KR101605725B1 - Nuclear reactor - Google Patents

Abstract

The present invention provides a nuclear reactor for minimizing a connection nozzle. The nuclear reactor includes an external container which stores cooling water and forms the appearance of a reactor container; an internal container which is installed in the internal space of the external container to separate a first region of storing the cooling water from a second region of an atmosphere environment; a cover which covers at least a part of the reactor container and forms a pressure boundary by using the external container and the internal container; and a control rod driving device which controls the insertion or withdrawal of the control rod and is installed in the second region of the atmosphere environment to prevent water leaks or discharge due to the exposure of the cooling water.

Description

NUCLEAR REACTOR

The present invention relates to a reactor having an inner vessel and an outer vessel, respectively.

Reactors are classified according to the installation location of main equipment (steam generator, pressurizer, reactor coolant pump, etc.). The main equipment of a separate reactor (eg domestic pressurized water reactor) is installed outside the reactor, and the main equipment of the integral reactor (eg SMART reactor) is installed inside the reactor vessel.

The reactor is also divided according to whether it allows boiling of the cooling water. The pressurized light water reactor does not pressurize the inside to allow boiling, and the boiling light water reactor is made to allow boiling.

In reactors, control rods are used to control the reactor core (nuclear reaction). The control rod is operated by a control rod drive mechanism (CRDM). The control rod is largely classified into a control rod and a stationary control rod.

Controls (for maneuvering and steady-state only) The control rod provides a means of controlling the reactivity of the core by controlling the amount of insertion when the reactor is in normal operation. The stationary control rod provides sufficient reactivity suppression means at reactor shutdown. The control and stop control rods function to shut down the reactor when emergency stop of the reactor is required, by interrupting the power supply and urgently interrupting the reactor by force of gravity, pressure or spring.

The stationary control rod compensates for the change in reactivity between the low temperature zero output state and the high temperature zero output state. The starting control rod compensates for the change in reactivity between the high temperature zero output state and the high temperature full output state. The operation control rod functions to compensate for the change in the combustion degree of the fuel with the passage of the operation time.

A control rod drive device, which is generally commercially available and applied to a reactor, is installed outside the reactor vessel. In the commercial pressurized light water reactor, an upper insertion type control rod drive device installed on the upper part of the reactor is used, and a lower insertion type control rod drive device installed in the lower part of the reactor is used in commercial boiling light water reactor.

However, since the external control rod drive unit installed outside the reactor vessel is installed in the nozzle passing through the reactor vessel, the control rod drive unit forms part of the reactor pressure boundary together with the nozzle. Accordingly, there is a possibility that the control rod driving apparatus is damaged, and thus it is impossible to exclude a coolant loss accident or a control rod exit accident.

Therefore, as a part of efforts to improve the safety of nuclear power plants (nuclear power plants) by eliminating these accidents, studies are being conducted on built-in control rod driving devices in which control rod driving devices are installed inside reactor vessels. In this study, by installing a number of control rods, a non - boric core is implemented to minimize the number of related facilities, simplify reactor vessel penetration design, and reduce the amount of radioactive waste.

The built-in control rod drive system was developed especially for the development of small-sized reactor (SMR) (including Babcock & Wilcox mPower, USA, Westinghouse Inc. IRIS, USA Westinghouse Company WEC-SMR , IMR of Mitsubishi Heavy Industries (Japan), CAREM (CNEA of Argentina)). In Japan, development of a control rod drive system for boiling light water reactors is underway. The built-in control rod drive system which is currently being developed or studied is largely driven by a motor drive system and a hydraulic drive system, as well as a liquid metal system such as the MP98 of France.

The built-in control rod drive system has various advantages such as prevention of the deviation from the control rod, easy implementation of the non-boric core, utilization of the reactor vessel space, and miniaturization of the reactor vessel and the containment building. However, when the control rod drive unit is placed inside the reactor vessel, it must be operated in a high temperature, high pressure, high activity primary cooling water environment. Therefore, it is necessary to develop the core parts of the internal control rod drive unit. In order to reduce the size of the control rod drive system,
Other techniques for the background of the invention refer to the following prior patent documents.
Korean Patent Publication No. 2000-0025702 (May.

It is an object of the present invention to provide a reactor having a structure capable of fundamentally solving the problem of a reactor having a conventional external control rod drive apparatus.

It is another object of the present invention to provide a reactor having a configuration capable of minimizing connection nozzles and the like passing through a pressurizer.

Another object of the present invention is to propose a reactor having a configuration capable of fully utilizing the internal space of the reactor vessel.

Another object of the present invention is to propose a reactor having a configuration in which a control rod driving device can be installed close to a reactor core.

Yet another object of the present invention is to selectively provide a reactor having a configuration capable of fundamentally shutting off the occurrence of a coolant loss accident or a control rod departure accident due to breakage of the control rod drive apparatus while mitigating environmental requirements of the control rod drive apparatus .

In order to achieve the above object, according to one aspect of the present invention, there is provided a nuclear reactor comprising: an outer vessel configured to store cooling water therein and forming an outer appearance of a nuclear reactor vessel; An inner container installed in an inner space of the outer container so as to spatially separate a first region storing the cooling water and a second region of the atmospheric environment; A cover that covers at least a portion of the reactor vessel and forms a pressure boundary with the outer vessel and the inner vessel; And a control rod driving device installed in the second region of the atmospheric environment to control insertion or withdrawal of the control rod and prevent water leakage or discharge due to exposure to the cooling water.

According to one example of the present invention, the control rod driving apparatus includes: a first control rod driving device for driving a control rod for starting and normal operation of the reactor and emergency stop of the reactor; And a second control rod driving device for driving a stationary control rod for emergency stop of the reactor, wherein the first control rod driving device and the second control rod driving device are arranged to form a height difference with respect to each other.

According to another embodiment of the present invention, a steam generator for heat exchange between a primary fluid and a secondary fluid is provided between the outer vessel and the inner vessel, As shown in FIG.

According to another embodiment of the present invention, a steam generator for heat exchange between a primary fluid and a secondary fluid is installed between the outer container and the inner container, and the casing and the tube constituting the flow path of the secondary fluid are connected to each other through a pressure- As shown in FIG.

Some of the outer vessels may have a cross-sectional area of an enlarged radius than the other portion corresponding to the size of the steam generator.

According to another embodiment of the present invention, the outer container is formed by a combination of a first outer container at a lower portion and a second outer container at an upper portion, and an intermediate separating portion is provided between the first outer container and the second outer container. Plate can be placed.

According to another example of the present invention, the cover may cover both the outer container and the inner container so as to seal both the first region and the second region.

The lid includes: a first lid formed in an annular shape to cover the first region; And a second cover corresponding to the inner container to cover the second area.

According to another embodiment of the present invention, the cover may be formed in an annular shape to cover the first area and open the second area.

According to another embodiment of the present invention, a cooler may be installed on the inner circumferential surface of the inner container to remove the heat of the second area.

According to another embodiment of the present invention, the reactor may further include a heat insulating material installed on an inner circumferential surface of the inner vessel to suppress heat transfer from the cooling water to the second region.

According to another embodiment of the present invention, a support structure for supporting the inner container from external pressure is formed on the inner circumferential surface of the inner container, and the support structure may be formed in an annular shape corresponding to the inner circumferential surface of the inner container.

According to another embodiment of the present invention, the reactor further includes a pressurizer that maintains a pressurized state exceeding a saturated pressure of the cooling water so as to suppress boiling of the cooling water, and the pressurizer is disposed between the outer container and the inner container As shown in FIG.

The reactor comprising: an insulation surrounding the pressurizer to mitigate heat loss; A pusher tube structure formed at a lower portion of the pusher; And a cushioning space formed in the lower portion of the shim tube structure to mitigate heat loss.

According to another embodiment of the present invention, the reactor further comprises a reactor coolant pump for promoting circulation of the coolant stored in the outer vessel, and the reactor coolant pump may be installed in the outer vessel or the cover.

According to another example of the present invention, the reactor may further include a circulator configured to promote circulation of the air present in the inner vessel.

According to the present invention having the above-described structure, since the control rod driving apparatus is installed close to the core and installed in the atmospheric environment, it is possible to overcome the conventional difficulties of leakage, discharge, and high temperature and high pressure environment.

Further, since the pusher is disposed in the annular space above the reactor vessel, which is relatively inefficient, the present invention minimizes the number of connecting nozzles such as a meter or the like that occurs when the pressurizer is centrally disposed, and simplifies the configuration of the pusher. Thus, the safety of the nuclear reactor can be improved.

Further, according to the present invention, it is possible to prevent the control rod from escaping when the lid is provided on the inner container, and it is possible to prevent the control rod from being expanded due to the loss of the coolant during the breakage of the control rod driving device. The possibility of an accident can be remarkably lowered.

1 is a conceptual view of a nuclear reactor according to an embodiment of the present invention;
2 is a conceptual view of a reactor according to another embodiment of the present invention;
3 is a conceptual view of a nuclear reactor according to another embodiment of the present invention.
FIG. 4 is a conceptual view of a nuclear reactor according to another embodiment of the present invention. FIG.
5 is a conceptual view of a nuclear reactor according to another embodiment of the present invention.
6 is a conceptual view of a nuclear reactor according to another embodiment of the present invention.
7 is a conceptual view of a nuclear reactor according to another embodiment of the present invention.
8 is a conceptual view of a nuclear reactor according to another embodiment of the present invention.
9 is a conceptual view of a nuclear reactor according to another embodiment of the present invention.
10 is a conceptual view of a nuclear reactor according to another embodiment of the present invention.
11 is a conceptual view of a nuclear reactor according to another embodiment of the present invention.

Hereinafter, a reactor according to the present invention 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 diagram of a reactor 100 according to an embodiment of the present invention.

The reactor 100 refers to a device in which the nuclear reaction is maintained on its own. Generally, the reactor 100 includes a reactor vessel 110, and the reactor vessel 110 stores cooling water. In the present invention, the reactor vessel 110 is developed in the conventional concept and includes an outer vessel 111 and an inner vessel 112.

The outer container 111 is configured to store cooling water therein. The outer vessel 111 is an element forming the outer appearance of the reactor vessel 110 and can be accepted as a concept similar to the conventional reactor vessel 110. The outer container 111 is provided with an opening at its upper end, and the remaining area except the opening is sealed to prevent leakage of the cooling water, except for a portion necessary for installation of the connection nozzle and the like.

The inner vessel 112 is installed in the inner space of the outer vessel 111. Specifically, the inner vessel 112 is formed to have a smaller height and a smaller radius than the outer vessel 111. The inner vessel 112 is installed at a position higher than the core 101. A space for installing the core 101 is formed between the bottom surface of the inner container 112 and the bottom surface of the outer container 111. An annular space is formed between the side surface of the inner container 112 and the side surface of the outer container 111, Is formed.

Like the outer container 111, the inner container 112 has an opening at its upper end, and the remaining area except the opening is sealed to prevent the inflow of the cooling water, except for the portion necessary for the installation of the control rod 135 and the like .

The inner space of the outer container 111 is separated into two regions by the inner container 112. [ In this specification, the area between the inner container 112 and the outer container 111 is referred to as a first area 111a, and the area defined by the inner container 112 and surrounded by the first area 111a is referred to as a first area 111a. 2 region 112a.

The first region 111a is a region for storing cooling water. Accordingly, the first region 111a corresponds to the cooling water environment. In contrast, the second region 112a is spatially separated from the first region 111a and corresponds to an atmospheric environment.

The lid 120 is configured to cover at least a part of the reactor vessel 110. The lid 120 is formed to be engageable with at least one of the outer container 111 and the inner container 112. The cover 120 shown in Fig. 1 covers both the outer container 111 and the inner container 112 to seal both the first area 111a and the second area 112a.

The lid 120 forms a pressure boundary with the outer vessel 111 and the inner vessel 112. The cooling water stored in the outer vessel 111 is fluid of the primary system, and the fluid of the primary system is separated from the atmospheric environment by the pressure boundary.

The lid 120 of the type shown in Figure 1 seals both the first region 111a and the second region 112a so that even if a portion of the inner vessel 112 is broken, . Accordingly, the lid 120 can prevent the leakage of the cooling water to the atmospheric environment.

As shown in FIG. 1, a nuclear reactor 101, a steam generator 140, a reactor coolant pump 180, a pressurizer 170, a control rod 135, a control rod drive unit 130, A heat insulating material 160 and a cooler 150 are installed. These components are installed at different positions according to need, and in particular, in the present invention, the installation position of the control rod driving device 130 has an important meaning.

The core 101 is installed in the first region 111a. The core 101 is the center of the reactor 100 where it obtains energy by nuclear fission of the nuclear fuel.

The control rod 135 is arranged to control the reactivity of the fission occurring in the core 101 according to the degree of insertion into the core 101 or withdrawal from the core 101.

The control rod driving device 130 is configured to regulate the insertion or withdrawal of the control rod 135. In the conventional built-in type control rod driving apparatus, since the control rod driving device 130 is installed inside the reactor vessel 110, it is exposed to the cooling water, and there is a problem of leakage or discharge due to exposure to the cooling water. Further, since the control rod driving device 130 is installed inside the reactor vessel 110, there is a design difficulty that can withstand high temperature and high pressure environments.

In the present invention, the control rod driving device 130 is installed in the second region 112a of the atmospheric environment to overcome the problem of the built-in control rod driving device. Therefore, the operating environment of the control rod driving device 130 becomes the air (air). Since the atmosphere is applied to the operating environment of the control rod driving device 130, the present invention can overcome the conventional leakage or discharge problem and the design difficulty of the high-temperature high-pressure environment.

Particularly, in the integrated reactor, the upper space of the core 101 has a low space utilization efficiency. In the present invention, since the space is used as an arrangement space of the control rod drive unit 130, the reactor 100 and the control rod drive unit 130 It has the advantage of optimizing space.

The control rod driving device 130 is installed in the second region 112a and the core 101 is installed in the first region 111a so that the control rod driving device 130 is inserted into the core 101 or inserted into the core 101, The control rod 135 is passed through the boundary between the first region 111a and the second region 112a. Specifically, since the boundary between the first region 111a and the second region 112a is formed by the inner vessel 112, the control rod 135 penetrates at least a part of the inner vessel 112. [ For example, as shown in FIG. 1, the control rod 135 may penetrate the bottom surface of the inner vessel 112.

The steam generator 140 is installed in the first region 111a. Specifically, the steam generator 140 may be installed in an annular space formed between the outer vessel 111 and the inner vessel 112. The steam generator 140 is for heat exchange between the primary fluid and the secondary fluid, and generates steam using heat transmitted from the core 101.

Generally, the lower inlet of the steam generator 140 is connected to a water supply system (not shown) by a water supply pipe (not shown), and the upper outlet of the steam generator 140 is connected to a turbine system (not shown) Lt; / RTI > However, FIG. 1 is only an example, and the installation position of the water supply pipe or the steam pipe in the present invention is not particularly limited. The water supplied to the steam generator 140 through the water supply pipe during normal operation of the nuclear power plant is heated in the steam generator 140 to be steam. The steam is supplied to the turbine system through the steam pipe.

In the steam generator 140 shown in FIG. 1, the flow path of the primary fluid is formed by the outer circumferential surface of each tube 142 and the inner circumferential surface of the casing (not shown). The flow path of the secondary fluid is formed by the headers 141a and 141b and the tube 142. At this time, the header 141a, 141b and the tube 142 constituting the flow path of the secondary fluid are formed as pressure-resistant structures. The flow path of the primary fluid and the flow path of the secondary fluid may be interchanged.

A cooler 150 and a heat insulating material 160 are provided on the inner peripheral surface of the inner container 112. Referring to FIG. 1, a heat insulating material 160 is installed on the inner peripheral surface of the inner container 112, and the cooler 150 can be installed inside the heat insulating material 160.

The cooler 150 is configured to remove heat in the second region 112a. Since the second region 112a in which the control rod driving device 130 is installed is an atmospheric environment, the heat that has passed through the heat insulating material 160, the heat transmitted along the guide pipe of the control rod 135, And the like can prevent the normal operating environment of the control rod driving device 130 from being established. The cooler 150 is configured to remove such heat, thereby creating a normal operating environment for the control rod drive device 130.

The cooler 150 has an inlet and an outlet, and the coolant flows through the inlet of the cooler 150, receives heat, and is discharged to the outlet. In Fig. 1, the arrow indicates the concept of the refrigerant flow direction.

The heat insulating material 160 is installed on the inner circumferential surface of the inner container 112 so as to prevent heat from being transferred from the high temperature cooling water to the second region 112a. As already described in the description of the cooler 150, the heat may prevent the normal operating environment of the control rod driving device 130 from being established. The heat insulator 160 is configured to suppress the heat transfer, and thus the normal operation environment of the control rod driving apparatus 130 can be established.

The pressurizer 170 functions to maintain the pressurized state exceeding the saturation pressure of the cooling water so as to suppress the boiling of the cooling water in the pressurized water reactor (100). The pressurizer 170 may be of any type as well as steam or nitrogen gas type, and is not limited to a particular type of pressurizer 170. In the present invention, the pressurizer 170 is installed in the upper part of the first region 111a, and in particular, in the annular space formed between the outer container 111 and the inner container 112.

Since the conventional pusher 170 is often disposed at the center of the reactor vessel 110, a connection nozzle for passing through the reactor vessel 110 such as various instruments is provided. However, the increase in the number of pressurizer connecting nozzles increases the possibility of occurrence of a coolant loss accident, complicating the construction of the pressurizer 170. In contrast, in the present invention, since the pusher 170 is installed in the annular space formed between the outer container 111 and the inner container 112, the number of presser connecting nozzles can be minimized and the configuration of the pusher 170 Can be simplified.

Referring to FIG. 1, a pressurizer 170, a reactor coolant pump 180, and a steam generator 140 are installed in an annular space from top to bottom.

The reactor coolant pump 180 is arranged to promote the circulation of the cooling water stored in the outer vessel 111. 1, the reactor coolant pump 180 is installed horizontally in the outer vessel 111, but the present invention is not limited thereto.

Hereinafter, another embodiment of the present invention will be described. The description overlapping with that described with reference to FIG. 1 will be omitted from FIG. 1, and a description will be given below of a portion that differs in structure and function from FIG.

2 is a conceptual diagram of a reactor 200 according to another embodiment of the present invention.

The lid 220 is formed in an annular shape to cover the first area 211a and open the second area 212a. The upper end of the first region 211a is formed in an annular shape and the upper end of the second region 212a is formed in a circular shape. The lid 220 is formed to correspond to the upper end of the first area 211a.

Since the second area 212a corresponds to the atmospheric environment, unlike the first area 211a, it can be exposed to the atmosphere. A cooler (not shown) may be installed in the second area 212a. If the second area 212a is exposed to the atmosphere, the ambient air at all times may be supplied from the outside. Therefore, 212a can be expected.

3 is a conceptual diagram of a nuclear reactor 300 according to another embodiment of the present invention.

The control rods 335 and 336 include a control rod 335 and a stationary control rod 336. The control control rod 335 is for starting and normal operation of the reactor 300 and emergency stop of the reactor 300. The stationary control rod 336 is for emergency stop of the reactor 300. The control rod driving devices 331 and 332 corresponding to the control rods 335 and 336 also include a first control rod driving device 331 and a second control rod driving device 332.

The first control rod driving device 331 drives the control rod 335 and the second control rod driving device 332 drives the stop control rod 336. The first control rod driving device 331 and the second control rod driving device 332 may be arranged to form a height difference with respect to each other. 3, the first control rod driving device 331 for driving the control control rod 335 is disposed on the relatively upper side and includes a second control rod driving device 332 for driving the stationary control rod 336 ) Are disposed relatively below.

By disposing the control rod driving devices 331 and 332 vertically, it is possible to secure a space for disposing the control rod driving devices 331 and 332, so that the size constraint conditions of the control rod driving devices 331 and 332 can be relaxed have. However, the arrangement of the control rod driving devices 331 and 332 may be changed according to the design conditions of the reactor 300.

4 is a conceptual diagram of a nuclear reactor 400 according to another embodiment of the present invention.

If it is necessary to increase the capacity of the steam generator 440 according to the design of the reactor 400, the size of the steam generator 440 may also be increased. Any portion of the outer vessel 411 may have a cross-sectional area of a larger radius than the other portion corresponding to the size of the steam generator 440.

Referring to FIG. 4, it can be visually confirmed that the size of the steam generator 440 is relatively large according to the design requirements of the reactor 400. Correspondingly, the upper portion of the outer container 411 may have an enlarged cross-sectional area as compared with the lower portion.

5 is a conceptual diagram of a nuclear reactor 500 according to another embodiment of the present invention.

The reactor 500 includes a support structure 512 '. The support structure 512 'is formed on the inner circumferential surface of the inner container 512 and is configured to support the inner container 512 from an external pressure (pressure applied from the first area to the second area). For example, the support structure 512 'may be formed in an annular shape corresponding to the inner circumferential surface of the inner container 512 or in the form of a disk having the control rod driving device 530 and the penetration portion of the cooler 550, have. The upper and lower support structures 512 'may be connected to each other.

Since the first area 511a is pressed by the presser 570, an external pressure is also applied to the outer peripheral surface of the inner container 512. [ It is necessary to increase the thickness of the inner container 512 in order to prevent deformation of the inner container 512 from external pressure. However, when the support structure 512 'is provided, Can be obtained.

6 is a conceptual diagram of a reactor 600 according to another embodiment of the present invention.

In general, the reactor vessel 610 may be formed as a single vessel, but the outer vessel 611 shown in FIG. 6 has a first outer vessel 611 'and a second outer vessel 611' Bond.

An intermediate separator 613 for separating the first region 611a from the upper portion of the first region 611a may be provided between the first outer container 611 'and the second outer container 611 " 613 conceptually separate the upper and lower portions of the first region 611a, but do not spatially separate them.

7 is a conceptual diagram of a reactor 700 according to another embodiment of the present invention.

As mentioned above, the flow path of the primary fluid and the flow path of the secondary fluid may be interchanged. The steam generator 740 of FIG. 7 has a flow path configuration opposite to that of the steam generators 140 to 640 shown in FIGS. 1 to 6. Accordingly, the shape of the steam generator 740 may also be partially modified.

The flow path of the secondary fluid in the steam generator 740 is formed by the outer circumferential surface of each tube 742 and the inner circumferential surface of the casing 743. At this time, the casing 743 and the tube 742 constituting the flow path of the secondary fluid are formed as pressure-resistant structures.

8 is a conceptual diagram of a reactor 800 according to another embodiment of the present invention.

The reactor 800 further includes a heat insulating material 871 surrounding the pressurizing device 870 in addition to the heat insulating material 860 provided on the inner peripheral surface of the inner container 812. In addition to the heat transferring material 872 and the cushioning space 873, .

The pressurizer 870 typically pressurizes the cooling water in the first region 811a by heating the water to form the vapor and maintaining the pressure. Therefore, the temperature of the pressurizer 870 is relatively higher than the temperature of the reactor vessel 810. The heat insulator 871 surrounds the pusher 870 so as to mitigate or suppress heat loss from the high temperature pusher 870.

The jamb pipe structure 872 is formed at the lower portion of the pusher 870. The original hopper is a component that connects the pressurizer 870 and the reactor vessel 810, and forms a flow path of the cooling water. The cooling water can flow through the lifting tube structure 872.

A buffer space 873 serving as a buffer is formed in the lower part of the journaling tube structure 872. The buffer space 873 is also for mitigating or suppressing the heat loss of the pusher 870.

9 is a conceptual diagram of a reactor 900 according to another embodiment of the present invention.

The reactor 900 further includes a circulator 990.

Circulator 990 is configured to facilitate circulation of the air present in inner vessel 912. For example, the circulator 990 can be understood as a fan that causes atmospheric convection of the inner vessel 912. The circulator 990 is configured to form the second region 912a together with the cooler 950 into the normal operating environment of the control rod driving apparatus 930. [

A plurality of circulators 990 may be provided, and the type and position of the circulators 990 may be variously modified.

10 is a conceptual diagram of a nuclear reactor 1000 according to another embodiment of the present invention.

The reactor coolant pump 1080 is configured to facilitate the circulation of the cooling water stored in the outer vessel 1011. Unlike the reactor coolant pump described above, the reactor coolant pump 1080 of FIG. 10 is installed vertically in the lid 1020. In this way, the position of the reactor coolant pump 1080 can be variously changed, and thus the space of the first region 1011a can be utilized variously.

11 is a conceptual diagram of a reactor 1100 according to another embodiment of the present invention.

The lid 1120 includes a first lid 1121 and a second lid 1122. The first cover 1121 is formed in an annular shape so as to cover the first area 1111a. The second cover 1122 is formed to correspond to the inner container 1112 so as to cover the second area 1112a. As shown, the second lid 1122 may be coupled to the first lid 1121, but is not limited thereto. In this structure, the first region 1111a and the second region 1112a can be separated and opened. The configuration and shape of the lid 1120 may be variously modified, such as a flat plate shape, a hemispherical shape, a hemispherical-cylindrical shape, and the like.

The above-described reactor is not limited to the configuration and the method of the above-described embodiments, but the embodiments may be configured by selectively combining all or a part of each embodiment so that various modifications can be made.

100: reactor
101: Core
110: reactor vessel, 111: outer vessel, 112: inner vessel
120: Cover
130:
135: control rod
140: Steam generator
150: cooler
160: Insulation
170: Presser
180: reactor coolant pump

Claims (16)

An outer container configured to store cooling water therein and forming an outer appearance of the reactor vessel;
An inner container installed in an inner space of the outer container so as to spatially separate a first region storing the cooling water and a second region of the atmospheric environment;
A cover that covers at least a portion of the reactor vessel and forms a pressure boundary with the outer vessel and the inner vessel; And
And a control rod driving device which is arranged to control the insertion or withdrawal of the control rod and installed in the second region of the atmospheric environment to prevent leakage or discharge due to exposure to the cooling water. The method according to claim 1,
The control rod driving device includes:
A first control rod driving device for driving control rods for starting and normal operation of the reactor, and emergency stop of the reactor; And
And a second control rod drive device for driving a stationary control rod for emergency stop of the reactor,
Wherein the first control rod driving device and the second control rod driving device are arranged to form a height difference with respect to each other. The method according to claim 1,
A steam generator for heat exchange between the primary fluid and the secondary fluid is installed between the outer vessel and the inner vessel,
Wherein the header and the tube constituting the flow path of the secondary fluid are formed as pressure-resistant structures. The method according to claim 1,
A steam generator for heat exchange between the primary fluid and the secondary fluid is installed between the outer vessel and the inner vessel,
Wherein the casing and the tube constituting the flow path of the secondary fluid are formed as pressure-resistant structures. The method according to claim 3 or 4,
Wherein a portion of said outer vessel has a cross-sectional area of an enlarged radius greater than that of the other portion corresponding to the size of said steam generator. The method according to claim 1,
Wherein the outer container is formed by a combination of a lower first outer container and an upper second outer container,
Wherein an intermediate separator is disposed between the first outer container and the second outer container. The method according to claim 1,
Wherein the cover covers both the outer container and the inner container so as to seal both the first region and the second region. 8. The method of claim 7,
Wherein the cover comprises:
A first lid formed in an annular shape to cover the first region; And
And a second cover corresponding to the inner container to cover the second region. The method according to claim 1,
Wherein the lid is formed in an annular shape to cover the first region and open the second region. The method according to claim 1,
Wherein a cooler for removing the heat of the second region is provided on an inner circumferential surface of the inner vessel. The method according to claim 1,
Wherein the reactor further comprises a heat insulating material disposed on an inner peripheral surface of the inner vessel to suppress heat transfer from the cooling water to the second region. The method according to claim 1,
A support structure for supporting the inner container from an external pressure is formed on an inner peripheral surface of the inner container,
Wherein the support structure is formed in an annular shape corresponding to an inner peripheral surface of the inner container. The method according to claim 1,
Wherein said reactor further comprises a pressurizer that maintains a pressurized state above the saturation pressure of said cooling water to suppress boiling of said cooling water,
Wherein the pressurizer is installed in an annular space formed between the outer container and the inner container. 14. The method of claim 13,
The reactor,
A heat insulating material surrounding the presser to mitigate heat loss;
A pusher tube structure formed at a lower portion of the pusher; And
Further comprising a cushioning space formed in the lower portion of said ramp structure to mitigate heat loss. The method according to claim 1,
The reactor further comprising a reactor coolant pump to facilitate circulation of the cooling water stored in the outer vessel,
Wherein the reactor coolant pump is installed in the outer container or the cover. The method according to claim 1,
Wherein the reactor further comprises a circulator configured to facilitate circulation of the air present in the inner vessel.

Images