Method and equipment for dismantling nuclear power plants

Abstract

Provided is a method and device for dismantling a nuclear power plant. The method for dismantling a nuclear power plant includes the steps of selecting a nuclear reactor to be dismantled and performing a dismantling operation of the nuclear power plant on the reactor by a nuclear reactor dismantling device, and the nuclear reactor dismantling device includes a frame unit for shielding the reactor to prevent external release of contaminants from the reactor, a cutting processing module for performing a cutting operation on the reactor, a bar-shaped interlocking and fastening module having a hollow area formed therein and entering the internal area of ​​the reactor to interlock the frame unit and the reactor, and a purge module for entering the hollow area of ​​the interlocking and fastening module to purge the inside of the reactor to ensure safety during the cutting operation.

Description

[Technical field]

[0001] The present invention relates to a method and an apparatus for dismantling a nuclear power plant. [Background technology]

[0002] Thermal cutting is usually used when dismantling nuclear power plants. When cutting and dismantling is performed using this type of thermal transfer method, an oxygen-propane torch can be used. In this case, cutting and dismantling is performed by melting metal using high-temperature thermal energy. Here, cutting and dismantling is an in-situ method using equipment installed inside the facility, and cutting and dismantling is performed by lifting the reactor in situ using lifting equipment without moving it to another space. When using thermal cutting in such an environment, there is a risk of explosion and detonation due to gas present above the object to be cut and dismantled. Therefore, safety must be ensured from the perspective of industrial safety. Summary of the Invention [Problem to be solved by the invention]

[0003] The problem to be solved by the present invention is to provide a method and apparatus for dismantling a nuclear power plant, which can eliminate the risk of explosion and detonation due to gas present in or around the object being cut and dismantled when performing thermal shearing as part of the dismantling work of the nuclear power plant.

[0004] Another object of the present invention is to provide a method and apparatus for dismantling a nuclear power plant which can prevent loss of life and damage to property by eliminating such risks.

[0005] Another object of the present invention is to provide a method and apparatus for dismantling a nuclear power plant which can ultimately ensure the safety of industries related to the nuclear power plant.

[0006] The objects of the present invention are not limited to the objects mentioned above, and other objects not mentioned herein will be clearly understood by those skilled in the art from the following description. [Means for solving the problem]

[0007] In order to achieve the above-mentioned object, a method and apparatus 1 for dismantling a nuclear power plant according to one aspect of the present invention is a nuclear power plant dismantling apparatus including a frame unit that shields the reactor to prevent external release of contaminants from the reactor; a cutting processing module that is provided on the frame unit and is used to perform cutting work on the reactor; an interlocking fixing module that has a hollow area formed therein and enters the interior of the reactor to interlock the frame unit and the reactor; and a purge module that enters the hollow area of ​​the interlocking fixing module and purges the interior of the reactor to ensure safety during the cutting work.

[0008] To achieve the above object, a method and apparatus 2 for dismantling a nuclear power plant according to another aspect of the present invention includes, as a method for operating a nuclear power plant dismantling apparatus, a step of selecting a reactor to be dismantled; and a step of performing dismantling work on the nuclear power plant by a reactor cutting apparatus, the reactor cutting apparatus including a frame unit that shields the reactor to prevent external release of contaminants from the reactor, a cutting processing module that is provided on the frame unit and performs cutting work on the reactor, a bar-shaped interlocking fixing module having a hollow area formed therein and that enters the internal space of the reactor to interlock the frame unit and the reactor, and a purge module that enters the hollow area of ​​the interlocking fixing module and purges the inside of the reactor to ensure safety during the cutting work.

[0009] The interlocking fixing module further includes a plurality of partitions in the height direction, the partitions including a first partition located above the height direction of the interlocking fixing module and forming a first space for communication with the internal space, a second partition located above the height direction of the interlocking fixing module and forming a second space with the first partition for communication with the internal space, and a third partition located above the height direction of the interlocking fixing module and forming a third space with the second partition for communication with the internal space, and the purge module purges the internal space of the reactor via the first space through the third space.

[0010] The purge modules further include a first purge module that enters the third space and supplies a first purge gas, a second purge module that enters the second space via the third partition and supplies a second purge gas to the second space, and a third purge module that enters the first space via the third partition and the second partition and supplies a third purge gas to the first space, and the purge module controls the purge level for the internal space of the reactor by selectively injecting the first purge gas or the third purge gas.

[0011] In addition, in the purge module, the first purge gas, the second purge gas, and the third purge gas are the same as each other, or at least one of the first purge gas, the second purge gas, and the third purge gas is different from the other gases.

[0012] In addition, the interlocking fixing module has a number of through holes formed on a peripheral surface surrounding the first region to the third region, and the purge module injects the first purge gas to the third purge gas through the through holes to purge the internal space of the reactor.

[0013] In addition, the first purge gas of the first purge module enters a first internal space among the internal spaces that corresponds to the first space to purge the reactor, the second purge gas of the second purge module enters a second internal space among the internal spaces that corresponds to the second space to purge the reactor, and the third purge gas of the third purge module enters a third internal space among the internal spaces that corresponds to the third space to purge the reactor. Effect of the Invention

[0014] According to the above-described method and apparatus for dismantling a nuclear power plant of the present invention, one or more of the following effects can be obtained.

[0015] The present invention can eliminate the risk of explosion and detonation due to gas present in or around the object being cut and dismantled when performing thermal shearing in the dismantling work of a nuclear power plant.

[0016] Furthermore, eliminating such risks can prevent loss of life and property damage at nuclear power plants.

[0017] Furthermore, ultimately, it is possible to ensure the safety of the nuclear power plant-related industries. [Brief description of the drawings]

[0018] [Figure 1] 1 is a diagram showing a nuclear power plant dismantling apparatus according to an embodiment of the present invention. [Diagram 2] FIG. 2 is a diagram showing the configuration of FIG. 1 in detail. [Diagram 3] FIG. 2 is a diagram showing the configuration of FIG. 1 in detail. [Figure 4] FIG. 2 is a diagram showing the configuration of FIG. 1 in detail. [Diagram 5] FIG. 2 is a diagram showing the configuration of FIG. 1 in detail. [Figure 6] 4 is a flowchart sequentially illustrating a method for operating a nuclear power plant decommissioning apparatus according to an embodiment of the present invention. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS

[0019] Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings. Advantages and features of the present invention, as well as methods for achieving the same, will become apparent from the following detailed embodiments in conjunction with the accompanying drawings. However, the present invention is not limited to the embodiments disclosed below, and may be realized in various different forms. The present embodiments are provided merely to complete the disclosure of the present invention and to fully inform those skilled in the art of the present invention of the scope of the invention, and the present invention is defined only by the scope of the claims. The same reference symbols refer to the same elements throughout the specification.

[0020] Referring to FIG. 1, a nuclear power plant dismantling device 100 according to one embodiment of the present invention includes a frame unit 110, a cutting processing module 120, a linkage fixing module 130, a purge module 140, a fire extinguishing module 150, a gas concentration analysis module 160 and an intake module 170.

[0021] Here, the frame unit 110 includes an upper structure 111 and a lower structure 112. The interlocking fastening module 130 includes partitions 131, 132, and 133. The partitions 131, 132, and 133 include a first partition 131, a second partition 132, and a third partition 133.

[0022] The purge module 140 includes a first purge module 141, a second purge module 142 and a third purge module 143. The fire extinguishing module 150 includes an outer cylinder body 151 and an inner cylinder body 152.

[0023] 2 to 5, the frame unit 110 is for shielding the reactor 10 to prevent external release of contaminants from the reactor 10. For this purpose, the frame unit 110 is provided as a structure of a predetermined shape mounted on the upper periphery of the reactor 10.

[0024] The cutting processing module 120 is mounted on the frame unit 110 and performs cutting work on the reactor 10. The interlocking and fixing module 130 has a hollow area S1 formed therein.

[0025] The interlocking fixing module 130 enters the inner region M1 of the reactor 10 to interlock the frame unit 110 with the reactor 10. Here, the interlocking may include various parts such as a physical connection and a functional operation.

[0026] The purge module 140 enters the hollow area S1 of the interlocking fixing module 130. After entering the hollow area S1, the purge module 140 purges the inside of the reactor 10 to ensure safety during the cutting operation.

[0027] The partitions 131, 132, and 133 divide the interlocking fastening module 130 into a plurality of partitions in the height direction. Here, the first partition 131 of the partitions 131, 132, and 133 is positioned on the upper side of the interlocking fastening module 130 in the height direction and forms a first region S11 for communication with the internal region M1.

[0028] Furthermore, the second partition 132 of the partitions 131, 132, and 133 is positioned above the interlocking fixing module 130 in the height direction, and forms with the first partition 131 a second region S12 for communication with the internal region M1.

[0029] The third partition body 133 of the partition bodies 131, 132, and 133 is positioned in the height direction of the interlocking fixing module 130 and includes a third partition body 133 that forms a third region S3 for communication with the second partition body 132 and the internal region M1.

[0030] The purge module 140 performs purging on the internal region M1 of the reactor 10 through the first region S11 to the third region S3. The first purge module 141 of the purge module 140 enters the third region S3 to supply a first purge gas.

[0031] The second purge module 142 of the purge module 140 enters the second region S12 via the third partition 133 and supplies a second purge gas to the second region S12.

[0032] The third purge module 143 of the purge module 140 enters the first region S11 via the third partition 133 and the second partition 132, and supplies a third purge gas to the first region S11.

[0033] Here, the purge module 140 controls the purge level for the inner region M1 of the reactor 10 by selectively injecting the first purge gas, the second purge gas, or the third purge gas.

[0034] In the purge module 140, the first purge gas, the second purge gas, and the third purge gas may be the same as each other, or at least one of the first purge gas, the second purge gas, and the third purge gas may be different from the other gases.

[0035] At least one of the first purge gas, the second purge gas, and the third purge gas includes an inert gas (e.g., nitrogen, argon, etc.). The interlocking fixing module 130 has a number of through holes TH formed on a peripheral surface surrounding the first region S11, the second region S12, and the third region S13.

[0036] The purge module 140 injects the first purge gas, the second purge gas, and the third purge gas through the through hole TH to purge the inner region M1 of the reactor 10.

[0037] The first purge gas of the first purge module 141 enters a first inner region M11 corresponding to the first region S11 of the inner region M1 to purge the reactor 10.

[0038] In addition, the second purge gas of the second purge module 142 enters a second inner region M12 corresponding to the second region S12 of the inner region M1 to purge the reactor 10.

[0039] The third purge gas of the third purge module 143 enters a third inner region M13 corresponding to the third region S3 of the inner region M1 to purge the reactor 10.

[0040] The upper structure 111 of the frame unit 110 is provided in a predetermined shape. The lower structure 112 of the frame unit 110 is provided to face the upper structure 111.

[0041] The upper structure 111 and the lower structure 112 are provided to have a cross-sectional shape of a rectangle, a polygon, a circle, an ellipse, etc. Furthermore, one or more cutting modules 120 are provided on the frame unit 110 to perform cutting work on the reactor 10.

[0042] A plurality of the fire extinguishing modules 150 are provided between the upper structure 111 and the lower structure 112. The fire extinguishing modules 150 react to the heat source and supply the fire extinguishing fluid L to the fire occurrence side where the fire occurs.

[0043] The fire extinguishing module 150 is installed on the frame unit 110, and when a fire occurs in the reactor 10, the fire extinguishing module 150 melts due to a heat source caused by the fire, so that the fire extinguishing fluid L inside is automatically supplied to the outside.

[0044] The lower structure 112 of the frame unit 110 is provided as a ring-shaped body surrounding the periphery of the reactor 10. A large number of the fire extinguishing modules 150 are arranged on the periphery of the lower structure 112.

[0045] The extinguishing module 150 supplies the extinguishing fluid L to the fire source side by the heat source. Furthermore, the outer cylinder 151 of the extinguishing module 150 includes a hollow metal material. The inner cylinder 152 of the extinguishing module 150 is accommodated inside the tubular portion.

[0046] The inner cylinder 152 is filled with the extinguishing fluid L. The outer cylinder 151 has an opening formed by cutting at least a part of the periphery of the outer periphery in the horizontal or vertical direction.

[0047] At least a part of the inner cylinder 152 melts in response to the fire. Such melting causes the extinguishing fluid L to be supplied to the outside of the outer cylinder 151 through the cutout.

[0048] The gas concentration analysis module 160 is provided at least one of the frame unit 110 and the reactor 10, or at a location where the frame unit 110 and the reactor 10 are adjacent to each other.

[0049] The gas concentration analysis module 160 can determine whether or not purging is necessary and can perform purging. In addition, the gas concentration analysis module 160 can continuously determine whether or not purging is performed properly and can manage whether or not the purge module is operating.

[0050] The intake module 170 corresponds to the purge module 140 and takes in the gas discharged through the purge module 140. For this purpose, the intake module 170 is provided on the frame unit 110 and the reactor 10.

[0051] Furthermore, the purge module 130 can move between the frame unit 110 and the reactor 10 and can perform an air intake operation. For example, the purge module 130 can be provided to be movable up and down in the same manner as the purge module 140.

[0052] 6, in the method for operating a nuclear power plant decommissioning apparatus according to an embodiment of the present invention, a nuclear reactor 10 to be decommissioned is selected. A nuclear reactor decommissioning apparatus 100 performs a nuclear power plant decommissioning operation on the nuclear reactor 10.

[0053] Here, the reactor decommissioning apparatus 100 is provided such that a frame unit 110 shields the reactor 10 to prevent external release of contaminants from the reactor 10. The reactor decommissioning apparatus 100 includes a function for lifting the reactor.

[0054] A cutting module 120 is provided on the frame unit 110 to perform cutting work on the reactor 10. A bar-shaped interlocking and fixing module 130 enters the inner region M1 of the reactor 10 to interlock the frame unit 110 and the reactor 10.

[0055] A hollow space S1 is formed inside the interlocking fastening module 130. A purge module 140 enters the hollow space S1 of the interlocking fastening module 130 and purges the inside of the reactor 10 to ensure safety during the cutting operation.

[0056] The fire extinguishing module 150 is installed on the frame unit 110. When a fire occurs in the reactor 10, the fire extinguishing module 150 melts due to the heat source of the fire. Due to the melting, the fire extinguishing fluid L located inside is automatically supplied to the outside.

[0057] Although the embodiment of the present invention has been described above with reference to the accompanying drawings, those skilled in the art will understand that the present invention can be embodied in other specific forms without changing the technical idea or essential features of the present invention. Therefore, it should be understood that the above embodiment is illustrative in all respects and is not limiting.

Claims

1. A method for dismantling a nuclear power plant, comprising the steps of: Selecting the reactor(s) for dismantling; and A step of performing a nuclear power plant dismantling operation on the nuclear reactor by a nuclear reactor dismantling device, The nuclear reactor dismantling apparatus comprises: a frame unit for shielding the reactor to prevent the reactor contaminants from being discharged to the outside; a cutting processing module provided on the frame unit for performing cutting operations on the reactor; a bar-shaped interlocking and fastening module having a hollow area formed therein and entering the inner area of ​​the reactor to interlock the frame unit and the reactor; A method for dismantling a nuclear power plant, comprising: a purge module that enters the hollow region of the interlocking fastening module and purges an interior of the reactor to ensure safety during the cutting operation.

2. The interlocking and fastening module includes a partition body that is divided into a plurality of partitions in a height direction, The partition body is a first partition body positioned above the interlocking fastening module in a height direction and forming a first region for communication with the internal region; a second partition body positioned above the interlocking fastening module in a height direction and forming with the first partition body a second region for communication with the internal region; a third partition body that is positioned above the interlocking fastening module in a height direction and forms with the second partition body a third region for communication with the internal region; 2. The method for dismantling a nuclear power plant according to claim 1, wherein the purge module performs purging of the internal region of the reactor via the first region, the second region, or the third region.

3. The purge module includes: a first purge module that enters the third region and supplies a first purge gas; a second purge module that enters the second region through the third partition and supplies a second purge gas to the second region; a third purge module that passes through the third partition and the second partition and enters the first region and supplies a third purge gas to the first region; 3. The method of claim 2, wherein the purge module controls a purge level to the interior region of the reactor by selective injection of the first purge gas through the third purge gas.

4. The purge module includes: The first purge gas, the second purge gas, the third purge gas, and the third purge gas are the same as each other, The method for dismantling a nuclear power plant according to claim 3 , wherein at least one of the first purge gas, the second purge gas, and the third purge gas is different from the other gases.

5. The interlocking fixing module has a number of through holes formed on a peripheral surface surrounding the first region to the third region, 5. The method for dismantling a nuclear power plant according to claim 4, wherein the purge module injects the first purge gas through the through hole to purge the internal region of the reactor.

6. The first purge gas of the first purge module enters a first internal region corresponding to the first region among the internal regions to purge the reactor; The second purge gas of the second purge module enters a second internal region corresponding to the second region of the internal region to purge the reactor; 6. The method for dismantling a nuclear power plant according to claim 5, wherein the third purge gas of the third purge module enters a third internal region corresponding to the third region among the internal regions to purge the reactor.

7. A nuclear power plant dismantling device, A frame unit for shielding the reactor to prevent the external release of contaminants from said reactor; a cutting module provided on the frame unit for performing cutting operations on the reactor; an interlocking and fixing module having a hollow area formed therein and extending into the interior of the reactor to interlock the frame unit with the reactor; and A nuclear power plant dismantling device including a purge module that enters the hollow area of ​​the interlocking fixing module and purges the inside of the reactor to ensure safety during the cutting work.

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