JP2012255742A - Conveyance method of radioactive structure member - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a conveyance method of radioactive structure member with which the time required for nuclear decommissioning can be reduced.SOLUTION: A dosage rate and a temperature of a plant structure member to be carried out are measured inside a reactor building 73 in which nuclear decommissioning is to be performed, and the plant structure member is then accommodated in an accommodation container. The accommodation container accommodating the plant structure member therein carried from the reactor building 73 and decontaminated in a decontamination chamber 58 is moved on a carrier truck along with a traveling rail 44A. On the basis of a dosage rate measurement, a temperature measurement and an identification number added to the accommodation container, a control device 64A determines a decontamination building 60, a high dosage rate structure member preservation building 61 or a fuel preservation building 62 that is a conveyance destination of the accommodation container. If the conveyance destination of the accommodation container is the decontamination building 60, the control device 64A turns at 90° a turn table located at an intersection of a traveling rail 46 communicated to the decontamination building 60 and the traveling rail 44A. Thus, the carrier truck with the accommodation container placed thereon reaches the decontamination building 60.

Description

  The present invention relates to a method for transporting a radioactive structural member, and more particularly, to a method for transporting a radioactive structural member suitable for application to a nuclear power plant having a plurality of boiling water nuclear power plants.

  When the end of life is reached, the nuclear power plant is dismantled and the waste generated by the dismantling is mainly radioactive metal waste and concrete waste. These radioactive wastes are radioactive wastes, and a method for separating and clearing these radioactive wastes is described in Japanese Patent Application Laid-Open No. 2007-248066.

  In the separation and clearance processing method described in Japanese Patent Laid-Open No. 2007-248066, radioactive waste generated by dismantling and removal is separated into a clearance object and a clearance object. The clearance object is a metal waste and a concrete waste, and is other than a clearance object. Non-clearance items are radioactive wastes with high radioactivity levels, combustibles, and radioactive wastes that are difficult to decontaminate. For clearance objects, decontamination is performed to remove highly contaminated parts. The surface contamination density is measured for the clearance object after decontamination, and the radioactivity concentration is measured for the clearance object that has been confirmed to be free of highly contaminated sites.

JP 2007-248066 A

  Japanese Patent Application Laid-Open Publication No. 2007-248066 that describes the separation of radioactive waste generated by dismantling and removal of a nuclear power plant does not mention the transportation of radioactive structural members generated by the dismantling and removal of a plurality of nuclear power plants. When dismantling and removing a plurality of nuclear power plants within one nuclear power plant, a large amount of radioactive structural members are generated as a result of the dismantling and removal. Therefore, it is necessary to efficiently transport the radioactive structural members. .

  An object of the present invention is to provide a method for transporting a radioactive structural member that can shorten the time required for decommissioning work.

  The feature of the present invention that achieves the above-described object is to measure the dose rate of a plant structural member that is a radioactive structural member to be carried out in a reactor building to be decommissioned, and to obtain image information of the plant structural member. The plant structure member obtained by acquiring and measuring the dose rate and storing the image information is stored in a storage container in the reactor building, and the target location for transporting the storage container storing the plant component member is measured. The dose rate, the shape information of the plant structural member obtained based on the acquired video information, and the identification information of the storage container storing the plant structural member, and determining the storage container storing the plant structural member It is to be transported to the determined destination.

  The plant structural member is stored based on the measured value of the dose rate of the plant structural member that is the radioactive structural member to be carried out, the shape information of the plant structural member, and the identification information of the storage container storing the plant structural member. Since the target location for transporting the storage containers is determined, a plurality of storage containers storing the plant structural members can be efficiently transported to the target locations for the respective storage containers. For this reason, the time required for decommissioning work can be shortened.

  According to the present invention, the time required for decommissioning work can be shortened. In particular, when the decommissioning operations of a plurality of nuclear power plants are performed in parallel, the time required for these decommissioning operations can be shortened.

It is a block diagram of the radioactive structure member conveyance apparatus used for the conveyance method of the radioactive structure member of Example 1 which is one suitable Example of this invention. It is an II-II arrow line view of FIG. It is explanatory drawing which shows arrangement | positioning of each traveling rail which connects each temporary stand provided with respect to each reactor building in FIG. 1, and traveling rails 54 and 55. FIG. It is a block diagram of the operation | work unit shown in FIG. 1 arrange | positioned ranging over a nuclear reactor building, and is IV-IV sectional drawing of FIG. It is a block diagram of the crane unit shown in FIG. 1 arrange | positioned ranging over a nuclear reactor building, and is VV sectional drawing of FIG. It is an enlarged plan view of the work unit and crane unit shown in FIG. It is a block diagram of the crane unit of the radioactive structure member conveying apparatus used for the conveyance method of the radioactive structure member of Example 2 which is another Example of this invention. It is a block diagram of the work unit of the radioactive structure member conveying apparatus used for the conveyance method of the radioactive structure member of Example 3 which is another Example of this invention.

  Examples of the present invention will be described below.

  A method for transporting a radioactive structural member according to embodiment 1, which is a preferred embodiment of the present invention, will be described with reference to FIGS.

  First, the radioactive structure member conveying apparatus 1 used for the radioactive waste transfer method of the present embodiment will be described with reference to FIGS. The radioactive structural member transport device 1 includes a work unit 2, a crane unit 22, and a transfer device 43.

  The work unit 2 includes a traveling carriage 3, work devices 5 and 11, and tool storage devices 16A and 16B. In the traveling carriage 3, the tool storage device 16 </ b> A is disposed next to the work device 5, and the tool storage device 16 </ b> B is disposed next to the work device 11. The work devices 5 and 14 and the tool storage devices 16A and 16B arranged next to the work device 5 are movably attached to the traveling carriage 3.

  The work device 5 includes a trolley 6, a support member 6A, a dose rate meter 8, a work arm 10, and a rotating body 102A. The trolley 6 is attached to the traveling carriage 3 so as to be movable in the longitudinal direction of the traveling carriage 3, and the support member 6A is attached to two wires 7 attached to a winding device (not shown) installed in the trolley 6. . The dose rate meter 8 is attached to the support member 6A, and the rotating body 102A is rotatably attached to the support member 6A. A work arm 10 is provided on the rotating body 102A.

  The work device 11 includes a trolley 12, a support member 13, a work arm 15, and a rotating body 102B (see FIG. 4). The trolley 12 is attached to the traveling carriage 3 so as to be movable in the longitudinal direction of the traveling carriage 3, and the support member 13 is attached to two wires 14 attached to a winding device (not shown) installed in the trolley 12. . The rotating body 102B is rotatably attached to the support member 13, and the working arm 15 is provided on the rotating body 102B. The dose rate meter 8 may be attached to the support member 13 of the work apparatus 11.

  The tool storage device 16A includes a trolley 17A and a tool storage unit 18A. A trolley 17 </ b> A is attached to the traveling carriage 3 so as to be movable in the longitudinal direction of the traveling carriage 3. A tool storage unit 18A having a tool changer 20A is attached to two wires 19A attached to a winding device (not shown) installed on the trolley 17A. The rotatable tool changer 20A stores a tool 21A used for work, for example, a gripping device, a cutting machine, a squeezer, and a breaker, although not shown. These tools 21 </ b> A are attached to the distal end portion of the work arm 10 one by one.

  The tool storage device 16B includes a trolley 17B and a tool storage unit 18A. The trolley 17 </ b> B is attached to the traveling carriage 3 so as to be movable in the longitudinal direction of the traveling carriage 3. A tool storage unit 18B having a tool changer 20B is attached to two wires 19B attached to a winding device (not shown) installed in the trolley 17B. In the rotatable tool changer 20B, a tool 21B used for work, for example, although not shown, a gripping device, a cutting machine, a squeezing machine, and a breaker are stored. These tools 21B are attached to the tip of the work arm 15 one by one.

  The crane unit 22 includes a traveling carriage 23, a first crane 25, a second crane 30, and a container moving device 36. The traveling carriage 23 is provided with guide rails 24A and 24B that extend in the longitudinal direction of the traveling carriage 23 and are arranged in parallel.

  The first crane 25 has a trolley 26 and hooks 27 and 29. The trolley 26 is attached to guide rails 24A and 24B (see FIG. 6) so as to be movable in the longitudinal direction of the traveling carriage 23. The hook 27 is attached to two wires 28 </ b> A attached to a winding device (not shown) installed on the trolley 26. The hook 29 is attached to two wires 28 </ b> B attached to another winding device (not shown) installed on the trolley 26.

  The second crane 30 has a trolley 31 and hooks 32 and 34. The trolley 31 is attached to the guide rails 24 </ b> A and 24 </ b> B so as to be movable in the longitudinal direction of the traveling carriage 23. The hook 32 is attached to one wire 33 attached to a winding device (not shown) installed on the trolley 31. The hook 34 is attached to one wire 35 attached to another winding device (not shown) installed in the trolley 31.

  The container moving device 36 includes a moving carriage 37 and a pantograph type lifting device 39. The lifting device 39 is installed on the support member 38, and the upper end of the lifting device 39 is attached to the support plate 40 on which the storage container 70 is placed. Two winding devices (not shown) are attached to the movable carriage 37, and two wires 41 suspended from the respective winding devices are attached to the support member 38. An opening 104 through which the lifting and lowering device 39 and the support plate 40 pass is formed in the movable carriage 37 (see FIG. 6).

  The nuclear power plant to which this embodiment is applied has four nuclear power plants 72A, 72B, 72C and 72D as shown in FIG. The nuclear power plants 72A, 72B, 72C and 72D include a reactor building 73 and a turbine building 74, respectively. Support members 2A and 2B are arranged on the side of the separate outer wall of each reactor building 73 and are installed on the ground. The upper ends of the support members 2 </ b> A and 2 </ b> B are located above the reactor building 73. A pair of guide rails 4 </ b> A are installed in parallel to the upper ends of the support members 2 </ b> A provided for each reactor building 73, and a pair of guide rails 4 </ b> B are parallel to the upper ends of the support members 2 </ b> B provided for each reactor building 73. Installed. The traveling carriage 3 of the work unit 2 and the traveling carriage 23 of the crane unit 22 are respectively installed on the guide rail 4A at the upper end of the support member 2A and the guide rail 4B at the upper end of the support member 2B provided for each reactor building 73. . The work unit 2 and the crane unit 22 are arranged in parallel above the respective reactor buildings 73 as shown in FIG. The traveling carriage 3 of the work unit 2 and the traveling carriage 23 of the crane unit 22 provided for each reactor building 73 move in the same direction along the guide rails 4A and 4B above the respective reactor buildings 73. The traveling trolleys 3 and 23 are arranged across the reactor buildings in the respective reactor buildings 73. A plurality of monitoring cameras 83 are provided on the traveling carriage 3, and a plurality of monitoring cameras 84 are provided on the traveling carriage 23.

  The transfer device 43 includes a transport carriage 42 and travel rails 44A, 44B and 45-53. The traveling rail 44A is provided with a plurality of turntables (rail switching devices) 54 provided with rails. The traveling rail 44B is provided with a plurality of turntables 55 provided with rails. The traveling rails 44A and 44B are arranged in parallel with each other along the reactor buildings 73 of the nuclear power plants 72A, 72B, 72C, and 72D. The traveling rails 44 </ b> A and 44 </ b> B are supported by a plurality of struts 66 (see FIG. 2) disposed along each reactor building 73, and are installed at the upper ends of the respective struts 66.

  The low-dose rate structural member storage building 59, the decontamination building 60, the high-dose rate structural member storage building 61, the fuel storage building 62, the maintenance building 63, and the water treatment building 65 are, for example, on a hill in the site of the nuclear power plant. Installed. The decontamination building 60, the high dose rate structural member storage building 61, the fuel storage building 62 and the maintenance building 63 are arranged in parallel, and the low dose rate structural member storage building 59 is arranged next to the decontamination building 60. A control chamber 64 in which the control device 64 </ b> A is installed is formed in the maintenance building 63. The low-dose-rate structural member storage building 59 and the decontamination building 60 are buildings that house plant structural members with a low dose rate, and the high-dose-rate structural member storage building 61 houses high-dose rate plant structural members other than each fuel. The fuel storage building 62 is a building that stores each fuel.

  The traveling rail 46 extends from the traveling rail 44 </ b> A toward the decontamination building 60. The traveling rail 47 is arranged in parallel with the traveling rail 46 and extends from the traveling rail 44 </ b> B toward the decontamination building 60. The end of the traveling rail 46 on the traveling rail 44 </ b> A side and the end of the traveling rail 47 on the traveling rail 44 </ b> B side are supported by the upper ends of the columns 66. In the decontamination building 60, the traveling rail 46 is connected to the traveling rail 47.

  The traveling rail 48 extends from the traveling rail 44 </ b> A toward the high dose rate structural member storage building 61. A traveling rail 49 is arranged in parallel with the traveling rail 48 and extends from the traveling rail 44 </ b> B toward the high dose rate structural member storage building 61. The end of the traveling rail 48 on the traveling rail 44 </ b> A side and the end of the traveling rail 49 on the traveling rail 44 </ b> B side are supported by the upper ends of the columns 66. In the high dose rate structural member storage building 61, the traveling rail 48 is connected to the traveling rail 49.

  The traveling rail 50 extends from the traveling rail 44 </ b> A toward the fuel storage building 62. The traveling rail 51 is disposed in parallel to the traveling rail 50 and extends from the traveling rail 44 </ b> B toward the fuel storage building 62. The end of the traveling rail 50 on the traveling rail 44 </ b> A side and the end of the traveling rail 51 on the traveling rail 44 </ b> B side are supported by the upper ends of the columns 66. In the fuel storage building 62, the traveling rail 50 is connected to the traveling rail 51.

  The traveling rail 52 extends from the traveling rail 44 </ b> A toward the maintenance building 63. The traveling rail 53 is arranged in parallel with the traveling rail 52 and extends from the traveling rail 44 </ b> B toward the maintenance building 63. The end of the travel rail 52 on the travel rail 44 </ b> A side and the end of the travel rail 53 on the travel rail 44 </ b> B side are supported by the upper ends of the columns 66. In the maintenance building 63, the traveling rail 52 is connected to the traveling rail 53.

  A plurality of turntables 54 provided with rails are arranged on the traveling rail 44A. These turntables 54 are disposed at the intersections of the traveling rails 46, 48, 50 and 52 and the traveling rail 44 </ b> A, respectively, and are installed at the upper ends of the columns 66. A plurality of turntables 55 provided with rails are arranged on the traveling rail 44B. These turntables 55 are disposed at the intersections of the traveling rails 46 to 53 and the traveling rail 44 </ b> B, respectively, and are installed at the upper ends of the columns 66.

  The transport carriage 42 moves from a certain reactor building 73 to a corresponding building, for example, the decontamination building 60 along the corresponding traveling rail. The traveling rails 44 </ b> A, 46, 48, 50, and 52 correspond to the decontamination building 60, the high dose rate structural member storage building 61, the fuel storage building 62, and the maintenance building 63 corresponding to the transport carriage 42 from each reactor building 73. It is a traveling rail that guides you to the building. The traveling rails 44B, 47, 49, 51, and 53 are traveling rails that, conversely, guide the carriage 42 from the corresponding building to the corresponding reactor building 73.

  The arrangement of the traveling rails 45A to 45D for moving the transport carriage 42 between the reactor building 73 of each of the nuclear power plants 72A, 72B, 72C and 72D and the traveling rails 44A and 44B will be described with reference to FIG. .

  A decontamination chamber 58 is provided outside the reactor building 73 for each reactor building 73 of each of the nuclear power plants 72A, 72B, 72C, and 72D (see FIG. 1). Temporary placement stands (parking areas) 56 are provided beside each decontamination chamber 58. Each temporary placement table 56 and each decontamination chamber 58 are installed on the column 57 in pairs. The traveling rail 45A connected to the temporary table 56 disposed near the reactor building 73 of the nuclear power plant 72A is in communication with the traveling rails 44A and 44B. The turntable 54A is disposed at the intersection of the traveling rail 45A and the traveling rail 44A, and the turntable 55A is disposed at the intersection of the traveling rail 45A and the traveling rail 44B. The traveling rail 45B connected to the temporary storage base 56 disposed near the reactor building 73 of the nuclear power plant 72B is connected to the traveling rails 44A and 44B. The turntable 54B is disposed at the intersection of the traveling rail 45B and the traveling rail 44A, and the turntable 55B is disposed at the intersection of the traveling rail 45B and the traveling rail 44B. The traveling rail 45C connected to the temporary table 56 disposed near the nuclear reactor building 73 of the nuclear power plant 72C is connected to the traveling rails 44A and 44B. The turntable 54C is disposed at the intersection of the traveling rail 45C and the traveling rail 44A, and the turntable 55C is disposed at the intersection of the traveling rail 45C and the traveling rail 44B. The traveling rail 45D connected to the temporary table 56 disposed near the reactor building 73 of the nuclear power plant 72D is communicated to the traveling rails 44A and 44B. The turntable 54D is disposed at the intersection of the traveling rail 45D and the traveling rail 44A, and the turntable 55D is disposed at the intersection of the traveling rail 45D and the traveling rail 44B.

  A decontamination water supply pipe 105 extends from the water treatment building 65 toward each decontamination chamber 58, and the decontamination water supply pipe 105 is connected to each decontamination chamber 58. A decontamination water return pipe 106 connected to each decontamination chamber 58 extends toward the water treatment building 65.

  The structure in each reactor building 73 of the nuclear power plants 72A, 72B, 72C and 72D to be decommissioned will be described. A reactor containment vessel 77 having a pressure suppression chamber 78 is installed in the reactor building 73. A reactor pressure vessel 75 having a core 76 loaded with a fuel assembly is installed in a reactor containment vessel 77. An operation floor 81 is formed in the reactor building 73 above the reactor containment vessel 77. An equipment temporary storage pool 79 and a fuel storage pool 80 are formed above the reactor containment vessel 77 and surrounded by the operation floor 81.

  A method for transporting the radioactive structural member according to the present embodiment in the decommissioning work using the radioactive structural member transporting apparatus 1 will be described below. In this embodiment, in each reactor building 73 of the nuclear power plants 72A, 72B, 72C and 72D, the decommissioning work such as dismantling of the plant structure members of the corresponding nuclear power plant is performed, and is carried out by the decommissioning work. The plant structural member is stored in the storage container 69 in the reactor building 73. The storage container 69 is made of a radiation shielding material. In the decommissioning operation, the plant structure stored in the storage container 69 and carried out of the reactor building 73 is radioactive waste. The storage container 69 that stores the plant structural member is placed on the transport carriage 42 and is transported to the decontamination building 60, the high-dose rate structural member storage building 61, or the fuel storage building 62 through the traveling rail after decontamination. .

  When carrying out the method for transporting the radioactive structural member according to the present embodiment, the work unit 2 and the crane unit 22 are installed in the reactor buildings 73 of the nuclear power plants 72A, 72B, 72C and 72D. The support member 2 </ b> A and the support member 2 </ b> B are installed outside the reactor building 73 near two opposing side walls of each reactor building 73. The reactor building 73 is located between the support member 2A and the support member 2B. The work unit 2 and the crane unit 22 lifted by the crawler crane are arranged across the reactor building 73, and a pair of guide rails 4A provided at the upper end of the support member 2A and a pair provided at the upper end of the support member 2B. Is movably installed on the guide rail 4B. The support column 57 is installed outside the reactor building 73, and the temporary table 56 and the decontamination chamber 58 are installed on the support column 57. A primary shielding tent 67 is installed on the ground so as to cover one reactor building 73 and the work unit 2 and the crane unit 22 arranged above the reactor building 73. A secondary shielding tent 68 covers the primary shielding tent 68, the column 57, the temporary table 56 and the decontamination chamber 58. A primary shielding tent 67 and a secondary shielding tent 68 are also provided for each reactor building 73. The traveling rails 44A, 44B, 45A to 45D, and 46 to 53 are respectively installed as described above. The dismantling work of the plant structural members in the reactor building 73 is performed in parallel in each reactor building 73 of the nuclear power plants 72A, 72B, 72C, and 72D.

  Since the decommissioning work in each reactor building 73 of each of the nuclear power plants 72A, 72B, 72C and 72D and the transfer work of the plant structural members to be carried out generated in the decommissioning work are the same, the nuclear power plant 72A is An example will be described.

  Information on the order of carrying out plant structural members in the reactor building 73 is stored in the memory of the control device 64 </ b> A in the control room 64. The control device 64A controls the movement of the traveling carriage 3 and the trolleys 6, 12, 17A, and 17B of the work unit 2, the work devices 5 and 11, and the tool storage devices 16A and 16B based on the information on the carry-out order. Operation control of each of the traveling carriage 23, trolleys 26, 31 and moving carriage 37 of the crane unit 22, operation control of each of the first crane 25, the second crane 30 and the container moving device 36, of the transport carriage 42. Movement control and switching control of the turntables 54 and 55 are performed. Unless otherwise indicated, the work performed by the work devices 5 and 11 of the work unit 2, the transport by the crane unit 22, and the transport by the transport carriage 42 are performed by automatic control by the control device 64 </ b> A.

  The dismantling of the plant structural members in the nuclear reactor building 73 is performed in the primary shielding tent 67 in a state where the nuclear reactor building 73 is covered with the primary shielding tent 67. It is assumed that the ceiling of the reactor building 73 of the nuclear power plant 72A is in a state where the concrete has disappeared and the steel frame is exposed. First, the steel frame is dismantled and removed. The traveling carriage 3 of the work unit 2 is moved along the guide rails 4A and 4B above the reactor building 73, and the trolleys 6 and 12 are further moved along the guide rail provided on the traveling carriage 3. It is moved in a direction orthogonal to the moving direction, and the work devices 5 and 11 are moved to a position where the ceiling is disassembled. The tool storage device 16A is moved close to the work device 5 by the trolley 17A, and the cutting machine is provided at the tip of the work arm 10 of the work device 5 in the tool storage unit 18A of the tool storage device 16A. Attach with 20A. The tool storage device 16B is moved close to the working device 11 by the trolley 17B, and the gripping device, for example, is present in the tool storage unit 18B of the tool storage device 16B at the distal end of the work arm 15 of the working device 11. Attach with 20B. The tool changers 20A and 20B can rotate.

  The work arm 10 is moved up and down by moving the support member 6 </ b> A up and down by winding or unwinding the two wires 7 with a winding device provided on the trolley 6. The work arm 15 is moved up and down by moving the support member 13 up and down by winding or unwinding the two wires 14 with a winding device provided on the trolley 12.

  The steel frame on the ceiling is gripped by a gripping device attached to the work arm 15, and the steel frame is cut by a cutting machine attached to the work arm 10. Such work is repeated to cut the steel frame on the ceiling, and the cut steel frame is gripped by a gripping device attached to the work arm 15, for example, a storage container placed on the operation floor 81 in the reactor building 73. 69. The dose rate measurement value obtained by measuring the dose rate of the steel frame stored in the storage container 69 by the dose rate meter 8 provided in the working device 7 is transmitted to the control device 64A. Further, the steel frame stored in the storage container 69 is photographed by the monitoring camera 83, and video information of the steel frame is transmitted from the monitoring camera 83 to the control device 64A. The control device 64A extracts the shape information of the plant structural member (for example, steel frame) stored in the storage container 69 from the video information, and stores the extracted shape information in the memory.

  The storage container 69 stores a cut steel frame having a dose rate (low dose rate) equal to or lower than a set dose rate (for example, 1 Sv / h). If there is a steel frame having a dose rate (high dose rate) exceeding the set dose rate, it is stored in another storage container 69 by the working device 11 holding the cut steel frame. Work on the work devices 7 and 11, transportation of the cut steel frame, and storage of the steel frame (plant structural member to be discharged) in the storage container 69 are provided in the monitoring camera 83 and the traveling carriage 23 provided in the traveling carriage 3. The video information photographed by the surveillance cameras 84 and output from the respective surveillance cameras is displayed on a monitor provided in the control room 64 and monitored by an operator. When one storage container 69 is filled with the cut steel frame, the lid is attached to the storage container 69 by the gripping device attached to the working device 11.

  For example, an identification number, which is an identification symbol (identification information) for identifying the storage container 69, is assigned to all the storage containers 69, and the identification number is attached to the side surface and the lid of the storage container 69. This identification number is photographed by the monitoring camera 83, and the video information of the identification number is transmitted to the control device 64A. The control device 64A associates the identification number of the storage container 69 with the dose rate and shape information of the plant structural member (for example, the steel frame of the ceiling) stored in the storage container 69 and stores them in the memory.

  The storage container 69 in which a plant structural member (for example, a steel frame on the ceiling) is stored and sealed with a lid is suspended from a crane of the crane unit 22, for example, a hook 29 of the first crane 25 according to the weight. The storage container 69 is suspended from the hook 29 by, for example, rewinding the wire 28B by driving a winding device provided in the trolley 26 to store the hook 29 and the plant structural member (for example, a steel frame on the ceiling). The container is lowered to the vicinity of the storage container 69 and is attached to the storage container 69 by using a gripping device attached to the work arm 15 of the work apparatus 11 while monitoring the video taken by the monitoring camera 83 (or 84) in the control room 63. This is done by hanging a handle (or wire) that is attached to the hook 29. A winding machine provided on the trolley 26 is rotated to wind the wire 28B, and the storage container 69 suspended from the hook 29 is lifted. The traveling carriage 23 moves on the guide rails 4 </ b> A and 4 </ b> B and moves the storage container 69 from the primary shielding tent 67 to the position of the decontamination chamber 58 in the secondary shielding tent 68. At this time, the crane unit 22 in which the storage container 69 is suspended is moved into the decontamination chamber 58 through an opening (not shown) provided in the primary shielding tent 67 to be opened and closed. Thereafter, the entire outer surface of the storage container 69 conveyed into the decontamination chamber 58 is decontaminated by, for example, a high-pressure jet cleaning device, which is a decontamination device provided in the decontamination chamber 58. The high pressure jet cleaning apparatus is supplied with decontamination water from the water treatment building 65 through the decontamination water supply pipe 105, and the decontamination water jet is transferred from the high pressure jet cleaning apparatus to the outer surface of the storage container for decontamination. It is jetted toward. The decontaminated water that has decontaminated the storage container 69 in the decontamination chamber 58 is returned to the water treatment building 65 through the decontamination water return pipe 106 and purified. The purified decontamination water is supplied again to the decontamination apparatus in the decontamination chamber 58 through the decontamination water supply pipe 105.

  After the decontamination, the storage container 69 is lifted by the first crane 25, moved to the transport carriage 42 waiting on the temporary placing table 56, and the hoisting machine of the first crane 25 is rotated to rotate the wire 28B. And the storage container 69 is placed on the transport carriage 42. The storage container 69 is removed from the hook 29 of the first crane 25. The storage container 69 is detached from the hook 29 by using a gripping device (not shown) attached to a work arm of a work device (not shown) provided in the temporary placement 56th place. This is done by removing the handle (or wire) of the storage container 69.

  A motor (not shown) provided on the transport carriage 42 is driven, and the transport carriage 42 on which the storage container 69 is placed moves from the temporary placement base 56 on the travel rail 45A toward the travel rail 44A. The transport cart 42 is a self-propelled transport vehicle. When the transport carriage 42 reaches the turntable 54A, the movement of the transport carriage 42 is stopped, and the turntable 54A is turned until the rail provided on the turntable is connected to the travel rail 44A. When the rotation of the turntable 54A is stopped, the transport carriage 42 moves on the travel rail 44A from the turntable 54A toward the turntable 54 located at the intersection of the travel rail 44A and the travel rail 46. A monitoring camera 107 is installed in the vicinity of each turntable 54 provided on the traveling rail 44A, and monitors that the transport carriage 42 has reached the turntable. That is, the storage camera 69 on the transport carriage 42 that has reached the turntable is photographed by the monitoring camera 107, and the photographed video information is transmitted to the control device 64A. Based on the video information, the control device 64A recognizes that the transport carriage 42 carrying the storage container 69 has reached the turntable 54A, and turns the turntable 54A by 90 ° as described above.

  The control device 64A recognizes the identification number of the storage container 69 based on the video information of the storage container 69 taken by the monitoring camera 107 when the transport carriage 42 arrives on the turntable 54A from the traveling rail 45A, and stores it in the memory. Based on the dose rate information corresponding to the stored identification number, the dose rate of the plant structural member stored in the storage container 69 is recognized. Then, the control device 64A displays the dose rate information (dose rate measured by the dose rate meter 8) corresponding to the recognized identification number and the shape information of the plant structural member (for example, steel frame) stored in the storage container 69. Based on this, a target location (decontamination building 60, high dose rate structural member storage building 61 or fuel storage building 62) for transporting the storage container 69 is determined. The shape information of the plant structural member (ceiling steel frame) stored in the storage container 69 is different from the shape information of the fuel assembly and the shape information of the fuel storage rack 82, and this plant structural member has a low dose rate. Therefore, the control device 64A determines that the plant structural member stored in the storage container 69 is a low-dose rate structural member, and determines that the target location for transporting the storage container 69 is the decontamination building 60. . Each of the fuel assembly and the fuel storage rack 82 (containing the spent fuel assembly) is a plant structure member containing nuclear fuel material, and the shape information of each of the fuel assembly and the fuel storage rack 82 is a plant structure containing nuclear fuel material. It is shape information of a member. For this reason, the shape information of the plant structural member (ceiling steel frame) stored in the storage container 69 is different from the shape information of the plant structural member containing the nuclear fuel material. The control device 64A determines the target location for transporting the storage container 69 when the storage container 69 in which the plant structural member (steel frame) is stored is sealed with a lid as described above. May be performed on the basis of the identification number of the storage container 69 stored in the above and the dose rate measurement value and shape information of the plant structural member (for example, the steel frame of the ceiling) stored in the storage container 69.

  The transport carriage 42 on which the storage container 69 is placed reaches the travel rail 44A on the travel rail 44A until it reaches the turntable 54 disposed at the intersection of the travel rail 44A and the travel rail 46 connected to the decontamination building 60. Other turntables 54 such as the provided turntable 54B are not turned by the control device 64A for the transport carriage 42. When the transport carriage 42 on which the storage container 69 is placed reaches the turntable 54 disposed at the intersection of the traveling rail 46 connected to the traveling rail 44 </ b> A and the decontamination building 60, the monitoring camera disposed in the vicinity of the turntable 54 The storage container 69 is photographed by 107, and the obtained video information is sent to the control device 64A. Based on the video information, the control device 64A recognizes that the transport carriage 42 on which the storage container 69 is placed has reached the turntable 54, and the plant structural member stored in the storage container 69 is low. When recognizing that it has a dose rate, the control device 64A turns the corresponding turntable 54 by 90 °. The turntable 54 makes it possible for the transport carriage 42 to travel on the travel rail 46, and the transport carriage 42 reaches the decontamination building 60 through the travel rail 46.

  The storage container 69 is lowered from the transport carriage 42 using a crane (not shown) provided in the decontamination building 60 in the decontamination building 60. A plant structural member in the storage container 69, for example, a steel frame, is decontaminated in the decontamination building 60 by using a decontamination device, and the radioactive material on the surface is removed. The decontaminated plant structural member has a dose rate measured by a dosimeter (not shown) in the decontamination building 60. Based on this dose rate, waste that does not need to be handled as radioactive material, and radioactive waste Are separated into low dose rate structural members that are treated as The low dose rate structural member is placed on a transport cart (not shown) that moves on the traveling rail 108 between the decontamination building 60 and the low dose rate structural member storage building 59, and the low dose rate structural member is transferred from the decontamination building 60 to the low dose rate structural member. It is conveyed to the member storage building 59. The low dose rate structural member is further finely discriminated into concrete and metal in the low dose rate structural member storage building 59 and stored. The plant structural member separated as waste that does not need to be handled as radioactive material in the decontamination building 60 is handled as general waste instead of radioactive waste.

  In the decontamination building 60, an empty storage container 69 is placed on the transport carriage 42 in which the storage container 69 in which the plant structural members are stored is lowered. The transport carriage 42 on which the empty storage container 69 is placed moves from the traveling rail 46 to the traveling rail 47 and further moves on the traveling rail 47 toward the traveling rail 44B. Based on the video information (including the identification number of the empty storage container 69) output from the monitoring camera 107 (not shown) disposed in the vicinity of the turntable 55 disposed at the intersection of the traveling rail 47 and the traveling rail 44B. When the control device 64A determines that the transport carriage 42 carrying the empty storage container 69 has reached the turntable 55 at the intersection of the travel rail 47 and the travel rail 44B, the control device 64A 55 is turned 90 °. The rail provided on the turntable 55 that has turned is connected to the traveling rail 44B, and the transport carriage 42 on the turntable 55 is transferred to the traveling rail 44B. The transport carriage 42 is moved toward the temporary placement table 56 in the primary shielding tent 67 that covers the reactor building 73 of any one of the nuclear power plants 72A, 72B, 72C, and 72D. The control device 64A determines, for example, as follows, to which temporary placement table 56 the transport carriage 42 on which the empty storage container 69 is placed is moved. Identification by the control device 64A of the transport carriage 42 to be returned to the temporary placement table 56 is performed by a control device from a monitoring camera 107 (not shown) installed in the vicinity of the turntable 55 arranged at the intersection of the travel rail 47 and the travel rail 44B. This is performed based on the identification number of the empty storage container 69 on the transport carriage 42 included in the video information transmitted to 64A.

  The control device 64 </ b> A stores information on the number of storage containers 69 that store the plant structural members, which are respectively stored in each reactor building 73. This number in each reactor building 73 is obtained by the control device 64A using video information output from the monitoring cameras 83 and 84 provided for each reactor building 73. The control device 64A moves toward the temporary storage table 56 provided for the nuclear power plant having the largest number of storage containers 69 storing the plant structural members, which are stored in the reactor building 73, for example. . At present, the number of storage containers 69 storing the plant structural members, which is accumulated in the reactor building 73 of the nuclear power plant 72A, is the largest. Therefore, the transport carriage 42 that has moved to the traveling rail 44B described above is moved toward the temporary placement table 56 provided for the nuclear power plant 72A.

  The fact that the transport carriage 42 carrying the empty storage container 69 has reached the turntable 55A located at the intersection of the traveling rail 44B and the traveling rail 45A is output from the monitoring camera 107 disposed in the vicinity of the turntable 55A. When the control device 64A determines based on the identification number of the empty storage container 69 included in the video information, the control device 64A turns the turntable 55A on which the transport carriage 42 is placed by 90 °. The rail provided on the turntable 55A is connected to the traveling rail 45A, and the turntable 54A is also connected to the traveling rail 45A. The transport carriage 42 on the turntable 55B moves on the turntable 54A and the traveling rail 45A, and reaches the temporary placement table 56 provided for the nuclear power plant 72A. A plurality of transport carriages 42 can be placed on the temporary placement table (parking area) 56.

  As described above, the storage container 69 containing the plant structural members is sequentially transported by the crane unit 22 and decontaminated in the decontamination chamber 58 from the reactor building 73 of the nuclear power plant 72A to the decontamination chamber 58. A storage container 69 storing the members is placed on the transport carriage 42 on the temporary storage table 56. Then, the storage container 69 storing the plant structural member is stored by the transport carriage 42 in accordance with the dose rate and shape information of the plant structural member in the storage container 69 (decontamination building 60, high dose rate structural member storage). It is sequentially transferred to the building 61 or the fuel storage building 62) through the traveling rails 45A and 44A.

  The empty storage container 69 mounted on the transport carriage 42 that has reached the temporary storage base 56 transports the storage container 69 storing the plant structural members to the temporary storage base 56, and the reactor building 73 of the nuclear power plant 72A. It is suspended by a crane (for example, the second crane 31) of the crane unit 22 returned to, and is transported into the reactor building 73.

  When the transport carriage 42 carrying the empty storage container 69 that moves on the traveling rail 44B is moved toward the temporary placement table 56 provided for the power generation plant 72B, the monitoring camera disposed in the vicinity of the turntable 55B. When the control device 64A recognizes that the transport carriage 42 is placed on the turntable 55B based on the video information 107 (not shown), the control device 64A turns the turntables 55B and 54B to turn these turns. Each rail of the table is connected to the traveling rail 45B. The transport carriage 42 on the turntable 55B is moved to the temporary placement table 56 provided for the power plant 72B through the traveling rail 45B. When the transport carriage 42 carrying the empty storage container 69 that moves on the traveling rail 44B is moved toward the temporary placement table 56 provided for the power plant 72C, the turntable 55A is similar to the turntable 55A. Rotate 55C and 54C. The transport carriage 42 on the turntable 55C is moved to the temporary placement table 56 provided for the power plant 72C through the traveling rail 45C. When the transport carriage 42 carrying the empty storage container 69 that moves on the traveling rail 44B is moved toward the temporary placement table 56 provided for the power plant 72D, the turntable 55A is similar to the turntable 55A. Rotate 55D and 54D. The transport carriage 42 on the turntable 55D is moved to the temporary placement table 56 provided for the power plant 72D through the traveling rail 45D.

  In the reactor building 73 of the nuclear power plant 72A, after the cutting of the steel frame on the ceiling by the working devices 5 and 11 and the storage in the storage container 69 are finished, the fuel that has been cut off and cut off from the fuel exchanger on the operation floor 81 Storage in the storage container 69 of the exchange is performed by the work devices 5 and 11. The shape information of the cut fuel changer is obtained by using video information obtained by photographing performed by the monitoring camera 83 when the cut fuel changer is stored in the storage container 69, as in the case of the steel frame. be able to. The storage container 69 storing the cut fuel changer is suspended and transferred by the crane of the crane unit 22, decontaminated in the decontamination chamber 58, and then placed on the transport carriage 42 on the temporary storage table 56. Since the cut fuel changer has a low dose rate equal to or lower than the set dose rate, and the shape information of the cut fuel changer is different from the shape information of the fuel assembly and the shape information of the fuel storage rack 82, the cut fuel changer The transport carriage 42 on which the storage container 69 storing therein is removed through the traveling rails 45A, 44A and 46 by turning control of the turntable by the control device 64A based on the information of the identification number attached to the storage container 69. Moved to dye building 60.

  After the crane unit 22 returns to the reactor building 73 after transporting the cut fuel changer, the fuel storage rack 82 in which the spent fuel assemblies (plant structural members) in the fuel storage pool 80 are stored is the crane unit 22. The first crane 25 is suspended by a hook 27 and stored in a storage container 70 placed in a fuel storage pool 80. The fuel storage rack 82 that stores the spent fuel assembly is also a kind of plant structural member. The storage container 70 is provided with a cooling device (for example, a fan that blows cooling air). When the fuel storage rack 82 is stored in the storage container 70, the dose rate of the fuel storage rack 82 is measured by the dose rate meter 8 provided in the working device 5, and the fuel storage rack 82 is photographed by the monitoring camera 83. The dose rate measurement value of the fuel storage rack 82 obtained by the measurement is transmitted to the control device 64A. Further, the control device 64 </ b> A acquires the shape information of the fuel storage rack 82 stored in the storage container 70 and the information of the identification number assigned to the storage container 70 from the video information obtained by the monitoring camera 83. The control device 64A associates the identification number of the storage container 70 with the dose rate of the stored fuel storage rack 82 and the shape information of the fuel storage rack 82, and stores them in the memory. Since the spent fuel assembly is accommodated in the fuel storage rack 82, the measured dose rate of the fuel storage rack 82 exceeds the set dose rate, and the shape information of the fuel storage rack 82 stored in the memory is naturally also included. It is the shape information of the fuel storage rack. Therefore, the measured value of the dose rate of the fuel storage rack 82 stored in the storage container 70 exceeds the set dose rate, and the shape information obtained from the video information of the fuel storage rack 82 includes the nuclear fuel material. Since it is the shape information of the member, the control device 64 </ b> A determines that the target location for transporting the storage container 70 storing the fuel storage rack 82 is the fuel storage building 62.

  The storage container 70 storing the fuel storage rack 82 is transported to the decontamination chamber 58 by moving the traveling carriage 23 while being suspended by the first crane 25, and after being decontaminated in the decontamination chamber 58, It is placed on the transport carriage 42 placed on the stage 56.

  The transport carriage 42 carrying the storage container 70 containing the fuel storage rack 82 moves toward the turntable 54A through the traveling rail 45A, and moves to the traveling rail 44A by turning the turntable 54A. A transport carriage 42 that passes through several turntables 54 on the way, moves on the traveling rail 44 </ b> A, and stores a storage container 69 containing the fuel storage rack 82 is located at the intersection of the traveling rail 44 </ b> A and the traveling rail 50. When the vehicle reaches the top of the turntable 54, a monitoring camera 107 (not shown) installed in the vicinity of the turntable 54 photographs the storage container 80 in which the fuel storage rack 82 is stored. Video information including the identification number of the storage container 80 output from the monitoring camera 107 is transmitted to the control device 64A. The control device 64A recognizes that the storage container 69 storing the fuel storage rack 82 is the storage container 69 to be transported to the fuel storage building 62 on the basis of the dose rate measurement value and the shape information corresponding to this identification number. The turntable 54, which is located at the intersection of the traveling rail 44A and the traveling rail 50, on which the transport carriage 42 on which the storage container 70 containing the storage rack 82 is placed is turned 90 °. As a result, the rail of the turntable 54 is connected to the traveling rail 50, and the transport carriage 42 can move on the traveling rail 48 toward the fuel storage building 62. When the transport carriage 42 reaches the fuel storage building 62, the storage container 70 storing the fuel storage rack 82 is lowered from the transport carriage 42, and the fuel storage rack 82 is taken out from the storage container 70. The fuel storage rack 82 is transported into a storage pool (not shown) filled with cooling water formed in the fuel storage building 62 and stored in the storage pool.

  As described above, the storage container 70 for storing the fuel storage rack 82 is provided with a cooling device. While the storage container 70 storing the fuel storage rack 82 is being transported by the crane unit 22 and the transport carriage 42, The flow of cooling air generated by the rotation of the fan, which is a cooling device, is applied to the outer surface of the storage container 70 in which the fuel storage rack 82 is stored and filled with cooling water, and the storage container 70 and the internal cooling water are cooled. The As a result, the spent fuel assembly in the storage container 70 is cooled. The storage container 70 is a storage container for transporting a fuel assembly that needs to be cooled. Incidentally, the storage container 69 is a storage container for transporting a plant structural member that does not require cooling because no cooling device is installed.

  After the storage container 70 storing the fuel storage rack 82 is lowered in the fuel storage building 62, the empty storage container 70 is placed on the transport carriage 42. The transport carriage 42 passes through the travel rail 51 and reaches the turntable 55 located at the intersection of the travel rail 51 and the travel rail 44B. Similar to when the traveling carriage 42 reaches the intersection of the traveling rail 47 and the traveling rail 44B through the traveling rail 47, the control device 64A turns the turntable 55 positioned at the intersection of the traveling rail 51 and the traveling rail 44B by 90 °. The rail of the turntable 55 is connected to the traveling rail 44B. The transport carriage 42 on which the empty storage container 70 is placed on the turntable 55 is moved to the temporary placement table 56 provided for the nuclear power plant 72A through the traveling rails 44B and 45A. Similarly to the empty storage container 69, the empty storage container 70 is moved to the reactor building 73 of each of the nuclear power plants 72B, 72C, 72D.

  Until all the fuel storage racks 82 in the fuel storage pool 80 are used up, the storage container 69 containing the fuel storage rack 82 is continuously carried out to the fuel storage building 62 described above.

  After transporting the fuel storage rack 82, the lid of the reactor containment vessel 77 is removed. The removal of the lid is performed by removing a bolt that attaches the lid to the reactor containment vessel 77 with a bolt wrench attached to the work arm 10 of the working device 5. The lid of the reactor containment vessel 77 is suspended from the hook 27 of the first crane of the crane unit 22 and transferred onto the operation floor 81 in the same manner as the containment vessel 69 containing the steel frame on the ceiling. On the operation floor 81, it is cut by a bolt wrench attached to the work arm 10 of the work device 5, and a cut piece of the lid of the reactor containment vessel 77 is stored by a gripping device attached to the work arm 15 of the work device 11. Housed in a container 69.

  Similar to the plant structural member described above, the image signal of the cut piece of the lid and the measured value of the dose rate are transmitted to the control device 64A. The control device 64A uses the identification number information, the shape information of the cut piece, and the dose rate measurement value of the storage container 69 for storing the cut piece obtained from the video signal as the identification number information. And corresponding dose rate measurements are stored in memory. The storage container 69 storing the lid is suspended and transported by the crane, and is decontaminated in the decontamination chamber 58 and placed on the transport carriage 42, similarly to the storage container 69 storing the steel frame. Since the dose rate measurement value of the lid of the reactor containment vessel is equal to or lower than the set dose rate and the shape information of the lid is different from the shape information of the fuel assembly and the fuel storage rack 82, the control device 64A carries the lid. Determine where the destination is. As a result, the transport carriage 42 on which the storage container 69 storing the lid of the reactor containment vessel 77 is moved to the decontamination building 60 through the traveling rails 45A, 44A and 46. In the decontamination building 60, the storage container 69 storing the lid is lowered from the transport carriage 42, and an empty storage container 69 is placed on the transport carriage 42. As described above, the transport carriage 42 carrying the empty storage container 69 is moved to the temporary placement table 56 of the nuclear power plant determined by the control device 64A.

  The lid of the reactor containment vessel 77 may be lifted and carried out by the crawler crane 109 (see FIG. 5) without being cut. A suspension balance (not shown) attached to the lid of the reactor containment vessel 77 is suspended from the crawler crane 109, and the secondary balance is passed through openings described later provided in the primary shielding tent 67 and the secondary shielding tent 68, respectively. It is carried out of the shielding tent 68. The suspension balance is attached to the lid of the reactor containment vessel 77 and is suspended from the crawler crane 109 of the suspension balance by the grip attached to the work arm 15 of the work device 11 in the same manner as the storage vessel 69 containing the steel frame. This is done using a device.

  After the lid of the reactor containment vessel 77 is removed, the lid 86 of the reactor pressure vessel 75 is removed. The lid 86 is removed by removing a plurality of bolts that fasten the lid 86 and the reactor pressure vessel 75 with a bolt wrench attached to the work arm 10. The lid 86 removed from the reactor pressure vessel 75 is suspended from the hook 27 of the first crane using a gripping device attached to the work arm 15 of the work device 11 and placed in the equipment temporary storage pool 79. It is stored in the storage container 69. The reactor well formed above the equipment temporary storage pool 79 and the reactor pressure vessel 75 is filled with cooling water 85. A part of the storage container 69 storing the lid 86 is present in the cooling water 79 in the equipment temporary storage pool 79. The dose rate of the removed lid 86 is measured by the dose rate meter 8, and the measured value is transmitted to the control device 64A. The video information of the lid 86 and the video information of the storage container 69 taken by the monitoring camera 84 when the storage container 69 of the lid 86 is stored in the storage container 69 are also transmitted to the control device 64A. Since the measured dose rate of the lid 86 exceeds the set dose rate, the control device 64A determines that the lid 86 is a high dose rate structural member with a high dose rate. The dose rate measurement value and shape information of the lid 86 are stored in the memory of the control device 64A in association with the identification number of the storage container 69 that houses the lid 86. Based on the dose rate measurement value and shape information of the lid 86, the control device 64 </ b> A determines that the target location for transporting the storage container 69 containing the lid 86 is the high dose rate structural member storage building 61. The shape information of the lid 86 is different from the shape information of the fuel assembly and the fuel storage rack 82.

  The storage container 69 storing the lid 86 is lifted by the hook 27 of the first crane 25 of the crane unit 22, and is transported to the position of the decontamination chamber 58 in the secondary shielding tent 68 by traveling of the traveling carriage 23. The outer surface is decontaminated in the dyeing chamber 58. The decontaminated storage container 69 is placed on the transport carriage 42 placed on the temporary placement table 56. Thereafter, the storage container 69 is removed from the hook 27 of the first crane 25.

  The transport carriage 42 on which the storage container 69 storing the lid 86 is moved moves toward the turntable 54A through the traveling rail 45A, and moves to the traveling rail 44A by turning of the turntable 54A. A turntable 42 that passes through several turntables 54 on the way, moves on the traveling rail 44 </ b> A, and carries a storage container 69 containing a lid 86 is positioned at the intersection of the traveling rail 44 </ b> A and the traveling rail 48. When the monitor camera 107 installed near the turntable 54 takes a picture of the storage container 69 storing the lid 86, the identification number of the storage container 69 output from the monitor camera 107 is displayed. The included video information is transmitted to the control device 64A. Based on the dose rate measurement value and shape information corresponding to this identification number, the control device 64A recognizes that the storage container 69 storing the lid 86 is the storage container 69 to be transported to the high dose rate structural member storage building 61. The turntable 54, which is located at the intersection of the traveling rail 44A and the traveling rail 48, on which the transport carriage 42 on which the storage container 69 containing the lid 86 is placed is turned 90 °. As a result, the rail of the turntable 54 is connected to the traveling rail 48, and the transport carriage 42 can move on the traveling rail 48 toward the high dose rate structural member storage building 61. When the transport carriage 42 reaches the high dose rate structural member storage building 61, the storage container 69 storing the lid 86 is lowered from the transport cart 42 and stored in the high dose rate structural member storage building 61.

  Instead, in the high dose rate structural member storage building 61, an empty storage container 69 is placed on the transport carriage 42, and the transport carriage 42 moves on the travel rail 49 toward the travel rail 44B. Based on the video information (including the identification number of the empty storage container 69) output from the monitoring camera 107 (not shown) disposed in the vicinity of the turntable 55 disposed at the intersection of the traveling rail 47 and the traveling rail 44B. When the control device 64A determines that the transport carriage 42 carrying the empty storage container 69 has reached the turntable 55 at the intersection of the travel rail 47 and the travel rail 44B, the control device 64A 55 is turned 90 °. The rail provided on the turntable 55 that has turned is connected to the travel rail 44B, and the transport carriage 42 on which the empty storage container 69 is placed moves on the turntable 55 toward the travel rail 44B.

  As described above, the control device 64A determines the destination of the transport carriage 42 on which the empty storage container 69 is placed. Here, it is assumed that the determined destination is the temporary storage table 56 provided corresponding to the nuclear power plant 72A. The transport carriage 42 on which the empty storage container 69 is placed moves to the temporary placement table 56 that is the destination through the traveling rails 44B and 45A. As described above, the storage container 69 placed on the transport carriage 42 is suspended by the crane of the crane unit 22 returned to the upper side of the reactor building 73 of the nuclear power plant 72A and transferred into the reactor building 73. The

  After the transport of the lid 86 is completed, the steam dryer and the steam separator in the reactor pressure vessel 75 are sequentially removed and separately placed in the equipment temporary storage pool 79 using the first crane 25 of the crane unit 22. In the storage container 69. The measured dose rates of the steam dryer and steam separator measured by the dose rate meter 8 exceed the set dose rate, and both the steam dryer and steam separator are high dose rate structural members. Each shape information is different from each shape information of the fuel assembly and the fuel storage rack 82. For this reason, the storage container 69 storing the steam dryer and the storage container 69 storing the steam / water separator use the crane unit 22 and the transport carriage 42 in the same manner as the storage container 69 storing the lid 86. It is conveyed to the structural member storage building 61. A plurality of jet pumps arranged and installed between the reactor pressure vessel 75 and the core shroud arranged in the reactor pressure vessel 75 are removed by using the work devices 5 and 11, and are placed in the temporary equipment pool 79. It is stored in the storage container 69 that is placed. Since the jet pump is a high dose rate structural member and its shape information is different from the shape information of the fuel assembly and the fuel storage rack 82, the storage container 69 storing the jet pump is also the storage container storing the lid 86. As in the case of 69, the high dose rate structural member storage building 61 is transported using the crane unit 22 and the transport carriage 42.

  A plurality of fuel assemblies (plant structural members) existing in the core in the reactor pressure vessel 75 are stored in a storage container 70 in which a cooling device is installed, like the fuel storage rack 82. The measured value of the dose rate of the fuel assembly exceeds the set dose rate, and the shape information of the fuel assembly is the shape information of the fuel assembly. Therefore, the control device 64A has a storage container in which the fuel assembly is stored. 70 determines that the fuel storage building 62 should be transported. The storage container 70 storing the fuel assembly is transported to the fuel storage building 62 in the same manner as the transport of the fuel storage rack 82 storing the fuel assembly described above.

  The high-dose rate structural members such as the upper lattice plate, the core shroud, the core support plate, and the control rod guide tube in the reactor pressure vessel 75 are removed by the working devices 5 and 11 (if necessary) And are sequentially stored in a plurality of storage containers 69 placed in the equipment temporary storage pool 79. These storage containers 69 storing the dismantled reactor internals are stored in the high dose rate structural member storage building 61 using the crane unit 22 and the transport carriage 42 in the same manner as the storage container 69 storing the lid 86 described above. Be transported.

  Pipes connected to the reactor pressure vessel 75 (recirculation system pipes and reactor purification system pipes, etc.) are cut by a cutting device attached to the work arm 10 of the work device 5, and the cut piping is used to grasp the device. It is stored in a plurality of storage containers 69 using the attached working device 11. Since these cut pipes are high dose rate structural members, the storage container 69 storing the cut pipes is transferred to the high dose rate structural member storage building 61 as described above.

  Next, the reactor pressure vessel 75 is unloaded. The reactor pressure vessel 75 is cut into an upper part, an intermediate part, and a lower part in the axial direction by a cutting device attached to the work arm 10 of the work device 5. The upper, middle and lower parts of the reactor pressure vessel 75 cut into three parts are separately stored in three storage containers 69 placed in the equipment temporary storage pool 79. The measured dose rate values of the upper, middle and lower portions of the reactor pressure vessel 75 measured by the dose rate meter 8 exceed the set dose rate. Each shape information obtained from the video information of the upper part and the intermediate part of the reactor pressure vessel 75 is different from each shape information of the fuel assembly and the fuel storage rack 82. For this reason, the control device 64 </ b> A determines that the storage containers 69 that separately store the upper part and the intermediate part of the reactor pressure vessel 75 are transported to the high dose rate structural member storage building 61. Based on this determination, the storage containers 69 that separately store the upper and intermediate portions of the reactor pressure vessel 75 are transferred to the high dose rate structural member storage building 61 using the transfer carriage 42 and the like. At the bottom of the lower part of the reactor pressure vessel 75, there is a possibility that the nuclear fuel material that has melted and dropped in the reactor core is solidified. The lower part of the reactor pressure vessel 75 where the nuclear fuel material is solidified at the bottom is a plant structural member containing the nuclear fuel material. The control device 64A indicates that the dose rate of the lower portion of the reactor pressure vessel 75 exceeds the set dose rate, and the shape information of the lower portion of the reactor pressure vessel 75 indicates the shape of the lower portion of the reactor pressure vessel 75 (nuclear fuel It is determined that the lower part of the reactor pressure vessel 75 is transported to the fuel storage building 62 at the lower part of the reactor pressure vessel 75. Based on this determination, the storage container 69 storing the lower part of the reactor pressure vessel 75 is transferred to the fuel storage building 62 using the transfer carriage 42 and the like.

  After that, the concrete of the reactor building 73, the equipment and piping installed in the reactor building 73, and the reactor containment vessel 77 are cut or crushed by using the working devices 5 and 11, and a plurality of storage containers are sequentially provided. 69. Each storage container 69 is transported to the decontamination building 60 or the high dose rate structural member storage building 61 determined based on the dose rate measurement value and shape information of the plant structural member stored inside. The low dose rate structural member transported from the decontamination building 60 to the low dose rate structural member storage building 59 after decontamination is divided into a low dose rate structural member that is less than or equal to the allowable dose rate and a low dose rate structural member that exceeds the allowable dose rate. The low dose rate structural members that are discriminated and are below the allowable dose rate and the low dose rate structural members that exceed the allowable dose rate are classified into metal and concrete, respectively.

  For example, it is assumed that the work arm 10 of the work device 5 is broken and cannot move. The control device 64A monitors the operating state of the working device and the like provided in the work unit 2 and the crane and the like provided in the crane unit 22, and detects an abnormal state of the work arm 10 (non-operation of the work arm 10). In such a case, the work device 5 that is in an abnormal state is removed from the work unit 2 using the work device 11 that is another normal work device under the control of the control device 64A. That is, the work device 5 is grasped by the gripping device attached to the work arm 15 of the work device 11, removed from the work unit 2, and stored in the storage container 69. The control device 64 </ b> A recognizes the identification number of the storage device 69 storing the failed working device 5 from the video information of the storage container 69.

  The storage device 69 storing the work device 5 is transported to the decontamination chamber 58 by the crane unit 22 and decontaminated, and then placed on the transport carriage 42 in the temporary storage table 56. The transport carriage 42 moves on the traveling rails 45 </ b> A and 44 </ b> A and reaches the turntable 54 located at the intersection of the traveling rail 44 </ b> A and the traveling rail 52. The control device 64A determines that the identification number of the storage container 69 obtained based on the video information of the storage device 69 photographed by the monitoring camera 107 (not shown) installed in the vicinity of the turntable 54 is the work device. 5 matches the identification number of the storage container 69 storing 5, it is determined that this storage container 69 is a storage container 69 to be transported to the maintenance building 63. Then, the control device 64 </ b> A turns the turntable 54 positioned at the intersection of the traveling rail 44 </ b> A and the traveling rail 52 by 90 ° to connect the rail of this turntable to the traveling rail 52. The transport carriage 42 on which the storage container 69 storing the work device 5 is moved moves on the traveling rail 52 to the maintenance building 63. In the maintenance building 63, the failed working device 5 is taken out of the storage container 69, and the worker checks the working device 5 to confirm the failed part. The failed working arm 10 is replaced with a new working arm 10 to restore the working device 5 to a normal state.

  The repaired work device 5 is stored in the storage container 69 on the transport carriage 42. The transport carriage 42 moves on the traveling rail 53 and reaches the position of the turntable 55 located at the intersection of the traveling rail 53 and the traveling rail 44B. Under the control of the control device 64A, the turntable 55 is turned, the rail of the turntable 55 is connected to the travel rail 44B, and the transport carriage 42 travels on the travel rail 44B. When the transport carriage 42 arrives on the turntable 55A, the turntables 55A and 54A turn to connect the rails to the traveling rail 45A, and the transport carriage 42 on which the storage container 69 containing the repaired work device 5 is placed. However, the vehicle travels on the traveling rail 45 </ b> A and reaches the temporary placement table 56. The storage container 69 is transported to the reactor building 73 suspended from the crane of the crane unit 22.

  In the reactor building 73, the repaired work device 5 in the storage container 69 is taken out from the storage container 69 using the gripping device of the work device 11 and attached to the work unit 2. As a result, the work device 5 can be used for the work of the reactor building 73.

  In the maintenance chamber 63, the transport carriage 42 is also maintained.

  A storage container 69 or 70 that stores the disassembled plant structural member using the traveling rail and the transport carriage 42 due to an increase in the number of transport carriages 42 moving on the traveling rail or damage to the traveling rail. When it becomes difficult to transport the container, the container 69 or 70 containing the plant structural member disassembled using the container moving device 36 is carried out of the secondary shielding tent 68 through the primary shielding tent 67 and the secondary shielding tent 68. To do. The conveyance of the storage container 69 using the container moving device 36 will be described.

  A plant structural member (for example, a core shroud) disassembled by cutting or the like using the work devices 5 and 11 in the reactor building 73 is gripped by a gripping device attached to the work arm 15 of the work device 11 and lifted and lowered 39 Is placed on a support plate 40 provided at the upper end of the plate. When the storage container 69 is placed on the support plate 40, the lifting and lowering device 39 is driven by driving the two winding devices provided on the movable carriage 37 and rewinding the wire 41 wound around each winding device. The support member 38 attached with is lowered to a certain height. By driving the elevating device 39, the support plate 40 is lowered to a position where it can be lowered most by the elevating device 39. In this state, the storage container 69 that stores the disassembled plant structural member is placed on the support plate 40 by the work device 11. The wire 41 is wound up by the winding device described above, and the storage container 69 is raised to the highest position possible by winding the wire 41. Thereafter, the support plate 40 is raised by the lifting device 39. The raised storage container 69 is raised to a position above the primary shielding tent 67 through an opening (not shown) formed in the ceiling of the primary shielding tent 67. The opening formed in the ceiling of the primary shielding tent 67 is sealed by an open / close door (not shown) except when the storage container 69 passes. The storage container 69 that has reached above the primary shielding tent 67 is lifted by the crawler crane 109 and is carried out of the secondary shielding tent 68 through an opening formed in the secondary shielding tent 68. Similarly to the storage container 69 mounted on the transport carriage 42 moved along the traveling rail, the storage container 69 storing the plant structural member other than the fuel assembly is the dose rate of the stored plant structural member. It is transported by a crawler crane or the like to one of the decontamination building 60 and the high dose rate structural member storage building 61 determined based on the measurement value and the shape information. The opening formed in the secondary shielding tent 68 is also sealed by the open / close door except when the storage container 69 passes. The same operation is performed when the storage container 70 storing the fuel assembly is taken out above the secondary shielding tent 68.

  When the measured dose rate of the plant structural member stored in the storage container 69 is less than the set dose rate and the shape information is not the shape of the fuel assembly and the fuel storage rack 82, the storage container 69 storing the plant structural member is removed. It is conveyed to the dyeing building 60. When the measured dose rate of the plant structural member exceeds the set dose rate and the shape information of the plant structural member is not the shape of each of the fuel assembly and the fuel storage rack 82, the storage container 69 that stores the plant structural member is: It is transferred to the high dose rate structural member storage building 61. When the measured dose rate of the plant structural member exceeds the set dose rate and the shape information of the plant structural member is the shape of the fuel assembly or the fuel storage rack 82, the storage container 70 that stores the plant structural member is: It is transported to the fuel storage building 62. Such conveyance of the plant structural member is also applied to the conveyance of the plant structural member stored in the storage containers 69 and 70 in the respective reactor buildings 73 of the nuclear power plants 72B, 72C, and 72D.

  The storage container storing the plant structural member in the reactor building 73 of the nuclear power plant 72B is decontaminated in the decontamination chamber 58, and then placed on the transport carriage 42 and moves to the turntable 54B through the traveling rail 45B. To do. A monitoring camera 107 (not shown) installed in the vicinity of the turntable 54B photographs the transport carriage 42 that has reached the turntable 54B and the storage container placed on the transport carriage 42, and the obtained video information (storage) (Including images of the respective identification numbers of the containers) are transmitted to the control device 64A. The control device 64A turns the turntable 54B, and the rail of the turntable 54B is connected to the traveling rail 44A. The transport carriage 42 carrying the storage container storing the plant structural member moves to the traveling rail 44A and is determined as described above based on the dose rate measurement value and the shape information of the plant structural member stored in the storage container. The decontamination building 60, the high dose rate structural member storage building 61, and the fuel storage building 62 are transported to any one of the buildings.

  The storage container storing the plant structural member in the reactor building 73 of the nuclear power plant 72C is decontaminated in the decontamination chamber 58, and then placed on the transport carriage 42 and moves to the turntable 54C through the traveling rail 45C. To do. A monitoring camera 107 (not shown) installed in the vicinity of the turntable 54C images the transport carriage 42 that has reached the turntable 54C and the storage container placed on the transport carriage 42, and obtains image information (storage). (Including the image of the container identification number) is transmitted to the control device 64A. The control device 64A turns the turntable 54C, and the rail of the turntable 54C is connected to the traveling rail 44A. The transport carriage 42 carrying the storage container storing the plant structural member moves to the traveling rail 44A and is determined as described above based on the dose rate measurement value and the shape information of the plant structural member stored in the storage container. The decontamination building 60, the high dose rate structural member storage building 61, and the fuel storage building 62 are transported to any one of the buildings.

  The storage container storing the plant structural member in the reactor building 73 of the nuclear power plant 72D is decontaminated in the decontamination chamber 58, and then placed on the transport carriage 42 and moves to the turntable 54D through the traveling rail 45D. To do. A surveillance camera 107 (not shown) installed in the vicinity of the turntable 54D images the transport carriage 42 that has reached the turntable 54D and the storage container placed on the transport carriage 42, and obtains image information (storage). (Including the image of the container identification number) is transmitted to the control device 64A. The control device 64A turns the turntable 54D, and the rail of the turntable 54D is connected to the traveling rail 44A. As described above, the transport carriage 42 carrying the storage container storing the plant structural member moves to the traveling rail 44A, and based on the dose rate measurement value and the shape information of the plant structural member stored in the storage container 69, as described above. The determined decontamination building 60, the high dose rate structural member storage building 61, and the fuel storage building 62 are transported to one of the buildings.

  In this embodiment, the plant structure member is stored based on the measured dose rate and shape information of the plant structure member stored in the storage container to be transported, and the identification number of the storage container storing the plant structure member. Since the target location (for example, the decontamination building 60, the high dose rate structural member storage building 61, or the fuel storage building 62) of the storage container is determined, each of the plurality of storage containers storing the plant structural member is efficiently stored. It can be transported to a target location for the storage container. For this reason, the time required for decommissioning work can be shortened. In addition, since the target location for transporting the storage container is determined based on the measured dose rate and shape information of the plant structural member stored in the storage container, and the identification number of the storage container, The target location can be determined with high accuracy.

  In the present embodiment, in the decommissioning work, the support members 2A and 2B are installed outside the opposing side walls of the reactor building 73, and the work unit 2 and the crane unit 22 are arranged across the reactor building 73. The support members 2A and 2B are movably installed on the guide rails provided at the upper ends of the support members 2A and 2B. For this reason, the storage unit storing the plant structural member can be easily transported to the decontamination chamber 58 by the crane unit 22 that can travel above the reactor building 73. Moreover, each operation | work of cutting | disconnecting the plant structural member in the reactor building 73, and storing in the storage container of the plant structural member by the working devices 5 and 11 provided in the work unit 2 that can run above the reactor building 73 is performed. Can be performed smoothly.

  Since the work unit 2 and the crane unit 22 are provided, and these can travel separately on the guide rails 4A and 4B, the crane is operated while cutting the plant structural member by using the work devices 5 and 11 of the work unit 2. The unit 22 can transport the storage container storing the plant structural member. For this reason, the time required for decommissioning work can be further shortened.

  Since the storage container storing the plant structural member whose outer surface has been decontaminated by the decontamination chamber 58 is transferred to the corresponding building by the transport carriage 42, the radioactive material adhered to the outer surface of the storage container in the reactor building 73 However, it is possible to prevent the storage container from being scattered to the outside environment during transportation.

In the present embodiment, the plant structural members are stored in the storage containers in the reactor buildings 73 of a plurality of nuclear power plants (for example, four nuclear power plants 72A to 72D) in one nuclear power plant. It is possible to smoothly perform the decommissioning work of the nuclear power plant.
In particular, the support members 2A and 2B are installed for each reactor building 73, and the work unit 2 and the crane unit 22 are arranged across the reactor building 73 and provided at the upper ends of the support members 2A and 2B. Since each guide rail is movably installed, decommissioning operations for a plurality of nuclear power plants can be performed in parallel. For this reason, it is possible to efficiently perform decommissioning operations for a plurality of nuclear power plants, and to complete these decommissioning operations in a short time.

  In the present embodiment, a first traveling rail and a second traveling rail are provided as traveling rails on which the transport carriage 42 moves. The first traveling rail includes traveling rails 44A, 46, 48, and 50, and a transport carriage 42 on which a storage container storing a plant structural member is placed is transported from the reactor building 73 side to a target place ( It is a running rail used for moving to the decontamination building 60, the high dose rate structural member storage building 61 or the fuel storage building 62). The traveling rails 46, 48 and 50 are branch rails of the traveling rail 44A. The second traveling rail includes traveling rails 44B, 47, 49, and 51. The transport carriage 42 in which the storage container storing the plant structural member is lowered is moved to a target place (decontamination building 60, high It is a traveling rail used for moving from the dose rate structural member storage building 61 or the fuel storage building 62) to the reactor building 73 side. The traveling rails 47, 49 and 51 are branch rails of the traveling rail 44B.

  In the present embodiment, as described above, the first traveling rail for moving the transport carriage 42 on which the storage container storing the plant structural member is placed from the reactor building 73 side to the target location for transporting the storage container. And the second traveling rail for moving the transport carriage 42 in which the storage container storing the plant structural member is lowered from the target location for transporting the storage container to the reactor building 73 side is installed. The transport carriage 42 on which the storage container storing the structural member is placed can be smoothly moved from the reactor building 73 side to the target location for transporting the storage container, and a large amount of storage storing the plant structural member The container can be transported to the target location in a short time.

  Each turntable 54 provided on the traveling rail 44A is a first rail switching device, and each turntable 55 provided on the traveling rail 44B is a second rail switching device. Switching control (turning control) of each of the turntables 54 and 55 for changing the traveling rail on which the transport carriage 42 moves is performed on each turntable output from the monitoring camera 107 provided in the vicinity of the corresponding turntable. Since it is based on the video signal of the transporting carriage 42 or the transporting carriage 42 that has arrived and the storage container mounted on the transporting carriage 42, the switching control of each of the turntables 54 and 55 can be reliably performed, The stagnation of the movement of the carriage 42 or the conveyance of the storage container is eliminated.

  After the storage container storing the plant structural member is unloaded from the transport carriage 42 at a target location for transporting the storage container storing the plant structural member, the transport cart 42 newly stores the storage container storing the plant structural member. In order to place it, it is returned to the reactor building 73 side, that is, the temporary placing table 56. When the storage container storing the plant structural member is transported from the reactor building 73 to the target location for transporting the storage container, the storage container storing the plant structural member is insufficient in the reactor building 73. It is necessary to transport the storage container into the reactor building 73. In this embodiment, an empty storage container is placed on a transport carriage 42 where the storage container storing the plant structural member is lowered at a place where the storage container storing the plant structural member is transported. It has moved to the building side. As described above, since the empty storage container is transferred to the reactor building 73 side using the transfer carriage 42 that needs to be returned to the reactor building 73 side, the empty storage container to the reactor building 73 is transferred. There is no need to provide a new conveying means. Further, the energy required to transport the empty storage container to the reactor building 73 side can use the energy consumed by driving the transport carriage 42 returned to the reactor building 73 side.

  In addition, transportation of an empty storage container from the temporary storage stand (parking area of the transfer carriage 42) 56 outside the reactor building 73 where the returned transfer carriage 42 is placed into the reactor building 73, The crane unit 22 is used for transporting the storage container storing the plant structural member from the reactor building 73 to the temporary storage table 56 and is located above the temporary storage table 56. When returning to above 73, the empty storage container is transferred into the reactor building 73. For this reason, since it is not necessary to move the crane unit 22 only to transport the empty storage container into the reactor building 73, the transport of the empty storage container into the reactor building 73 can be performed by transferring the plant structural members. There is no obstacle to the transport of the stored storage container from the reactor building 73 to the position of the temporary table 56. While transporting the empty storage container into the reactor building 73, the storage container storing the plant structural member can be efficiently transported to the outside of the reactor building 73.

  In the present embodiment, the positions of the intersections of the traveling rails 45A to 45D and the traveling rail 44A are more in the same direction than the positions of the intersections of the traveling rails 46, 48 and 50 and the traveling rail 44A. Since it is arranged at a distant position, the plant structural member from any reactor building 73 of the nuclear power plants 72A to 72D to any one of the decontamination building 60, the high dose rate structural member storage building 61, and the fuel storage building 62 Are transported on the travel rail 44A by the transport carriage 42, so that the transport carriage 42 loaded with the storage containers containing the plant structural members transported from the respective nuclear power plants is moved on the travel rail 44A. It can be moved in one direction. For this reason, the conveyance efficiency of each storage container which accommodated the plant structural member conveyed from the nuclear power plant improves.

  A method for transporting a radioactive structural member according to embodiment 2, which is another embodiment of the present invention, will be described with reference to FIG.

  The radioactive structural member transport device used in the method for transporting the radioactive structural member of the present embodiment has a configuration in which the container moving device 36 is replaced with the container moving device 36A in the radioactive structural member transport device 1 used in the first embodiment. Yes. The other structure of the radioactive structure member conveying apparatus used in the method for conveying the radioactive structure member of the present embodiment is the same as that of the radioactive structure member conveying apparatus 1.

  The container moving device 36 </ b> A includes a moving carriage 37 and a support plate 87. The support plate 87 is suspended from the wires 41 wound around the two winding devices provided on the movable carriage 37. By installing the container moving device 36 </ b> A, the crane unit 22 includes a crane device 88 having a hook 86.

  In the method for transporting the radioactive structural member according to the present embodiment, as in the first embodiment, the support member 2A and the guide rail 4B each having the guide rail 4A attached are attached to the respective reactor building 73 sides of the nuclear power plants 72A to 72D. The supporting member 2B is installed, and the work unit 2 and the crane unit 22 are installed on the guide rails 4A and 4B across the reactor building 73. Also in this embodiment, the decontamination building 60, the high dose rate structure, in which the storage container 69 storing the plant structure member in the reactor building 73 is determined based on the measured dose rate value and the shape information of the plant structure member. It is transported by the building transport cart 42 of either the member storage building 61 or the fuel storage building 62.

  A storage container 69 (or a container housing a disassembled plant structural member using the travel rail and the transport carriage 42 due to an increase in the number of transport carriages 42 moving on the travel rail or damage to the travel rail (or 70), it becomes difficult to transport the storage containers 69 and 70 containing the plant structural members disassembled using the container moving device 36A. Unload outside. The conveyance of the storage container 69 using the container moving device 36A will be described.

  A storage container 69 is placed on the support plate 87. A plant structural member (for example, a core shroud) disassembled by cutting or the like using the work devices 5 and 11 in the reactor building 73 is suspended in the crane device 88 and placed in the storage container 70 placed on the support plate 87. Stored. The wire 41 is wound up by two winding devices, and the support plate 87 on which the storage container 69 is placed is raised. Thereafter, the storage container 69 on the support plate 87 is moved on the support plate 103 installed in the secondary shielding tent 68 above the primary shielding tent 67 through the opening formed in the primary shielding tent 67. The storage container 69 storing the plant structural member on the support plate 103 is suspended from the crawler crane 109 and carried out of the secondary shielding tent 68 through an opening formed in the secondary shielding tent 68. Thereafter, the storage container 69 is transported to any one of the decontamination building 60, the high dose rate structural member storage building 61, and the fuel storage building 62 as in the first embodiment. Similarly, the storage container 70 storing the fuel assembly is also carried out above the secondary shielding tent 68.

  Each opening formed in the ceiling of each of the primary shielding tent 67 and the secondary shielding tent 68 through which the storage containers 69 and 70 pass is closed by an open / close door except when the storage containers 69 and 70 pass.

  In the present embodiment, each effect produced in the first embodiment can be obtained.

  A method for transporting a radioactive structural member according to embodiment 3, which is another embodiment of the present invention, will be described with reference to FIG.

  The radioactive structural member transport apparatus used in the method for transporting the radioactive structural member according to the present embodiment replaces the work unit 2 with the work unit 94 in the radioactive structural member transport apparatus 1 used in the first embodiment, and adds a radiation shield cover 90. It has the structure. The other structure of the radioactive structure member conveying apparatus used in the method for conveying the radioactive structure member of the present embodiment is the same as that of the radioactive structure member conveying apparatus 1.

  The work unit 94 includes a turning table 92, a support body 95, a guide member 96, and a work device 97. The support body 95 is installed on a turntable 92 in which an opening 93 extending long in one direction is formed. One end of a guide member 96 extending parallel to the turntable 92 is attached to the support body 95 and held by the support body 95. A working device 97 having a multi-axis manipulator 98 provided with a gripping grapple 99 and an abrasive cutting device is movably attached to a guide member 96 extending in one direction from the support 95 in the horizontal direction.

  The swivel table 92 is a biological shield that surrounds the reactor containment vessel 77 so as to cover the reactor pressure vessel 75 after the lid of the reactor containment vessel 77 and the lid of the reactor pressure vessel 75 are removed and carried out. Installed at the top. In the reactor building 73, the radiation shield cover 90 to which the open / close door 91 is attached covers the reactor well formed immediately above the equipment temporary storage pool 79, the fuel storage pool 80, and the reactor pressure vessel 75. Installed on the operation floor 81 of the vehicle.

  A swivel table 92 so that the gripping grapple 99 of the working device 97 moving along the guide member 96 and the abrasive cutting device provided in the multi-axis manipulator 98 face the plant structural member to be cut in the reactor pressure vessel 75. Is turned to turn the guide member 96 in the horizontal direction. The gripping grapple 99 of the working device 97 and the abrasive cutting device provided in the multi-axis manipulator 98 are inserted into the reactor pressure vessel 75 through the opening 93 formed in the swivel table 92, and plant structural members such as a core shroud, for example. Is cut by the abrasive sprayed from the nozzle of the abrasive cutting device. The cut core shroud is gripped by the grip grapple 99 and stored in the storage container 100 placed in the equipment temporary storage pool 79.

  The radiation dose rate of the cut core shroud is measured by a dose rate meter (not shown) provided in the working device 97. The dose rate measurement value is transmitted to the control device 64A, and the image information of the cut core shroud is also transmitted to the control device 64A. The control device 64A creates shape information of the cut core shroud based on the video information.

  The storage container 100 containing the core shroud, which is a high-dose rate structural member, is opened by the first crane 25 and is opened and closed by the first crane 25. The storage container 100 is suspended from the hook 27 of the first crane 25 of the crane unit 22. Is pulled up through the opening formed in the radiation shielding body cover 90. When the storage container 100 is raised above the reactor building 73, the traveling carriage 23 of the crane unit 22 is guided to the guide rail 4A provided at the upper end of the support member 2A and the guide rail provided at the upper end of the support member 2B. It is moved along 4B and conveyed to the decontamination chamber 58. The storage container 100 decontaminated in the decontamination chamber 58 is transported to the high-dose-rate structural member storage building 61 on the transport carriage 42 present on the temporary placement table 56 as in the first embodiment.

  In the present embodiment, the plant components in the reactor pressure vessel 75 cut by the abrasive sprayed from the nozzle of the abrasive cutting device are sequentially stored in the storage vessel 100, and the dose of the stored plant components is stored. It is conveyed to any one of the decontamination building 60, the high dose rate structural member storage building 61 and the fuel storage building 62 determined based on the rate measurement value and the shape information.

  In the present embodiment, each effect produced in the first embodiment can be obtained.

  DESCRIPTION OF SYMBOLS 1 ... Radioactive structural member conveying apparatus, 2,94 ... Work unit, 2A, 2B ... Supporting member, 3,23 ... Traveling carriage, 5, 11, 97 ... Work apparatus, 6, 12, 17A, 17B, 26, 31 ... Trolley, 8 ... Dose rate meter, 10, 15 ... Working arm, 16A, 16B ... Tool storage device, 18A, 18B ... Tool storage, 20A, 20B ... Tool changer, 22 ... Crane unit, 25 ... First crane, 27, 29, 32, 34 ... hook, 30 ... second crane, 36 ... container moving device, 37 ... moving cart, 39 ... lifting device, 40 ... support plate, 42 ... transport cart, 43 ... transfer device, 44A, 44B , 45A to 45D, 46 to 53 ... traveling rail, 54, 54A to 54D, 55, 55A to 55D ... turntable, 56 ... temporary table, 58 ... purification device, 59 ... low dose rate structural member storage building 60 ... decontamination building, 61 ... high dose rate structural member storage building, 62 ... fuel storage building, 63 ... maintenance building, 64 ... control room, 64A ... control device, 67 ... primary shielding tent, 68 ... secondary shielding tent 69, 70, 100 ... storage container, 72A-72D ... nuclear power plant, 73 ... reactor building, 74 ... turbine building, 75 ... reactor pressure vessel, 77 ... reactor containment vessel, 90 ... radiation shield cover, 92 ... swivel table, 96 ... guide member.

Claims (15)

  The dose rate of the plant structural member, which is a radioactive structural member to be carried out in the reactor building to be decommissioned, is measured, and the plant structural member is photographed by the first imaging device in the reactor building. The measured plant rate is measured and the measured plant dose is stored in a storage container in the reactor building, and the target location for transporting the storage container storing the plant component is the measured dose rate, Determining based on the first shape information of the plant structure member obtained based on the first video information output from the first imaging device and the information of the identification symbol of the storage container storing the plant structure member; A method for transporting a radioactive structural member, comprising transporting the storage container storing the plant structural member to the determined target location.   Transport of the storage container storing the plant constituent member is performed by a transport vehicle moving on a traveling rail, and the target location for transporting the storage container storing the plant constituent member is the measured dose rate, 2. The radioactive structural member according to claim 1, which is determined by a control device based on the first shape information and information on an identification symbol of the storage container, and the control device moves the transport vehicle to the determined target location. Transport method.   The target location is a first building that houses the plant structural member whose measured dose rate is equal to or less than a set dose rate, the measured dose rate exceeds the set dose rate, and the first shape information is A second building containing the plant structural member different from the second shape information of the plant structural member containing nuclear fuel material, and the measured dose rate exceeds the set dose rate, and the first shape information is It is one of the 3rd buildings which store the plant structural member which is the 2nd shape information, and the control device controls the rail switching device based on the determined target place, and thereby the plant structural member The transport vehicle that transports the storage container storing the container travels to one of the first building, the second building, and the third building, which is the determined target location. Method of transporting radioactive structural member according to claim 2 which is moved through the Lumpur.   The measurement of the dose rate of the plant structural member, imaging of the plant structural member, and storage of the plant structural member in the storage container are respectively performed in a plurality of the reactor buildings in one nuclear power plant. The method for transporting a radioactive structural member according to any one of 3.   The plant structure is constructed by a crane unit that is movably installed on each guide member provided on each support member installed on each outer side of the opposing side walls of the reactor building and arranged across the reactor building. The storage container storing the member is transported to a decontamination apparatus provided outside the reactor building, the storage container is decontaminated by the decontamination apparatus, and the decontaminated storage container is transported by the transport vehicle. The method for transporting a radioactive structural member according to claim 2 or 3, wherein the transporting is performed to the determined target location.   The plant structural member in the reactor building is cut by the work unit of the work unit that is movably installed on each guide member and arranged across the reactor building, and the cut plant structural member is The method for transporting a radioactive structural member according to claim 5, which is stored in a storage container.   Measurement of the dose rate of the plant structural member, imaging of the plant structural member, and storage of the plant structural member in the storage container are performed in a plurality of the reactor buildings in one nuclear power plant, and each of the atoms In the reactor building, by a crane unit that is movably installed on each guide member provided on each support member installed on each outer side wall of the reactor building and that straddles the reactor building. The container containing the plant structural member is transported to a decontamination apparatus installed outside the reactor building corresponding to the reactor building, and the reactor building is built for each reactor building. The storage container transported from the reactor is decontaminated by the decontamination apparatus, and the storage container decontaminated for each reactor building is determined by the transport vehicle. Method of transporting radioactive structural member according to claim 2 or 3, transferred to the target location.   In each of the reactor buildings, a plant structural member in the reactor building is cut using a work device of a work unit that is movably installed on each guide member and arranged across the reactor building. The method for transporting a radioactive structural member according to claim 7, wherein in each of the reactor buildings, the cut plant structural member is stored in the storage container. The travel rail includes a first travel rail and a second travel rail;
The transport vehicle carrying the storage container storing the plant component is moved to the building, which is the determined target location, by moving the transport vehicle along the first travel rail. I,
The transport vehicle in which the storage container is lowered in the building that is the determined target location is moved along the second traveling rail,
The movement of the transport vehicle for transporting the storage container to the first building, the second building, or the third building, which is the building of the determined target location, is moved to the first traveling rail. Controlling the first rail switching device provided and connecting the first traveling rail to the first branch rail of the first traveling rail;
The movement of the transport vehicle returning from the building at the determined target location is connected to each of the first building, the second building, and the third building. Among them, the second branch rail connected to the building as the determined target location is connected to the second traveling rail by controlling the second rail switching device provided on the second traveling rail. The method for conveying a radioactive structural member according to claim 3, wherein the method is carried out.   The storage container with the identification symbol attached to the transport vehicle that has moved along the first traveling rail and reached the first rail switching device is photographed by a second photographing device, The second video information including the video of the identification symbol is input to the control device from the two photographing devices, and the control device uses the determination of the target location for transporting the storage container storing the plant component. The method for transporting a radioactive structural member according to claim 9, wherein information on the identification symbol included in the second video information is used as information on the identification symbol of the storage container.   The switching control of the second rail switching device is performed by the control device along the second branch rail based on the third video information output from the third imaging device that images the transport vehicle. The method for transporting a radioactive structural member according to claim 9 or 10, which is performed when it is determined that the transport vehicle has reached the switching device.   The method for transporting a radioactive structural member according to any one of claims 9 to 11, wherein an empty storage container is placed on the returned transport vehicle and the empty storage container is transported to the reactor building side.   When the measured dose rate of the plant structural member stored in the storage container is equal to or lower than a set dose rate, the control device determines that the target location for transporting the storage container is the measured dose rate. Is determined to be the first building that houses the plant structure member that is less than or equal to the set dose rate, and the measured dose rate of the plant structure member stored in the storage container exceeds the set dose rate When the first shape information of the plant structural member is different from the second shape information of the plant structural member containing the nuclear fuel material, the measured dose rate is set as the target location for transporting the storage container. Determining that the first shape information is a second building containing the plant structure member that exceeds the dose rate and the first shape information is different from the second shape information of the plant structure member containing nuclear fuel material; When the measured dose rate of the plant structural member stored in the storage container exceeds the set dose rate and the first shape information is the second shape information, the purpose of transporting the storage container is The location is determined to be a third building that houses the plant structural member in which the measured dose rate exceeds the set dose rate and the first shape information is the second shape information. 3. A method for conveying a radioactive structural member according to 2.   In the control device, when the measured dose rate of the plant structural member stored in the storage container is equal to or lower than the set dose rate, a target place for transporting the storage container is the first building. And when the measured dose rate of the plant structural member stored in the storage container exceeds the set dose rate and the first shape information is different from the second shape information, It is determined that the intended location for transporting the storage container is the second building, and the measured dose rate of the plant structural member stored in the storage container exceeds the set dose rate. The method for transporting a radioactive structural member according to claim 3, wherein when the shape information is the second shape information, the target location for transporting the storage container is determined to be the third building. Measurement of the dose rate of the plant structural member, imaging of the plant structural member and storage of the plant structural member in the storage container are respectively performed in a plurality of the reactor buildings in one nuclear power plant,
Each storage container storing the plant structural member in each reactor building is transported to the building, which is the determined target location, by the transport vehicle moving on the first traveling rail. Item 13. The method for transporting a radioactive structural member according to any one of Items 9 to 12.

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