Method and apparatus for dismantling nuclear power plants

Abstract

Provided is a method and apparatus 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, the nuclear reactor dismantling device including a frame unit for shielding the reactor to prevent external release of contaminants from the reactor, a cutting 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 dismantling a radioactive pressure vessel of a nuclear power plant, a thermal cutting method is applied for cutting and dismantling. In such a case, an oxygen-propane torch is applied, but fire monitoring and fire extinguishing equipment are not arranged. Therefore, there is a problem that it is not easy to ensure fire safety during the cutting and dismantling process using the thermal cutting method.

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 dismantling apparatus and method for a nuclear power plant that can ensure stability against fire when performing thermal cutting as a dismantling operation of a nuclear power plant.

[0004] Another object is to provide a dismantling apparatus and method for a nuclear power plant that can automatically extinguish a fire at the fire occurrence part in case of a fire.

[0005] Another object is to provide a dismantling apparatus and method for a nuclear power plant having a fire extinguishing structure that can stably perform fire extinguishing without interfering with the surrounding system in a general operating environment.

[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 method for decommissioning a nuclear power plant according to one aspect of the present invention for achieving the above object includes a step of selecting a nuclear reactor to be decommissioned; and a step of performing a decommissioning operation of the nuclear power plant on the nuclear reactor by a nuclear reactor decommissioning device. 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, and a fire extinguishing module provided on the frame unit that melts by a heat source when a fire occurs on the nuclear reactor and automatically supplies an internal fire extinguishing fluid to the outside.

[0008] Further, the frame unit includes an upper structure portion and a lower structure portion facing the upper structure portion. A plurality of the fire extinguishing modules are provided between the upper structure portion and the lower structure portion, and supply the fire extinguishing fluid to the fire occurrence side where the fire has occurred in response to the heat source.

[0009] Further, the lower structure portion of the frame unit is provided as a ring-shaped body surrounding the peripheral portion of the nuclear reactor. A plurality of the fire extinguishing modules are arranged on the peripheral portion of the lower structure portion, and supply the fire extinguishing fluid to the fire occurrence side by the heat source, respectively.

[0010] Further, the fire extinguishing module includes an outer cylinder body including a hollow metal material, and an inner cylinder body accommodated inside the tubular portion and filled with the fire extinguishing fluid inside. The outer cylinder body is formed with a cut portion in which at least a part of the peripheral portion of the outer peripheral surface is cut in a horizontal direction or a vertical direction. When the inner cylinder body melts in response to the fire, the fire extinguishing fluid is supplied to the outside through the cut portion.

[0011] The nuclear power plant dismantling device according to another aspect of the present invention for achieving the above object includes 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 work on the nuclear reactor; and a fire extinguishing module provided on the frame unit that melts by the heat source of the fire when a fire occurs on the nuclear reactor and automatically supplies the internal fire extinguishing fluid to the outside.

Advantages of the Invention

[0012] According to the nuclear power plant dismantling method and device of the present invention as described above, there is one or more of the following effects.

[0013] In the present invention, when performing thermal cutting as a nuclear power plant dismantling operation, the stability against fire can be ensured.

[0014] In addition, it is possible to automatically extinguish the fire at the fire occurrence part in case of a fire.

[0015] In addition, in a general operating environment, it is possible to operate a nuclear power plant dismantling device equipped with a fire extinguishing structure that enables stable fire extinguishing without interfering with the surrounding power grid.

Brief Description of the Drawings

[0016]

Figure 1

Figure 2

Figure 3

Figure 4

Figure 5

Figure 6

Best Mode for Carrying Out the Invention

[0017] 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.

[0018] Referring to FIG. 1, a nuclear power plant dismantling device 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.

[0019] 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.

[0020] 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 cylindrical body 151 and an inner cylindrical body 152.

[0021] Referring to FIGS. 2 to 5, the frame unit 110 is for shielding the reactor 10 to prevent external release of contaminants in 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.

[0022] The cutting module 120 is provided on the frame unit 110 and performs a cutting operation on the reactor 10. The interlocking fixing module 130 has a hollow region S1 formed therein.

[0023] 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.

[0024] 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.

[0025] 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.

[0026] 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.

[0027] 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.

[0028] 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.

[0029] The second purge module 142 of the purge module 140 enters the second region S12 through the third partition 133 and supplies the second purge gas to the second region S12.

[0030] The third purge module 143 of the purge module 140 enters the first region S11 through the third partition 133 and the second partition 132 and supplies the third purge gas to the first region S11.

[0031] 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.

[0032] The purge module 140 may have the first purge gas to the third purge gas be 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.

[0033] 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.

[0034] 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.

[0035] 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.

[0036] 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.

[0037] 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.

[0038] 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.

[0039] Such an upper structure portion 111 and a 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 in plurality on the frame unit 110 to perform a cutting operation on the reactor 10.

[0040] A large number of the fire extinguishing modules 150 are provided between the upper structure portion 111 and the lower structure portion 112. Such a 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.

[0041] The fire extinguishing module 150 is provided on the frame unit 110, and when a fire occurs in the reactor 10, it melts by the heat source of the fire so that the internal fire extinguishing fluid L is automatically supplied to the outside.

[0042] The lower structure portion 112 of the frame unit 110 described above is provided as a ring-shaped body surrounding the peripheral portion of the reactor 10. A large number of the fire extinguishing modules 150 are arranged on the peripheral portion of the lower structure portion 112.

[0043] 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 151 of the fire extinguishing module 150 includes a hollow metal material. The inner cylinder 152 of the fire extinguishing module 150 is housed inside the tubular portion.

[0044] Such an inner cylinder 152 is filled with the fire extinguishing fluid L inside. An incision portion is formed in the outer cylinder 151, at least a part of the peripheral portion of the outer peripheral surface being incised in the horizontal or vertical direction.

[0045] At least a part of the inner cylinder 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 151 through the incision portion.

[0046] 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 and in contact.

[0047] 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.

[0048] The intake module 170 intakes 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.

[0049] Furthermore, it can move between the frame unit 110 and the nuclear reactor 10 and perform an intake operation. For example, it can be provided to be movable up and down in the same manner as the purge module 140.

[0050] Referring to FIG. 6, a method for operating 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 power plant dismantling work on the nuclear reactor 10 is performed by the nuclear reactor dismantling device 100.

[0051] 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 from the nuclear reactor 10. Such a nuclear reactor dismantling device 100 includes functions for lifting the nuclear reactor.

[0052] A cutting module 120 is provided on the frame unit 110 to perform cutting work on the nuclear reactor 10. A bar-shaped interlocking fixing module 130 enters the internal region M1 of the nuclear reactor 10 to interlock the frame unit 110 and the nuclear reactor 10.

[0053] Such an interlocking fixing module 130 has a hollow region S1 formed therein. The purge module 140 enters the hollow region 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 work.

[0054] 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.

[0055] The embodiments of the present invention have been described above with reference to the accompanying drawings. Those of ordinary skill 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 aspects and not restrictive.

Claims

Claim 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 configured to shield the nuclear reactor and prevent external release of contaminants of the nuclear reactor; a cutting module provided on the frame unit and configured to perform a cutting operation on the nuclear reactor; a fire extinguishing module provided on the frame unit and configured to melt by a heat source of a fire when a fire occurs on the nuclear reactor and automatically supply an internal fire extinguishing fluid to the outside; wherein the frame unit includes: an upper structure portion and a lower structure portion facing the upper structure portion; wherein the fire extinguishing module includes: a plurality of the fire extinguishing modules provided between the upper structure portion and the lower structure portion and configured to supply the fire extinguishing fluid to a fire occurrence side where the fire has occurred in response to the heat source; the lower structure portion of the frame unit is provided as a ring-shaped body surrounding a peripheral portion of the nuclear reactor; a plurality of the fire extinguishing modules are arranged on a peripheral portion of the lower structure portion, and the fire extinguishing fluid is respectively supplied to the fire occurrence side by the heat source. A method for decommissioning a nuclear power plant. Claim 2. 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 configured to shield the nuclear reactor and prevent external release of contaminants of the nuclear reactor; a cutting module provided on the frame unit and configured to perform a cutting operation on the nuclear reactor; a fire extinguishing module provided on the frame unit and configured to melt by a heat source of a fire when a fire occurs on the nuclear reactor and automatically supply an internal fire extinguishing fluid to the outside; wherein the frame unit includes: an upper structure portion and a lower structure portion facing the upper structure portion; wherein the fire extinguishing module includes: a plurality of the fire extinguishing modules provided between the upper structure portion and the lower structure portion and configured to supply the fire extinguishing fluid to a fire occurrence side where the fire has occurred in response to the heat source; wherein the fire extinguishing module includes: an outer cylinder including a hollow metal material; an inner cylinder housed inside the outer cylinder and filled with the fire extinguishing fluid therein; the outer cylinder is formed with a cut portion in which at least a part of a peripheral portion of an outer peripheral surface is cut in a horizontal direction or a vertical direction. A method for decommissioning a nuclear power plant, wherein when the inner cylindrical body melts in response to the fire, the fire extinguishing fluid is supplied to the outside through the cut portion.

3. 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 cutting operations on the nuclear reactor; and a fire extinguishing module provided on the frame unit, which melts by the heat source of the fire when a fire occurs on the nuclear reactor, and automatically supplies the internal fire extinguishing fluid to the outside, wherein the frame unit includes an upper structure portion and a lower structure portion facing the upper structure portion; wherein the fire extinguishing module is provided in a plurality between the upper structure portion and the lower structure portion, and supplies the fire extinguishing fluid to the fire occurrence side where the fire has occurred in response to the heat source; the lower structure portion of the frame unit is provided as a ring-shaped body surrounding the peripheral edge of the nuclear reactor; the fire extinguishing module is arranged in a plurality on the peripheral edge of the lower structure portion, and supplies the fire extinguishing fluid to the fire occurrence side by the heat source respectively. A decommissioning device for a nuclear power plant.

4. 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 cutting operations on the nuclear reactor; and a fire extinguishing module provided on the frame unit, which melts by the heat source of the fire when a fire occurs on the nuclear reactor, and automatically supplies the internal fire extinguishing fluid to the outside, wherein the frame unit includes an upper structure portion and a lower structure portion facing the upper structure portion; wherein the fire extinguishing module is provided in a plurality between the upper structure portion and the lower structure portion, and supplies the fire extinguishing fluid to the fire occurrence side where the fire has occurred in response to the heat source; wherein the fire extinguishing module includes an outer cylindrical body made of a hollow metal material; an inner cylindrical body accommodated inside the outer cylindrical body and filled with the fire extinguishing fluid inside; a cut portion is formed on at least a part of the peripheral edge of the outer peripheral surface of the outer cylindrical body, which is cut in the horizontal or vertical direction; when the inner cylindrical body melts in response to the fire, the fire extinguishing fluid is supplied to the outside through the cut portion. A decommissioning device for a nuclear power plant.

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