Method and apparatus 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 apparatus for dismantling a nuclear power plant.

Background Art

[0002] When performing the dismantling work of a nuclear power plant, usually, a thermal cutting method is used. When performing cutting and dismantling by such a heat transfer method, it is possible to cut using an oxygen-propane torch. In this case, the cutting and dismantling is performed by melting the metal using high-temperature heat energy. Here, the cutting and dismantling is an in-situ method using equipment introduced into the facility, and without moving the reactor to another space, the lifting equipment is used to directly lift and perform cutting and dismantling in place. When performing the thermal cutting method in such an environment, there are risks such as explosion and detonation caused by the gas existing on the cutting and dismantling target. Therefore, it is necessary to ensure safety from the aspect of industrial safety.

Summary of the Invention

Problems 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 that can eliminate the risks of explosion and detonation caused by the gas existing on or around the cutting and dismantling target when performing thermal shearing as the dismantling work of a nuclear power plant.

[0004] Another object is to provide a method and apparatus for dismantling a nuclear power plant that can prevent human casualties and property damage by eliminating such risks.

[0005] Another object is to provide a method and apparatus for dismantling a nuclear power plant that can ultimately achieve safety assurance in the safety of the nuclear power plant-related industry.

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

Means for Solving the Problems

[0007] A nuclear power plant decommissioning method and apparatus 1 according to one aspect of the present invention for achieving the above object is a nuclear power plant decommissioning apparatus, comprising: a frame unit that shields the nuclear reactor to prevent external release of contaminants in the nuclear reactor; a cutting module provided on the frame unit for performing cutting operations on the nuclear reactor; an interlocking fixing module having a hollow region formed therein and entering the interior of the nuclear reactor to interlock the frame unit and the nuclear reactor; and a purge module that enters the hollow region of the interlocking fixing module and purges the interior of the nuclear reactor to ensure safety during the cutting operation.

[0008] A nuclear power plant decommissioning method and apparatus 2 according to another aspect of the present invention for achieving the above object is an operation method of a nuclear power plant decommissioning apparatus, comprising: a step of selecting a nuclear reactor to be decommissioned; and a step of performing a nuclear power plant decommissioning operation on the nuclear reactor by a nuclear reactor cutting device, wherein the nuclear reactor cutting device comprises: a frame unit that shields the nuclear reactor to prevent external release of contaminants in the nuclear reactor; a cutting module provided on the frame unit for performing cutting operations on the nuclear reactor; a bar-shaped interlocking fixing module having a hollow region formed therein and entering the interior space of the nuclear reactor to interlock the frame unit and the nuclear reactor; and a purge module that enters the hollow region of the interlocking fixing module and purges the interior of the nuclear reactor to ensure safety during the cutting operation.

[0009] In addition, the interlocking fixing module includes a partitioning body that is partitioned into a plurality in the height direction. The partitioning body is located in the height direction of the interlocking fixing module, and includes a first partitioning body that forms a first space for communication with the internal space, a second partitioning body that is located in the height direction of the interlocking fixing module and forms a second space for communication between the first partitioning body and the internal space, and a third partitioning body that is located in the height direction of the interlocking fixing module and forms a third space for communication between the second partitioning body and the internal space. The purge module purges the internal space of the reactor through the first space to the third space.

[0010] In addition, the purge module includes 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 partitioning body and supplies a second purge gas to the second space, and a third purge module that enters the first space via the third partitioning body and the second partitioning body and supplies a third purge gas to the first space. The purge module controls the purge level of the internal space of the reactor by selectively injecting the first purge gas to the third purge gas.

[0011] In addition, for the purge module, the first purge gas to the third purge gas are identical to each other, or at least one of the first purge gas to the third purge gas is different from the other gases.

[0012] In addition, a large number of through holes are formed on the peripheral surface of the interlocking fixing module that surrounds the first region to the third region. The purge module purges the internal space of the reactor by injecting the first purge gas to the third purge gas through the through holes.

[0013] Further, the first purge gas of the first purge module enters the first internal space corresponding to the first space in the internal space to perform purge on the reactor, the second purge gas of the second purge module enters the second internal space corresponding to the second space in the internal space to perform purge on the reactor, and the third purge gas of the third purge module enters the third internal space corresponding to the third space in the internal space to perform purge on the reactor.

Advantages of the Invention

[0014] According to the method and apparatus for decommissioning a nuclear power plant of the present invention as described above, there is one or more of the following effects.

[0015] In performing thermal shearing as a decommissioning operation of a nuclear power plant, the present invention can eliminate risks such as explosion and deflagration caused by gases present in the object to be cut and disassembled or in the vicinity.

[0016] Further, by eliminating such risks, it is possible to prevent human casualties and material damage in a nuclear power plant.

[0017] Furthermore, ultimately, it is possible to achieve ensuring safety in the safety of the nuclear power plant-related industries.

Brief Description of the Drawings

[0018]

Figure 1

Figure 2

Figure 3

Figure 4

Figure 5

Figure 6

Best Mode for Carrying Out the Invention

[0019] Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings. The advantages and features of the present invention, and the methods for achieving them, will become clear by referring to the embodiments described in detail later together with the accompanying drawings. However, the present invention is not limited to the embodiments disclosed below, and can be realized in various different forms. This embodiment is merely to complete the disclosure of the present invention and is provided to fully inform those with ordinary knowledge in the technical field to which the present invention belongs of the scope of the invention. The present invention is defined only by the scope of the claims. The same reference numerals throughout the specification refer to the same components.

[0020] Referring to FIG. 1, a nuclear power plant decommissioning apparatus 100 according to an embodiment of the present invention includes a frame unit 110, a cutting module 120, an interlocking 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 part 111 and a lower structure part 112. The interlocking fixing module 130 includes partition bodies 131, 132, 133. The partition bodies 131, 132, 133 include a first partition body 131, a second partition body 132, and a third partition body 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 151 and an inner cylinder 152.

[0023] Referring to FIGS. 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, it is provided as a structure of a predetermined shape placed around the upper part of the reactor 10.

[0024] The cutting module 120 is provided on the frame unit 110 and performs a cutting operation on the reactor 10. A hollow region S1 is formed inside the interlocking fixing module 130.

[0025] Such an interlocking fixing module 130 enters the internal region M1 of the reactor 10 to interlock the frame unit 110 and the reactor 10. Here, the interlocking can include various parts such as physical connection and functional operation.

[0026] The purge module 140 enters the hollow region S1 of the interlocking fixing module 130. Such a purge module 140 performs a purge on the inside of the reactor 10 to ensure safety during the cutting operation after entering the hollow region S1.

[0027] The partition bodies 131, 132, 133 partition the interlocking fixing module 130 into a plurality in the height direction. Here, the first partition body 131 of the partition bodies 131, 132, 133 is located in the height direction of the interlocking fixing module 130 and forms a first region S11 for communication with the internal region M1.

[0028] Furthermore, the second partition body 132 of the partition bodies 131, 132, 133 is located in the height direction of the interlocking fixing module 130 and forms a second region S12 for communication between the first partition body 131 and the internal region M1.

[0029] The third partition body 133 of the partition bodies 131, 132, 133 is located 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 between the second partition body 132 and the internal region M1.

[0030] The purge module 140 purges 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 and supplies the 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 the 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 the third purge gas to the first region S11.

[0033] Here, the purge module 140 controls the purge level of the internal region M1 of the reactor 10 by selectively injecting the first purge gas to the third purge gas.

[0034] The purge module 140 may have the first purge gas to the third purge gas being the same as each other, or at least one of the first purge gas to the third purge gas may be different from the other gases.

[0035] Note that at least one of the first purge gas to the third purge gas contains an inert gas (e.g., nitrogen, argon, etc.). Note that a large number of through holes TH are formed on the peripheral surface surrounding the first region S11 to the third region S13 of the interlocking fixing module 130.

[0036] The purge module 140 purges the internal region M1 of the reactor 10 by injecting the first purge gas to the third purge gas through the through holes TH.

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

[0038] Also, the second purge gas of the second purge module 142 enters a second internal region M12 corresponding to the second region S12 in the internal region M1 to perform a purge on the reactor 10.

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

[0040] Note that the upper structure portion 111 of the frame unit 110 is provided with a predetermined shape. The lower structure portion 112 of the frame unit 110 is provided so as to face the upper structure portion 111.

[0041] Such the upper structure portion 111 and the lower structure portion 112 are provided so as to have a cross-sectional shape such as a quadrangle, a polygon, a circle, and an ellipse. Further, the cutting module 120 is provided singly or plurally on the frame unit 110 to perform a cutting operation on the reactor 10.

[0042] A number of the fire extinguishing modules 150 are provided between the upper structure portion 111 and the lower structure portion 112. Such the fire extinguishing module 150 serves to supply the fire extinguishing fluid L to the fire occurrence side where the fire has occurred in response to the heat source.

[0043] The fire extinguishing module 150 is provided on the frame unit 110. When a fire occurs in the reactor 10, it melts by the heat source due to the fire, and the internal fire extinguishing fluid L is automatically supplied to the outside.

[0044] Note that the lower structure portion 112 of the frame unit 110 described above is provided as a ring-shaped body surrounding the peripheral edge of the reactor 10. A large number of the fire extinguishing modules 150 are arranged on the peripheral edge of the lower structure portion 112.

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

[0046] Such an inner cylinder body 152 is filled with the fire extinguishing fluid L inside. An incision portion is formed in at least a part of the peripheral edge of the outer peripheral surface of the outer cylinder body 151, which is incised in the horizontal direction or the vertical direction.

[0047] At least a part of the inner cylinder body 152 melts in response to the fire. Due to such melting, the fire extinguishing fluid L is supplied to the outside of the outer cylinder body 151 through the incision portion.

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

[0049] With such a gas concentration analysis module 160, it is possible to grasp the necessity of purging of the purge module 140 and perform purging. Further, it is possible to continuously grasp whether appropriate purging has been performed and manage whether the purge module has operated.

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

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

[0052] Referring to FIG. 6, an operation method of a nuclear power plant dismantling device according to an embodiment of the present invention includes selecting a nuclear reactor 10 to be dismantled. The nuclear reactor 10 is dismantled by the nuclear reactor dismantling device 100.

[0053] Here, the nuclear reactor dismantling device 100 is provided such that the frame unit 110 shields the nuclear reactor 10 to prevent external release of contaminants in the nuclear reactor 10. Such a nuclear reactor dismantling device 100 includes a function for lifting the nuclear reactor.

[0054] A cutting module 120 is provided on the frame unit 110 to perform a cutting operation on the nuclear reactor 10. The bar-shaped interlocking fixing module 130 enters the internal area M1 of the nuclear reactor 10 to interlock the frame unit 110 and the nuclear reactor 10.

[0055] Such an interlocking fixing module 130 has a hollow area S1 formed therein. The purge module 140 enters the hollow area S1 of the interlocking fixing module 130 to perform a purge on the inside of the nuclear reactor 10 to ensure safety during the cutting operation.

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

[0057] While the embodiments of the present invention have been described with reference to the above and the attached drawings, those having ordinary knowledge in the technical field to which the present invention pertains can understand that the present invention can be implemented in other specific forms without changing its technical idea and essential features. Therefore, it should be understood that the above-described embodiment is illustrative in all respects and not restrictive.

Claims

1. A method for decommissioning a nuclear power plant, comprising: selecting a nuclear reactor to be decommissioned; and performing a decommissioning operation of the nuclear power plant on the nuclear reactor by a nuclear reactor decommissioning device, wherein the nuclear reactor decommissioning device includes: a frame unit that shields the nuclear reactor to prevent external release of contaminants of the nuclear reactor; a cutting module provided on the frame unit for performing a cutting operation on the nuclear reactor; a bar-shaped interlocking fixing module having a hollow region formed therein, entering the inner region of the nuclear reactor and interlocking the frame unit and the nuclear reactor; and a purge module that enters the hollow region of the interlocking fixing module and purges the inside of the nuclear reactor to ensure safety during the cutting operation.

2. The interlocking fixing module includes a partitioning body partitioned into a plurality in the height direction, wherein the partitioning body includes: a first partitioning body located in the height direction of the interlocking fixing module and forming a first region for communication with the inner region; a second partitioning body located in the height direction of the interlocking fixing module and forming a second region for communication between the first partitioning body and the inner region; and a third partitioning body located in the height direction of the interlocking fixing module and forming a third region for communication between the second partitioning body and the inner region, wherein the purge module purges the inner region of the nuclear reactor through the first region to the third region. The method for decommissioning a nuclear power plant according to claim 1.

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 partitioning body and supplies a second purge gas to the second region; and a third purge module that enters the first region through the third partitioning body and the second partitioning body and supplies a third purge gas to the first region, wherein the purge module controls the purge level of the inner region of the nuclear reactor by selectively injecting the first purge gas to the third purge gas. The method for decommissioning a nuclear power plant according to claim 2.

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

5. A large number of through holes are formed in a peripheral surface of the interlocking fixing module that surrounds the first region to the third region. The method for decommissioning a nuclear power plant according to claim 4, wherein the purge module injects the first purge gas to the third purge gas through the through holes to perform a purge on the internal region of the nuclear reactor.

6. The first purge gas of the first purge module enters a first internal region corresponding to the first region in the internal region to perform a purge on the nuclear reactor. The second purge gas of the second purge module enters a second internal region corresponding to the second region in the internal region to perform a purge on the nuclear reactor. The method for decommissioning 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 in the internal region to perform a purge on the nuclear reactor.

7. A decommissioning device for a nuclear power plant, comprising: A frame unit that shields the nuclear reactor to prevent external release of contaminants in the nuclear reactor; A cutting module provided on the frame unit for performing a cutting operation on the nuclear reactor; An interlocking fixing module having a hollow region formed therein, entering the inside of the nuclear reactor to interlock the frame unit and the nuclear reactor; and A decommissioning device for a nuclear power plant, including a purge module that enters the hollow region of the interlocking fixing module and performs a purge on the inside of the nuclear reactor to ensure safety during the cutting operation.

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