30, a valve 40 and a supplement tank 70 and the like.

On the other hand, the steam generator 50 for converting water into steam by the heat generated inside the reactor is connected via a pipe (32, 34) to the heat exchanger 20, commonly referred to as a condensation heat exchanger.

Here, the heat exchanger 20 is disposed inside the emergency cooling tank 10 in which the coolant is stored, converts the steam generated from the steam generator 50 into the water by flowing through the pipe 34, and converts the water into water. The water converted from is introduced into the steam generator 50 again through the pipe (32).

That is, when the reactor is stopped due to an accident and needs to cool the residual heat of the core 60 installed in the reactor and the sensible heat of the reactor coolant system, as shown in FIG. 1, the heat exchanger connection valve 42 is opened.

In addition, the turbine system connecting valve 44 provided to deliver the steam generated by the steam generator 50 to the secondary system and the water supply system connecting valve 46 provided to supply water to the steam generator 50 are closed. .

Here, steam generated from the steam generator 50 is transferred to the heat exchanger 20 through a pipe 34, cooled through heat exchange, converted into water (condensation), and the converted (condensed) water is gravity (density difference). ) Is introduced into the steam generator 50 through the pipe 32, and this circulation process is repeated.

As a result, the passive residual heat removal system removes the residual heat of the core 60 and the sensible heat of the reactor coolant system through the steam generator 50 so that the reactor coolant system is stopped at a high temperature from an arbitrary output operation temperature, that is, the stop cooling system is removed. After cooling to a temperature at which the operation can be started, the stationary cooling system cools the reactor coolant system to room temperature. In general, the stationary cooling system employs a system in which a coolant is forcedly circulated by a pump.

Here, in the conventional passive residual heat removal system, when the cooling water stored in the emergency cooling tank is reduced by evaporation, it is necessary to operate active equipment such as a pump requiring power supply to continuously replenish the reduced cooling water. If a problem occurs in the equipment, the means for removing the residual heat and sensible heat of the reactor coolant system including the reactor core is lost, and accordingly, the accident may be worsened by a serious accident including the core melting.

In addition, the conventional passive residual heat removal system is installed on the outside of the containment vessel is connected to the steam generator through the pipes, so many pipes are required and facilities such as heat exchangers and emergency cooling tanks have disadvantages in terms of economics. .

In addition, since the operator (the driver) who has lost the residual heat and the sensible heat removal means must replenish the cooling water directly, the accident may be aggravated by the operator (operator) action error.

Residual heat removal apparatus of the reactor according to the present invention is derived to solve the above-mentioned conventional problems, and aims to solve the following problems.

In one aspect, the present invention enables semi-permanent operation of a cooling system using passive means by reusing coolant to cool a reactor and cooling using an external atmosphere of a containment container, thereby eliminating the need for power supply and active device operation. It is an object of the present invention to provide an improved residual heat removal device of a nuclear reactor.

In addition, an aspect of the present invention is to provide an apparatus for removing residual heat of a nuclear reactor with improved economic efficiency by simplifying a circulation structure of a coolant (steam and water) by simplifying an entire system.

In addition, an aspect of the present invention is to provide an apparatus for removing residual heat of a reactor capable of excluding a possibility of worsening an accident due to an error of an operator (operator) because an operator (operator) does not have to replenish cooling water separately.

The solution to the problem of the present invention is not limited to those mentioned above, and other solutions not mentioned can be clearly understood by those skilled in the art from the following description.

Residual heat removal apparatus of the reactor according to an embodiment of the present invention is connected to the reactor and the steam generator for cooling the reactor, the cooling water storage unit is disposed at a higher position than the steam generator and generally referred to as a reload tank in the containment vessel And a steam discharge unit connected to the steam generator and discharged from the cooling water storage unit by converting the cooling water into steam from the steam generator, and the reactor and the cooling water storage unit disposed therein and discharged from the steam discharge unit. After the steam is heat-exchanged on the inner surface, the first containment vessel and the first containment vessel are arranged to surround the first containment vessel and are spaced apart from each other and are cooled with water to be introduced into the cooling water storage unit, and at least one opening is formed at one side thereof. Air flowing into the air flows through the space separated from the first containment vessel and the first It may include a second containment is provided to cool the lead container.

In addition, in the residual heat removal apparatus of the reactor according to an embodiment of the present invention, the upper portion of the first containment vessel has a curved shape so that steam may be easily flowed into the cooling water storage unit after cooling with water in the inner surface of the first containment vessel. It may be formed into a structure containing.

In the apparatus for removing residual heat of a nuclear reactor according to an embodiment of the present invention, the steam discharge unit may include steam immersed in the cooling water inside the cooling water storage unit so that steam may be discharged to the cooling water.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention further includes a watering tank portion installed on the second containment vessel, and the watering pipe connected to the watering tank portion and the opening is formed, the watering The water in the tank portion may be discharged to the first containment vessel side through the opening formed in the sprinkling pipe to cool the first containment vessel.

In addition, the apparatus for removing residual heat of a nuclear reactor according to an embodiment of the present invention may further include a cooling tank unit in which water is stored and provided in contact with the first containment vessel to cool the first containment vessel.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention, the detection unit for detecting the occurrence of the accident that needs to remove the residual heat of the reactor by the reactor stop, and receives the detection signal of the detection unit turbine system connection valve and water supply system It may further include a control unit for controlling the operation of closing the connection valve and the operation of opening the cooling water storage connection valve.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention may further include an auxiliary power supply for supplying power for opening and closing the valve when the main power is cut off.

Residual heat removal apparatus of the reactor according to an embodiment of the present invention has at least some of the following effects.

Residual heat removal apparatus of the reactor according to an embodiment of the present invention can be driven semi-permanently by using passive means for reusing the cooling water for cooling the reactor and cooling the first containment vessel using an external atmosphere, the conventional passive residual heat removal It is possible to secure semi-permanent means to remove residual heat and sensible heat in the reactor coolant system including the reactor core without replenishing the coolant in the emergency cooling tank by the power supply and active equipment operation required by the system. It has the effect of excluding the possibility of an accident worsening.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention is formed in a structure in which the upper portion of the first containment vessel includes a curved shape so that the steam is cooled with water and then easily flows to the cooling water storage unit to improve the efficiency of recycling the cooling water. There is a synergistic effect.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention has an effect of releasing steam to the cooling water stored in the cooling water storage unit through the immersion unit to directly cool the steam in the cooling water.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention can cool the first containment vessel through the watering tank unit installed on the first containment vessel, thereby releasing a lot of energy into the first containment vessel. There is an effect that the cooling efficiency of the initial accident is increased.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention can cool the first containment vessel through a cooling tank portion directly contacting the first containment vessel, whereby a lot of energy is stored in the first containment vessel. There is an effect that the cooling efficiency of the initial accident is released.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention has the effect that it is easy to adjust the process of removing the residual heat of the reactor by operating a variety of valves in the event of a detection unit and the controller is installed.

In addition, the residual heat removal apparatus of a nuclear reactor according to an embodiment of the present invention includes an auxiliary power supply unit such as a diesel generator and a battery, and thus the valve can be opened and closed even when the main power is cut off.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention has the effect of reducing the economic cost by simplifying the circulation structure of the coolant (steam and water) as the entire system is simplified.

In addition, the residual heat removal apparatus of the nuclear reactor according to an embodiment of the present invention has an effect of eliminating the possibility of accident deterioration due to an operator (operator) action error because the operator (operator) does not need to supplement the cooling water separately.

The effects of the present invention are not limited to those mentioned above, and other effects not mentioned can be clearly understood by those skilled in the art from the following description.

1 is an operation of the residual heat removal system of the prior art.
2 is a view showing the operation in the normal operation of the residual heat removal apparatus of the reactor according to an embodiment of the present invention.
3 to 5 are cross-sectional views showing respective embodiments of the residual heat removal apparatus of the reactor according to the present invention.

As used herein, the singular forms "a", "an", and "the" include the plural expressions unless the context clearly dictates otherwise. , Number, steps, actions, components, parts, or combinations thereof, and the presence or addition of one or more other features or numbers, steps, actions, components, parts, or combinations thereof It should be understood that it does not exclude.

Hereinafter, the residual heat removal apparatus 1000 of the nuclear reactor will be described in detail with reference to the drawings.

3 to 5, a residual heat removal apparatus 1000 of a nuclear reactor according to an embodiment of the present invention is connected to a reactor 100 and a steam generator 120 for cooling the reactor 100. It may include a coolant storage unit and a coolant storage unit 200 disposed at a higher position than the steam generator 120 and generally referred to as a reloading water tank in a containment vessel.

In addition, the residual heat removal apparatus 1000 of the nuclear reactor according to an embodiment of the present invention is connected to the steam generator 120, the coolant flowing out of the coolant storage unit 200 to the steam from the steam generator 120 It may include a vapor discharge unit 300 is converted and discharged.

In addition, in the residual heat removal apparatus 1000 of the nuclear reactor according to the embodiment of the present invention, the reactor 100 and the cooling water storage unit 200 are disposed therein, and the steam discharged from the steam discharge unit 300 is included. After the heat exchange in the inner surface may be cooled with water may include a first containment container 400 is provided to be introduced into the cooling water storage unit 200.

In addition, the residual heat removal apparatus 1000 of the nuclear reactor according to an embodiment of the present invention is disposed to surround the first containment vessel 400 in a spaced state, at least one opening 510 is formed on one side, Air flowing into the interior through the opening 510 flows through the space separated from the first containment vessel 400 and includes a second containment vessel 500 provided to cool the first containment vessel 400. can do.

Meanwhile, in the present specification, an integrated reactor is mainly described, but is not limited to the integrated reactor, and the residual heat removal apparatus of the reactor according to an embodiment of the present invention is not only applicable to an integrated reactor, but also uses a steam generator in an accident. Therefore, it is found that it is applicable to general reactors that can be cooled.

Hereinafter, each configuration will be described in detail.

In general, the integral reactor is composed of a reactor vessel 110 in which main equipment such as a core 130, a reactor coolant pump, a steam generator 120, and a pressurizer are installed, and constitutes the reactor coolant pump and a steam generator. Main equipment, such as 120 and a pressurizer, is installed in the same one reactor vessel 110 together with the core 130.

A core 130 including a nuclear fuel assembly and related facilities is disposed in the integrated reactor, and high temperature heat is generated in the core 130 according to a nuclear fission reaction.

Here, as shown in FIG. 2, when the reactor 100 is in normal operation, the coolant of the reactor coolant system is forcedly circulated by the reactor coolant pump, whereby the heat generated in the core 130 is steam generator 120. Is transmitted to the secondary system.

However, if an accident such as a power loss or piping breakdown occurs and the reactor coolant system is unable to be cooled through the secondary system, the accident does not worsen due to a serious accident including core melting, and the reactor is cooled according to normal accident mitigation procedures. In order to remove the residual heat of the core 130 and the sensible heat of the reactor coolant system.

In the related art, the residual heat of the core 130 and the sensible heat of the reactor coolant system are cooled through the residual heat removal apparatus of the reactor, which is generally referred to as a passive residual heat removal system.

However, referring to Figure 1, the conventional passive residual heat removal system, as described above, is installed on the outside of the containment vessel is connected to the steam generator 50 through a pipe, so many connection pipes 30 are required, heat exchanger (20) and the emergency cooling tank (10) and the like because it is economically disadvantageous, and if the cooling water stored in the emergency cooling tank (10) evaporated to reduce the reduced cooling water by using an active device must continue to be replenished It had such disadvantages.

Therefore, the residual heat removal apparatus 1000 of the nuclear reactor according to an embodiment of the present invention is installed in the first containment container 400, the cooling water storage unit 200 for supplying the cooling water to solve the above problems, Cooling water evaporated from the steam generator 120 is converted (condensed) into water through heat transfer with the first containment vessel 400, and then flows back into the coolant storage unit 200, and heat transferred to the first containment vessel 400. Since is delivered back to the external atmosphere (environment), it is possible to remove the residual heat of the reactor 100 semi-permanently without additional cooling water.

3 to 5, the coolant storage unit 200 is connected to the steam generator 120 inside the reactor 100 and may be provided to be disposed at a higher position than the steam generator 120.

Here, the coolant storage unit 200 is provided to allow the coolant to be introduced into the steam generator 120 by opening the connection valve 210 of the coolant storage unit when various accidents that require residual heat removal of the reactor by the reactor stop.

That is, if the reactor is stopped due to various accidents after the reactor is operated and the core 130 is heated, the residual heat of the core 130 installed inside the reactor and the sensible heat of the reactor coolant system are prevented in order to prevent secondary accidents. There is a need for cooling.

At this time, the turbine system connection valve 840 provided to deliver the steam generated by the steam generator 120 to the secondary system, and the water supply system connection valve 850 provided to supply water to the steam generator 120 are closed. In addition, the coolant storage connection valve 210 is opened to allow the coolant stored in the coolant storage 200 to be introduced into the steam generator 120.

Here, the cooling water introduced into the steam generator 120 from the cooling water storage unit 200 is converted (evaporated) into steam by the residual heat of the core 130 or the sensible heat of the reactor coolant system, and thus the steam generator 120 Emitted to the outside.

On the other hand, since the cooling water storage unit 200 is disposed at a position higher than the steam generator 120, a water head difference is generated between the cooling water storage unit 200 and the steam generator 120, and is generated from the water head difference. By the gravitational action, the cooling water stored in the cooling water storage unit 200 may be introduced into the steam generator 120 in a passive manner.

In addition, the cooling water storage unit 200 is disposed in the first containment vessel 400, as shown in FIGS. 3 to 5.

Here, when the first containment vessel 400 is formed in the same or similar shape as the cylinder and hemisphere, the cooling water storage unit 200 may be formed to surround the inner wall surface of the first containment vessel 400. have.

As a result, as described later, when steam is converted (condensed) into water by heat transfer with the first containment vessel 400, the water flows along the inner wall surface of the first containment vessel 400 to cool the water. It is possible to flow back into the storage unit 200.

Here, the repetition of the operation enables semi-permanent operation of the residual heat removal apparatus 1000 of the reactor by reusing the coolant and cooling the first containment vessel 400 using the external atmosphere.

3 to 4, the steam discharge unit 300 is connected to the steam generator 120, the cooling water flowing out of the coolant storage unit 200 is converted (evaporated) into steam in the steam generator 120. It may be provided to be discharged through the vapor discharge unit 300.

That is, when the coolant stored in the coolant storage unit 200 is introduced into the steam generator 120 after the coolant storage unit connection valve 210 is opened, the coolant is the residual heat or the reactor coolant inside the core 130. It is converted (evaporated) into steam through sensible heat and heat exchange of the system, and the steam may be provided to flow through the steam discharge unit 300 connected to the steam generator 120.

Here, the steam discharge unit 300 is connected to the steam discharge unit valve 310, the steam discharge unit valve 310 is closed when the reactor 100 is in normal operation, the cooling water storage unit due to various accidents When the connection valve 210 is opened, the steam discharge valve 310 is also opened.

And, as shown in Figure 4, the steam discharge unit 300 is disposed in the first containment vessel 400, the steam flowing out through the steam discharge unit 300 is the first containment vessel ( 400 is exchanged with the inner wall surface of the first containment vessel 400 by flowing in various directions inside.

That is, since the first containment vessel 400 is cooled by air cooling or water cooling as described below, the temperature is lower than that of the steam flowing out through the steam discharge unit 300.

Here, when the steam flowing out through the steam discharge unit 300 flows in the interior of the first containment vessel 400 to move near the inner wall surface of the first containment vessel 400, the steam is the first The heat transfer is made through the containment vessel 400, whereby the steam is converted (condensed) into water and then flows along the inner wall of the first containment vessel 400 to be introduced into the coolant storage unit 200. (See B path).

Meanwhile, the steam discharge unit 300 may include an immersion unit 320 immersed in the cooling water inside the cooling water storage unit 200 so that steam may be discharged to the cooling water.

That is, the steam discharged through the steam discharge unit 300, as shown in Figure 5, the cooling water in the cooling water storage unit 200 through the immersion unit 320 included in the steam discharge unit 300 Can be introduced into.

Here, the steam introduced into the cooling water inside the cooling water storage unit 200 exchanges heat with the cooling water, and when the steam continues to flow into the cooling water, the temperature of the cooling water inside the cooling water storage unit 200 increases.

Accordingly, the cooling water inside the cooling water storage unit 200 is evaporated, and as described above, the vaporized vapor may be introduced into the cooling water storage unit 200 again after heat exchange with the first containment vessel 400. .

In addition, as shown in FIG. 3, the steam discharge unit 300 includes a portion in which steam is directly discharged into the air inside the first containment vessel 400 and the immersion unit 320 to store the cooling water storage unit. 200 may be provided to include all of the portion outflow of the steam into the cooling water.

3 to 5, in the first containment vessel 400, a reactor 100 and a coolant storage unit 200 are disposed in the first containment vessel 400 and are discharged from the vapor discharge unit 300. The steam may be heat-exchanged on the inner surface of the first containment vessel 400 and then cooled with water to be introduced into the cooling water storage unit 200.

Here, the first containment vessel 400 is disposed inside the second containment vessel 500 in which one or more openings 510 are formed at one side thereof, and the first containment vessel 400 and the second containment vessel ( Spaces may be provided between the spaces 500).

3 to 5, air is introduced through the opening 510 formed at one side of the second containment container 500, and the air introduced through the opening 510 is the first. It rises through the space formed between the containment vessel 400 and the second containment vessel 500, and forms a natural convection flow structure flowing out through the outlet formed on the second containment vessel 500 (see A path). ).

Here, the air introduced through the opening 510 formed at one side of the second containment vessel 500 exchanges heat with the first containment vessel 400 through heat transfer, whereby the first by air cooling Cooling of the first containment vessel 400, that is, cooling of the first containment vessel 400 by air introduced through the opening 510 is possible.

On the other hand, the first containment vessel 400 of the first containment vessel 400 so that the steam on the inner surface of the first containment vessel 400 can be easily flowed to the cooling water storage unit 200 after cooling with water. The upper portion may be formed in a structure including a curved shape.

Here, the curved shape may be all or part of a circular shape or an elliptical shape, may be a part of a parabolic shape, or it may be a concept including various various curved shapes.

That is, as described above, the steam flowing out through the steam discharge unit 300 is moved to the inner wall surface of the first containment vessel 400 and converted into water through heat transfer with the first containment vessel 400 ( Condensation) and then flows along the inner wall of the first containment vessel 400 to be introduced into the cooling water storage unit 200.

Here, the steam discharged from the steam discharge unit 300 is converted (condensed) to water by heat exchange with the first containment vessel 400 through heat transfer, and then the surface of the first containment vessel 400 by an adhesive force, etc. It can be attached to.

Then, the water attached to the inner wall surface of the first containment vessel 400 is then flowed down along the surface of the first containment vessel 400 by the action of gravity.

Here, as described above, the cooling water storage unit 200 may be provided on the inner wall surface of the first containment container 400 to surround the inner wall surface of the first containment container 400. Condensed water flowing down the surface of the inner wall of the containment vessel 400 may be introduced into the cooling water storage unit 200.

On the other hand, the first containment vessel 400 is provided to be cooled in various ways to condense the steam discharged from the steam discharge unit 300 with water.

That is, as described above, the first containment vessel 400 may be cooled by air by air circulating through a space formed between the first containment vessel 400 and the second containment vessel 500. .

In addition, as shown in Figure 4, the watering tank 600 is installed on the second containment vessel 500, the watering pipe connected to the watering tank 600, the opening 615 is formed ( Including 610, the water of the watering tank 600 is discharged to the first containment container 400 through the opening 615 formed in the watering pipe 610 to the first containment container 400 It may be provided to cool.

Here, as shown in FIG. 4, when the sprinkling pipe valve 620 is opened, water stored in the sprinkling tank part 600 flows through the sprinkling pipe 610 connected to the sprinkling tank part 600. .

Water flowing through the sprinkling pipe 610 is discharged to the first containment vessel 400 side according to the passive method by the gravity action through the opening 615 formed in the sprinkling pipe 610 is the first containment vessel ( 400).

On the other hand, the first containment vessel 400 can be cooled through the cooling tank portion 700 in contact with the first containment vessel 400.

That is, referring to Figure 5, the cooling tank 700 is stored in the water, the contact with the first containment container 400 is provided to cool the first containment container 400 through heat transfer. Can be.

Here, although FIG. 5 illustrates that the cooling tank part 700 contacts only one side of the first containment container 400, this is only one example, and the cooling tank part 700 may be formed in various forms. It may be provided to contact the outer wall surface of the containment container (400).

In addition, it may be formed of one or more numbers depending on the degree of cooling required.

In addition, although the cooling tank part 700 is shown to protrude to the outside of the second containment container 500 in FIG. 5, such a structure is also merely one example, and the cooling tank part 700 is the second. It may be configured to be sealed inside the containment container 500.

On the other hand, the cooling method of the first containment container 400, that is, the cooling method by the air, the cooling method by the water spray tank 600, the cooling method by the cooling tank unit 700 may be individually applied, Note that it can also be applied by a plurality of combinations.

That is, the cooling of the first containment container 400 is a cooling method using only air cooling, a cooling method using a combination of an air cooling system and a water spray tank unit 600, a method using a combination of an air cooling system and a cooling tank unit 700, and an air cooling type. And the cooling method by the combination of the watering tank 600 and the cooling tank 700 may be considered.

3 to 5, the second containment vessel 500 is disposed to surround the first containment vessel 400 in a spaced apart state, and at least one opening 510 is formed at one side thereof, and the opening 510 is formed. The air flowing into the through () may flow through the space separated from the first containment vessel 400 and may be provided to cool the first containment vessel 400.

Here, the operation of the air introduced through the space formed between the second containment vessel 500 and the first containment vessel 400 to cool the first containment vessel 400 is as described above.

Meanwhile, the openings 510 formed in the second containment container 500 may be configured in various shapes, sizes, and numbers, and the position where the openings 510 are formed may also be changed as necessary.

2 to 5, the detector 810 is provided to detect an occurrence of an accident requiring removal of residual heat of the reactor by stopping the reactor.

Here, the detection unit 810 means various means for detecting an accident of a reactor, such as pressure, water level, temperature, nuclear reactivity, radiation dose, and stops the nuclear reaction of the reactor core 130 when various accidents occur. In order to cool the reactor by safely cooling the residual heat of the reactor 130 and the sensible heat of the reactor coolant system, it is installed to detect various accidents that may occur in the reactor.

On the other hand, the control unit 820 is provided to control the operation of the various valves, the operation of closing the turbine connection valve 840 and the water supply system connection valve 850 by receiving the detection signal of the detection unit 810 and the coolant It is provided to regulate the operation of opening the reservoir connection valve (210).

That is, after the reactor stops, if the cooling of the reactor coolant system using the secondary system is impossible, as shown in Figures 3 to 5, the cooling water storage connection valve 210 is opened.

In addition, the turbine system connection valve 840 provided to deliver the steam generated by the steam generator 120 to the secondary system and the water supply system connection valve 850 provided to supply water to the steam generator 120 are closed. .

Here, the steam generated from the steam generator 120 is discharged through the steam discharge unit 300 and then converted (condensed) into water through heat exchange with the first containment vessel 400 to condense the cooling water storage unit 200. Inflow to the cooling water storage unit 200, the water is introduced to the steam generator 120 by the gravity (density difference) through the connection pipe 830 to repeat the circulation process, the first containment vessel ( Heat transferred to 400 is transferred back to the outside atmosphere.

As a result, the residual heat removal apparatus 1000 of the nuclear reactor according to an embodiment of the present invention removes residual heat of the core 130 and sensible heat of the reactor coolant system through the steam generator 120, thereby arbitrarily outputting the reactor coolant system. By cooling from the temperature to the high temperature stop state, the cooling system is cooled down to a temperature at which the operation can start.

In addition, the residual heat removal apparatus 1000 of the nuclear reactor according to an embodiment of the present invention, when the cooling of the residual heat and sensible heat of the reactor using the static cooling system is impossible due to power loss or equipment failure after the operation of the static cooling system is started. In addition, the remaining heat and sensible heat of the nuclear reactor can be semi-permanently removed by the residual heat removal apparatus 1000 of the nuclear reactor according to an embodiment of the present invention, so that an accident may be prevented from worsening.

2 to 5, the auxiliary power supply 900 is provided to supply power for opening and closing the valve when the main power is cut off.

Here, in normal operation of the reactor, the main power is connected, and the main power supplies power to open and close various valves.

However, when the main power is disconnected due to an accident, the auxiliary power supply 900 may supply power for opening and closing various valves.

Here, the auxiliary power supply 900 may be provided as a diesel generator or a battery.

Hereinafter, the effect of the embodiment on the residual heat removal apparatus 1000 of the reactor will be described.

First, when the reactor is stopped due to an accident, but the cooling of the reactor coolant system using the secondary system is impossible, the cooling water storage connection valve 210 and the steam discharge unit 300 is opened, the turbine system connection valve (840) ) And the water supply system connecting valve 850 is closed.

Next, the coolant stored in the coolant storage unit 200 is introduced into the steam generator 120 through the connection pipe 830 to remove the residual heat of the core 130 and the sensible heat of the reactor coolant system through heat exchange and then evaporate into steam.

Next, the vapor evaporated in the steam generator 120 is discharged through the steam discharge unit 300.

Here, the steam discharge unit 300 may be provided to directly discharge the steam to the air is exposed to the air in the first containment container 400 (see FIG. 4), or the cooling water in the cooling water storage unit 200 It may be provided to discharge the steam to the cooling water, including the immersion unit 320 submerged in (see FIG. 5), the portion to directly discharge the steam to the air and the portion to discharge the steam to the cooling water by the immersion unit 320 It may be arranged to include all (see FIG. 3).

Next, the steam discharged through the steam discharge unit 300 flows near the first containment vessel 400, and the flowed steam is condensed into water by heat exchange on the inner wall of the first containment vessel 400 and then It flows along the wall surface of the first containment vessel 400 to be introduced into the coolant storage unit 200.

Next, the water introduced into the cooling water storage unit 200 is introduced into the steam generator 120 by gravity (density difference) through the connection pipe 830 again, and repeats the above circulation process. Since the heat transferred to the containment vessel 400 is finally discharged to the outside atmosphere, thereby it is possible to remove the residual heat of the core 130 and the sensible heat of the reactor coolant system.

It is to be understood that within the scope of the technical idea included in the specification and drawings of the present invention, the description of the present invention, the present embodiment, and the drawings attached hereto are only a part of the technical idea included in the present invention, The present invention is not limited to the above-described embodiments, and various modifications and changes may be made without departing from the scope of the present invention.

100 reactor 110 reactor vessel
120: steam generator 130: core
200: Cooling water storage unit 210: Cooling water storage connection valve
300: steam outlet 310: steam outlet valve
320: immersion unit 400: the first containment vessel
500: second containment container 510: opening
600: watering tank 610: watering pipe
620: watering pipe valve 615: opening
700: cooling tank unit 810: detection unit
820: control unit 830: connection piping
840: turbine system connecting valve 850: water supply system connecting valve
900: auxiliary power supply 1000: residual heat removal device of the reactor

Claims (7)

nuclear pile;
A cooling water storage unit connected to a steam generator for cooling the reactor and disposed at a position higher than the steam generator;
A steam discharge unit connected to the steam generator and configured to convert the cooling water discharged from the cooling water storage unit into steam in the steam generator;
A first containment vessel disposed inside the reactor and the cooling water storage unit, the first discharge vessel being cooled to water and introduced into the cooling water storage unit after the steam discharged from the steam discharge unit is heat-exchanged at an inner surface thereof; And
Is disposed to surround the first containment container in a spaced apart state, one or more openings are formed on one side, the air flowing into the interior through the opening flows through the space separated from the first containment container and the first A second containment vessel provided to cool the containment vessel;
Residual heat removal apparatus of the reactor comprising a. The method of claim 1,
Residual heat removal apparatus of the reactor, characterized in that the upper portion of the first containment vessel is formed in a structure including a curved shape so that the steam on the inner surface of the first containment vessel can be easily flowed to the cooling water storage after cooling with water. The method of claim 1,
And the steam discharge unit includes an immersion unit submerged in the cooling water inside the cooling water storage unit so that steam can be discharged to the cooling water. The method of claim 1,
And a watering tank unit installed on the second containment vessel and a watering pipe connected to the watering tank part and having an opening, wherein the water of the watering tank part is opened through the opening formed in the watering pipe. Residual heat removal apparatus of the reactor, characterized in that discharged to the container side is provided to cool the first containment vessel. The method of claim 1,
Residual heat removal apparatus of the nuclear reactor, characterized in that it further comprises a cooling tank unit is stored in the water and is in contact with the first containment vessel to cool the first containment vessel. The method according to any one of claims 1 to 5,
A detector for detecting an accident that needs to remove residual heat from the reactor by stopping the reactor, an operation of closing the turbine system connection valve and the water supply system connection valve by receiving the detection signal of the detection unit, and opening the connection valve of the coolant storage unit. Residual heat removal device of the reactor, characterized in that it further comprises a control unit for adjusting. The method according to any one of claims 1 to 5,
Residual heat removal device of the reactor, characterized in that further comprising a secondary power supply for supplying power for opening and closing the valve, when the main power is cut off.

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