JP2006038730A - Dismantling method for nuclear reactor pressure vessel - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To dismantle a nuclear reactor pressure vessel safely in a short period of time. <P>SOLUTION: This dismantling method includes a first process for dismantling and removing an inner structure of the nuclear reactor pressure vessel 14, a second process for pushing up the pressure vessel 14 by means of a thereunder-placed jack system 30, and a third process for cutting off the pressure vessel 14 by a length by which it is pushed up by a cutter 32 placed at a fixed position in a nuclear reactor well 18. By repeating the second and third processes, the pressure vessel 14 is cut off sequentially from an upper part at the fixed position in the reactor well 18. Cut pieces obtained by the cutting in the third process are transferred into water in a dryer separator pool 22. In executing the second and third processes, an upper opening in the reactor well 18 is closed with a well shield plug 20. <P>COPYRIGHT: (C)2006,JPO&NCIPI

Description

  The present invention relates to a method for dismantling a reactor pressure vessel.

  At nuclear power plants and other nuclear facilities, decommissioning will be taken once the operation mission is complete. Decommissioning will be performed in the order of system decontamination, safe storage, and dismantling. In dismantling and removal, the internal piping and equipment are removed, and then the building is removed. In dismantling and removal, it is necessary not to scatter radioactive materials to the outside, and to prevent exposure to workers engaged in dismantling and removal. Among the equipment, removal of the reactor pressure vessel, which is the heart of the reactor facility, is the most difficult task.

  FIG. 12 is a cross-sectional view showing an example of a main part of the reactor building. A reactor containment vessel 2 is formed in the reactor building 1, and a reactor pressure vessel 3 is installed in the reactor containment vessel 2. A heat shielding wall 4 is provided around the reactor pressure vessel 3. The upper space in the reactor containment vessel 2 is generally called a reactor well, and the upper opening of the reactor well 5 is sealed by a well shield plug 6. A dryer separator pool 7 filled with water is disposed on the side of the reactor well 5. The uppermost part of the reactor building 1 is an operation area 8, and an overhead crane 9 is disposed in the operation area 8 so as to be able to travel.

  In a nuclear power plant with a generation capacity of 400,000 kW, the reactor pressure vessel 3 has a diameter of about 5 m, a height of about 20 m, and a fuselage wall thickness of about 150 mm. Further, the total weight of the reactor pressure vessel 3 including the internal structure such as the shroud reaches about 700 tons, and the cavity weight excluding the internal structure reaches about 350 tons. As described above, it is difficult to dismantle and remove such a huge reactor pressure vessel 3 while preventing radioactive substances from being scattered outside and preventing exposure to workers.

  Patent Document 1 discloses a method of cutting an internal structure of a reactor pressure vessel. In the method described in Patent Document 1, the reactor pressure vessel and the reactor well are filled with water, the reactor internal structure is first cut, and the cut reactor structure is moved to the reactor well. Next cut. According to this method, since the cutting is performed in water, radioactive substances are hardly scattered to the outside, and exposure to workers can be reduced. Moreover, since the primary cutting and the secondary cutting can be performed in parallel, the working time can be shortened and the exposure of the worker can be reduced. Patent Document 2 also discloses a method for cutting an internal structure of a reactor pressure vessel underwater. The method described in Patent Document 2 is characterized in that an existing fuel exchanger or an overhead crane is used for the cutting operation of the in-furnace structure and the transfer of the cut object. However, if the underwater cutting method disclosed in Patent Document 1 or Patent Document 2 is applied to the dismantling of the reactor pressure vessel main body, the huge reactor pressure vessel is immersed in water itself. Is very difficult and unsuitable.

  Patent Document 3 discloses a method of cutting and dismantling a reactor pressure vessel in the air. In the method described in Patent Document 3, mortar is filled and cured as a shielding material in the reactor pressure vessel, and then the entire reactor pressure vessel is divided into three so as to be cut along a cross section. Carry out sequentially. When unloading, a lifting device is installed in the operation area at the top of the reactor building, and each divided body cut in the reactor well is lifted from the upper opening of the reactor well by the lifting device. However, the method described in Patent Document 3 generates a large amount of mortar cutting powder filled inside when the reactor pressure vessel is cut. This cutting powder is highly radioactive and must be treated as radioactive waste. In addition, the reactor pressure vessel is cut in a fixed state. However, as described above, the reactor pressure vessel is surrounded by the heat shielding wall, so a cutting machine such as a wire saw is set at a desired cutting position. However, it is extremely difficult to operate. Even if it is possible, it is necessary to prepare a part or all of the heat shielding wall in advance, which requires a lot of labor and increases the risk of exposure to the worker.

Patent Document 4 discloses a method of cutting and dismantling a reactor pressure vessel sequentially from the upper surface. However, as described above, a cutting apparatus for scraping a huge reactor pressure vessel having a diameter of about 5 m, a height of about 20 m, and a fuselage wall thickness of about 150 mm is difficult to realize. Another problem is that the cutting period is several months.
JP-A-8-240663 JP-A-8-75892 JP 2004-77149 A JP-A-9-105799

  An object of the present invention is to improve the problems of the prior art, and to dismantle the reactor pressure vessel in a short time and safely, and to dismantle the reactor pressure vessel that can reduce secondary waste. Is to provide.

  In order to achieve the above object, the reactor pressure vessel dismantling method according to the present invention includes a jack disposed below the reactor pressure vessel, and while pushing up the reactor pressure vessel with the jack, The reactor pressure vessel is sequentially cut from the upper part at a fixed position.

  More specifically, the reactor pressure vessel dismantling method according to the present invention includes a first step of dismantling and removing the internal structure of the reactor pressure vessel, and a first step of pushing up the reactor pressure vessel by a jack installed below. Including a second step and a third step of cutting the reactor pressure vessel by the amount pushed up by a cutting machine arranged at a fixed position in the reactor well, and repeating the second step and the third step. And

  It is desirable to use a cylinder as a jack used in the second step and move the cylinder sequentially upward by adding a spacer below the cylinder.

  It is desirable that the cutting machine used in the third step is a milling cutting machine or a band saw cutting machine. In the third step, it is desirable that the reactor pressure vessel is cut in a circle and cut in parallel. Preferably, the cut piece cut in the third step is transferred into the water of the pool facility.

  When performing the second step and the third step, it is desirable to close the upper opening of the reactor well with a well shield plug. In addition, when the second and third steps are performed, it is desirable to support the reactor pressure vessel with a roll prevention member that protrudes from the heat shielding wall. Preferably, when performing the second step and the third step, a foreign matter fall prevention means is disposed in a gap between the outer surface of the reactor pressure vessel and the inner surface of the heat shielding wall, It is desirable to be able to prevent the cutting powder generated when the third step is performed.

  According to the reactor pressure vessel dismantling method of the present invention, a jack is disposed below the reactor pressure vessel, and the reactor pressure vessel is placed at a fixed position in the reactor well while the reactor pressure vessel is pushed up by the jack. Cutting was performed sequentially from the top. For this reason, the reactor pressure vessel can be disassembled safely in a short time. Moreover, since the cylinder is sequentially moved upward by adding a spacer below the cylinder as a jack, the reactor pressure vessel can be pushed up stepwise with simple equipment.

  If a cutting type cutting machine such as a milling cutting machine or a band saw cutting machine is used in the third step, the amount of secondary waste generated can be greatly reduced as compared with a thermal cutting type such as plasma cutting. In addition, at a fixed position in the reactor well, ring cutting and longitudinal cutting of the reactor pressure vessel were performed in parallel. For this reason, the reactor pressure vessel can be quickly cut out as a cut piece of a desired size. Further, since the cut pieces are transferred into the water of the pool facility, the pool facility can take safety measures such as automatically storing the received radioactive cut pieces in a storage container in the water. In addition, when the second step and the third step were performed, the upper opening of the reactor well was closed with a well shield plug. For this reason, the exposure to the worker engaged in another work in the operation area can be greatly reduced.

  Furthermore, when carrying out the second step and the third step, the reactor pressure vessel is supported by a roll prevention member protruding from the heat shielding wall. For this reason, the attitude of the reactor pressure vessel can be stably maintained, and the reactor pressure vessel can be pushed up or cut smoothly. In addition, this roll prevention member can ensure earthquake resistance during dismantling. Furthermore, when performing the second step and the third step, foreign matter fall prevention means is disposed between the outer surface of the reactor pressure vessel and the inner surface of the reactor containment vessel. For this reason, it is possible to prevent an operator engaged in the operation of the jack from being injured by falling objects from above or being exposed to radioactive cutting powder.

DESCRIPTION OF EMBODIMENTS Hereinafter, an embodiment of a reactor pressure vessel dismantling method according to the present invention will be described based on the drawings. FIG. 1 is a cross-sectional view for explaining an embodiment of the present invention. FIG. 2 is a cross-sectional view of the main part of FIG.
A reactor containment vessel 12 is formed in the reactor building 10, and a reactor pressure vessel 14 is installed in the reactor containment vessel 12. A heat shielding wall 16 is provided around the reactor pressure vessel 14. The upper space in the reactor containment vessel 12 is called a reactor well, and the upper opening of the reactor well 18 is sealed by a well shield plug 20. A dryer separator pool 22 filled with water is disposed on the side of the reactor well 18. The uppermost part of the reactor building 10 is an operation area 24, and an overhead crane 26 is movably disposed in the operation area 24.

  First, as a preliminary preparation, the jack system 30 is disposed below the reactor pressure vessel 14. A cutting device 32 is disposed at a fixed position of the reactor well 18. The cutting device 32 is supported by a bracket 34 protruding from the inner wall of the reactor containment vessel 12. A plurality of brackets 36 are disposed at the upper end of the heat shielding wall 16, and a roller 38 is rotatably attached to the tip of the bracket 36. When the roller 38 is in rolling contact with the outer surface of the reactor pressure vessel 14, the roll of the reactor pressure vessel 14 is prevented. The reactor well 18 and the dryer separator pool 22 are communicated with each other through a communication port 40. A monorail 42 is stretched between the reactor well 18 and the dryer separator pool 22 through the communication port 40, and a cut piece, which will be described later, is removed from the reactor well 18 to the dryer separator pool by a hoist 44 that is movably attached to the monorail 42. Transfer to 22 The dryer separator pool 22 is open at the top, and a green house 48 is provided in the region of the operation area 24 corresponding to the opening 46. The green house 48 is a temporary airtight chamber for preventing radioactive fine particles diffused from the cut pieces carried into the dryer separator pool 22 from diffusing into other regions of the operation area 24.

  FIG. 3 is a plan view showing a conceptual configuration of the cutting device 32. The cutting device 32 includes an annular base 32A, on which one milling cutting machine 50 for cutting a ring and four milling cutting machines 52 for longitudinal cutting are mounted. The milling cutter 50 is configured to be able to circulate along the base 32 </ b> A, and cuts the reactor pressure vessel 14 in a circle by moving the end mill in a lateral direction with respect to the reactor pressure vessel 14. The four milling cutters 52 are simultaneously used at a fixed position at the time of cutting, and vertically cut the reactor pressure vessel 14 by moving the end mill in the longitudinal direction with respect to the reactor pressure vessel 14. Each of the milling cutters 52 is movable along the base 32A within an angle range of 90 degrees. Therefore, when it is desired to reduce the vertical cutting pitch, the vertical cutting can be performed by moving each milling cutter 52 to a position indicated by a two-dot chain line, for example. Note that a band saw type cutting machine may be employed instead of the milling cutting machine 50 as a cutting machine for ring cutting.

  Next, the jack system 30 will be described. FIG. 4 is a side view showing the main configuration of the jack system 30. A base 54 is disposed below the reactor pressure vessel 14. A support 56 is mounted on the base 54, and a receiving plate 62 is fixed to the upper part of the support 56. When the receiving plate 62 contacts the lower end of the fuel rod control pipe group 63 at the bottom of the reactor pressure vessel 14, the load of the reactor pressure vessel 14 is supported by the support 56 through the receiving plate 62. A plurality of cylinders 58 are suspended from the receiving plate 62 via the telescopic rod 60.

  In order to push up the reactor pressure vessel 14 by the jack system 30, the spacer 64 is suspended and fixed to the lower end of each cylinder 58 from the state shown in FIG. 4 as shown in FIG. Next, as shown in FIG. 5B, the telescopic rod 60 of the cylinder 58 is extended. Then, the load of the reactor pressure vessel 14 shifts to the cylinder 58 side, and a space S1 is created below the support column 56. Next, as shown in FIG. 5 (3), the auxiliary column 66 is suspended and fixed to the lower end of the column 56 using the space S1.

  Next, as shown in FIG. 6A, the telescopic rod 60 of the cylinder 58 is shortened. Then, the load of the reactor pressure vessel 14 shifts to the support 56 side, and a space S2 is created below the cylinder 58. Next, as shown in FIG. 6 (2), the spacer 64A is suspended and fixed to the lower end of the cylinder 58 using the space S2. Thereafter, by repeating the same procedure, the auxiliary struts 66,... Are sequentially added below the support column 56, and the spacers 64, 64A,. As a result, the reactor pressure vessel 14 can be lifted step by step.

  FIG. 7 is a flowchart showing another embodiment of the jack system 30. In this embodiment, as shown in FIG. 7 (1), a cylinder 67 is mounted on the base 54, and the connecting column 68 is suspended and fixed to the receiving plate 62. A horizontal bar 67B is attached to the upper end of the telescopic rod 67A of the cylinder 67. The connecting column 68 is provided with a connecting tool 68A in two upper and lower stages. By connecting both ends of the horizontal bar 67B to the connecting tool 68A, the connecting column 68 moves up and down in accordance with the expansion and contraction of the telescopic rod 67A. When the telescopic rod 67A is extended from the state shown in FIG. 7 (1), a space S3 is formed below the connecting column 68 as shown in FIG. 7 (2). Next, as shown in FIG. 7 (3), the auxiliary connecting column 69 is suspended and fixed to the lower end of the connecting column 68 using the space S 3.

  Next, as shown in FIG. 7 (4), the horizontal rod 67B is changed to be connected to the lower connection tool 68A, and then the telescopic rod 67A is extended as shown in FIG. 7 (5). Next, as shown in FIG. 7 (6), the next auxiliary connecting column 69 </ b> A is added to the lower end of the auxiliary connecting column 69 using the space formed below the auxiliary connecting column 69. Thereafter, the reactor pressure vessel 14 can be lifted step by step by repeating the same procedure. In this embodiment, since the cylinder 67 is always in a fixed position below, it is not necessary to move the pump unit or extend the hose to operate the cylinder 67.

  Next, the procedure of the dismantling method will be described. FIG. 8 is a cross-sectional view of the reactor pressure vessel 14, and the reactor pressure vessel 14 is roughly divided into an upper lid 70, a body 72, and a lower mirror 74. The radioactivity level varies greatly depending on the internal structure, the radioactivity level in the central region X of the fuselage 72 where the shroud and fuel assembly are arranged is the highest, the upper and lower regions Y are the middle level, the upper lid 70 and the lower mirror Region Z far from central region X, such as 74, is lowest. In disassembling the reactor pressure vessel 14, first, the upper lid 70 having a low radioactivity level is removed. The operation of removing the upper lid 70 is performed by removing the bolts of the flange 76 that connects the upper lid 70 and the body 72. Next, the well shield plug 20 is removed by the overhead crane 26 shown in FIG. 1, and the upper opening of the reactor well 18 is opened. Next, the upper lid 70 removed by the overhead crane 26 is pulled out from the upper opening and disposed of by an appropriate method. FIG. 1 shows a state where the upper lid 70 removed at one corner of the operation area 24 is temporarily placed and stored.

  In the present embodiment, substantial dismantling and removal work proceeds from the state shown in FIG. In the first step, the internal structure of the reactor pressure vessel 14 is dismantled and removed. For this first step, for example, the dismantling and removal method by underwater cutting described in Patent Document 1 or Patent Document 2 is employed. However, this first step may be performed by air cutting. In the state in which the reactor pressure vessel 14 is emptied by the first step, the process proceeds to the next second step.

  In the second step, the reactor pressure vessel 14 is pushed up by the jack system 30 described above. When the reactor pressure vessel 14 is pushed up, when the upper portion of the reactor pressure vessel 14 reaches the cutting position in the cutting device 32 as shown in FIG. 9, the pushing-up operation by the jack system 30 is stopped, and the next third step Proceed to

  In the third step, one milling cutter 50 for cutting a ring and four milling cutters 52 for longitudinal cutting are automatically driven in parallel. The milling cutter 50 for ring cutting moves around along the outer peripheral surface of the reactor pressure vessel 14, and sets the end mill at a position corresponding to one push-up height h of the reactor pressure vessel 14. The furnace pressure vessel 14 is cut in a circle. On the other hand, the four milling cutters 52 for longitudinal cutting vertically cut the reactor pressure vessel 14 at the pitch p shown in FIG. FIG. 10 is a side view showing a cutting state. For convenience of explanation, the cutting machine is not shown in the figure. In FIG. 10, the cutting line c <b> 1 is a ring cutting line by the milling cutting machine 50, and the cutting line c <b> 2 is a vertical cutting line by the milling cutting machine 52. Longitudinal cutting by the four milling cutters 52 is preceded, and the circular cutting is followed. As a result, when the cutting line c1 reaches the preceding cutting lines c2, c2,..., The cutting pieces 80 are sequentially separated from the reactor pressure vessel.

  When the cut piece 80 is cut off, the cut piece 80 is held by the chuck means 82 suspended from the hoist 44 shown in FIG. Therefore, the cut piece 80 cut off is suspended by the hoist 44 without falling. The hoist 44 travels along the monorail 42 and transfers the cut piece 80 from the reactor well 18 toward the dryer separator pool 22. In the dryer separator pool 22, safety measures such as automatically storing the received cut piece 80 in a storage container in water can be taken. When the size of the cut piece 80 accommodated in the storage container is set to a rectangle of, for example, 100 cm × 80 cm, the above-described pushing height h may be set to 100 cm, and the vertical cutting pitch p may be set to 80 cm.

  When the second step and the third step are performed, the upper opening of the reactor well 18 is closed with the well shield plug 20. The well shield plug 20 shields radiation emitted from the reactor pressure vessel 14. For this reason, the exposure to the worker engaged in another work in the operation area 24 can be significantly reduced. Further, when performing the second step and the third step, the roller 38 disposed at the upper end of the heat shielding wall 16 as shown in FIG. 2 is in rolling contact with the outer surface of the reactor pressure vessel 14, The rolling of the reactor pressure vessel 14 is prevented. For this reason, the attitude | position of the reactor pressure vessel 14 can be maintained stably, and the reactor pressure vessel 14 can be pushed up or cut smoothly. The roller 38 also functions as an earthquake-resistant means when an earthquake occurs during the dismantling period of the reactor pressure vessel 14.

  Further, when performing the second step and the third step, the foreign matter fall prevention means 84 is disposed between the outer surface of the reactor pressure vessel 14 and the inner surface of the reactor containment vessel 12 as shown in FIG. It is desirable to install. By this foreign matter fall prevention means 84, it is possible to prevent an injury accident caused by a fallen object from above on an operator who is engaged in the operation of the jack system 30. As this foreign matter fall prevention means 84, a net-like thing can be considered. However, the net-shaped one cannot prevent the radioactive cutting powder falling when the third step is performed. Therefore, it is more desirable that the foreign matter fall prevention means 84 is a means capable of preventing the fall of the cutting powder.

  When one batch of the second process and the third process is completed, the reactor pressure vessel 14 is sequentially cut from the top by repeating the second process and the third process. As described above, since the reactor pressure vessel 14 has a difference in radioactivity level depending on each part, the dimension of the cut piece 80 is set to a preferable value according to the radioactivity level, and the set value is realized. The push-up amount h of the reactor pressure vessel 14 for one batch and the longitudinal cutting pitch p are determined, and the second step and the third step are repeated.

  When the cutting of the body 72 of the reactor pressure vessel 14 shown in FIG. 8 is completed by repeating the second step and the third step, the lower mirror 74 remains. The state at this time is shown in FIG. The lower mirror 74 is a portion (see FIG. 8) where the radioactivity level in the region Z is the lowest as described above. Therefore, after removing the well shield plug 20, the lower mirror 74 is transferred to the operation area by the overhead crane 26 and disposed of in an appropriate manner in the same manner as the upper lid 70.

  The entire process of dismantling the reactor pressure vessel 14 is completed according to the procedure described above. According to the reactor pressure vessel dismantling method of the present embodiment, the jack system 30 is disposed below the reactor pressure vessel 14, and the reactor pressure vessel 14 is pushed up by the jack system 30, while The reactor pressure vessel 14 was cut sequentially from the top at a fixed position. For this reason, the reactor pressure vessel 14 can be disassembled safely in a short time. Further, since the cylinder 58 is used as the jack system 30 and the spacers 64, 64A,... Are added below the cylinder, the cylinder 58 is sequentially moved upward. The pressure vessel 14 can be pushed up stepwise.

  Further, the cutting device 32 disposed at a fixed position in the reactor well 18 is configured to include a milling cutting machine 50 for round cutting and a milling cutting machine 52 for vertical cutting, and the circular cutting and vertical cutting of the reactor pressure vessel 14 are performed. Cutting was done in parallel. For this reason, the reactor pressure vessel 14 can be quickly cut out as a cut piece 80 having a desired size. Further, since the cut piece 80 is transferred into the water of the dryer separator pool 22, the dryer separator pool 22 is provided with safety measures such as automatically storing the received radioactive cut piece 80 in a storage container in the water. Can be taken. In addition, when the second step and the third step are performed, the upper opening of the reactor well 18 is closed with the well shield plug 20. For this reason, the exposure to the worker engaged in another work in the operation area 24 can be significantly reduced.

  Furthermore, the reactor pressure vessel 14 was supported by a roller 38 protruding from the heat shielding wall 16 when performing the second step and the third step. For this reason, the attitude | position of the reactor pressure vessel 14 can be maintained stably, and the reactor pressure vessel 14 can be pushed up or cut smoothly. Further, when performing the second step and the third step, the foreign matter fall prevention means 84 is disposed between the outer surface of the reactor pressure vessel 14 and the inner surface of the reactor containment vessel 12. For this reason, it is possible to prevent an operator involved in the operation of the jack system 30 from being injured by falling objects from above or being exposed to radioactive cutting powder.

  In the above embodiment, the jack system 30 has been described with the configuration in which the cylinder is sequentially moved upward by adding a spacer below the cylinder and the configuration shown in FIG. However, the jack according to the present invention is not limited to the jack system 30 described above. For example, a telescovic cylinder can be used instead. Further, in the above embodiment, when cutting the reactor pressure vessel 14 at a fixed position in the reactor well 18, the ring cutting and the longitudinal cutting are performed in parallel. However, the method according to the present invention is not limited to the above method. For example, only the circular cutting may be performed at a fixed position in the reactor well, and the circular cutting may be transferred to a dryer separator pool and chopped into pieces of a desired size in the water of the dryer separator pool. Further, the cutting machine is not limited to a mechanical cutting machine such as a milling cutting machine or a band saw cutting machine, but may be a gas cutting machine, a plasma cutting machine, a high-pressure water cutting machine, or the like.

  In the above embodiment, the cut piece 80 is transferred into the water of the dryer separator pool 22. However, the present invention is not limited to this, and the used fuel storage pool can be changed from the transport destination of the cut pieces to the dryer separator pool. Further, when the radioactive level of the cut piece is relatively low, safety measures such as storing the cut piece in the storage container in the air can be taken.

  In the above embodiment, the upper opening of the reactor well 18 is closed with the well shield plug 20 when the second step and the third step are performed. However, the present invention is not limited to this, and the upper opening of the reactor well can be opened when there is little risk of exposure to workers in the operation area.

It is sectional drawing for demonstrating embodiment of this invention. It is sectional drawing of the principal part of FIG. 3 is a plan view showing a conceptual configuration of a cutting device 32. FIG. 1 is a side view showing a main configuration of a jack system 30. FIG. FIG. 3 is a first explanatory diagram showing an operation procedure of the jack system 30. FIG. 6 is a second explanatory diagram showing an operation procedure of the jack system 30. It is a procedure figure which shows another embodiment of the jack system. 2 is a cross-sectional view of a reactor pressure vessel 14. FIG. 3 is a side view of the cutting device 32. FIG. 3 is a side view showing a cutting state of a reactor pressure vessel 14. FIG. It is a side view of the principal part which shows the state of the final stage of dismantling. It is sectional drawing which showed an example of the principal part of a reactor building.

Explanation of symbols

10 ......... Reactor building, 12 ......... Reactor containment vessel, 14 ......... Reactor pressure vessel, 16 ......... Heat shield wall, 18 ......... Reactor well, 20 ......... Well shield plug, 22 ......... Drier separator pool, 24 ......... Operating area, 26 ......... Overhead crane, 30 ......... Jack system, 32 ......... Cutting device, 38 ......... Roller, 42 ......... Monorail, 44 ... ...... Hoist, 48 ......... Greenhouse, 50 ......... (for cutting round) Milling cutter, 52 ......... (for vertical cutting) Milling cutter, 54 ......... Base, 56 ......... Post, 58 ......... Cylinder, 60 ......... Extensible rod, 62 ......... Receiver plate, 63 ......... Fuel rod control tube group, 64, 64A ......... Spacer, 66 ...... Auxiliary strut, 67 ......... Cylinder , 67A ... Telescopic rod, 6 B ......... Horizontal bar, 68 ......... Connecting post, 68A ......... Connector, 69 ...... Auxiliary connecting post, 70 ......... Upper lid, 72 ...... Body, 74 ......... Lower mirror, 80 ... ...... Cut piece, 82... Chuck means, 84.

Claims (10)

  An atomic device characterized in that a jack is disposed below the reactor pressure vessel, and the reactor pressure vessel is sequentially cut from above at a fixed position in the reactor well while the reactor pressure vessel is pushed up by the jack. Dismantling method for furnace pressure vessels.   A first step of dismantling and removing the internal structure of the reactor pressure vessel, a second step of pushing up the reactor pressure vessel by a jack installed below, and a cutting machine disposed at a fixed position in the reactor well A reactor pressure vessel dismantling method comprising: a third step of cutting the reactor pressure vessel by the amount pushed up, and repeating the second step and the third step.   The reactor pressure vessel according to claim 2, wherein a cylinder is used as a jack used in the second step, and a cylinder is sequentially moved upward by adding a spacer below the cylinder. Demolition method.   The reactor pressure vessel dismantling method according to claim 2, wherein the cutting machine used in the third step is a milling cutting machine or a band saw cutting machine.   3. The reactor pressure vessel disassembly method according to claim 2, wherein in the third step, the ring cutting and the longitudinal cutting of the reactor pressure vessel are performed in parallel.   The method for dismantling a reactor pressure vessel according to claim 2, wherein the cut pieces cut in the third step are transferred into the water of a pool facility.   The reactor pressure vessel dismantling method according to claim 2, wherein when the second step and the third step are performed, an upper opening of the reactor well is closed with a well shield plug.   3. The reactor pressure vessel disassembly according to claim 2, wherein the reactor pressure vessel is supported by a roll prevention member that protrudes from a heat shielding wall when the second step and the third step are performed. Construction method.   The foreign matter fall prevention means is disposed in a gap between the outer surface of the reactor pressure vessel and the inner surface of the containment vessel when performing the second step and the third step. Dismantling method for nuclear reactor pressure vessels. The method for dismantling a reactor pressure vessel according to claim 9, wherein the foreign matter fall prevention means is a means capable of preventing the fall of cutting powder generated when the third step is performed.

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