JP4960064B2 - Method and facility for treating radioactive metal waste - Google Patents

Description

  TECHNICAL FIELD The present invention relates to a radioactive metal waste processing method and a processing facility that enable a shared processing between processing of radioactive metal waste generated in nuclear facilities and other processing other than that.

  In nuclear power facilities such as nuclear power plants, the integrity and repair of equipment removed during periodic inspections, etc. are performed. Furthermore, installation equipment is exchanged as necessary. For radioactive metal waste generated during these operations, the volume of radioactive metal is reduced until it reaches a non-radioactive state below the clearance level in the controlled area, and then processing such as cutting, melting and solidification is performed in the non-controlled area. It is stored through or used as a reusable product.

  In the case of such radioactive metal waste treatment work, decontamination, measurement, and the accompanying transport process are included in any case, but conventionally it is generally compatible with decontamination, measurement, transport, etc. Thus, facilities such as different buildings are individually provided, and processing using a plurality of different dedicated facilities is performed.

  For example, radioactive metal volume reduction processing for decontamination of radioactive metal waste and confirmation measurement of radioactive metal waste becoming non-radioactive is performed in a dedicated volume reduction processing area. Further, the reused product manufacturing process in which the non-radioactive metal waste is melted and solidified to produce a reused product is performed in a dedicated reused product manufacturing processing area. Furthermore, equipment inspection processing for inspecting equipment removed from nuclear facilities is performed in nuclear power plants or in dedicated equipment inspection processing areas.

  A specific example of the equipment inspection process will be described. When carrying out inspection of equipment such as a turbine internal casing, a feed water heater, a high pressure nozzle, a low pressure nozzle, a reactor recirculation (PLR) pump, etc. during periodic inspection, In the nuclear power plant, parts are removed from the equipment and inspected, and if sound, the parts are assembled again. If it is not healthy, it is necessary to repair the equipment or replace it with a new one. Therefore, at the time of inspection, a certain amount of time is spent for removing parts, determining whether replacement is necessary, and then re-installing or carrying in and installing replacement parts.

  In addition, the equipment and parts to be removed are removed from the nuclear power plant and stored as waste in the nuclear power plant. In this case, a removal area is required in the nuclear power plant in order to dispose of large equipment, and the work area in the nuclear power plant is reduced accordingly.

  In clearance inspection, the object is cut and decontaminated if necessary, and inspection is performed, and the verified object is stored. Therefore, a certain area is required in the nuclear power plant.

  Furthermore, conventionally, a regular inspection equipment warehouse for storing regular inspection equipment has been set up, and this regular inspection equipment warehouse is stored in a cask. During use, the inspection equipment is usually taken out to the nuclear power plant in a state where it is housed in the cask, taken out from the cask at the place of use and inspected, and after use, it is again housed in the cask and returned to the inspection equipment warehouse. store. For this reason, a dedicated inspection equipment storage space is required.

  In addition, tools, scaffolding, turntables, and other equipment may be managed at a certain storage site outside the power plant. When tools are used, they are brought from the storage site to the nuclear power plant. Take it home on the route. Therefore, a constant tool conveyance distance and time are always required.

  As a conventional technique, it has been proposed to discriminate, decontaminate and measure radioactive metal waste generated at a nuclear power plant, and to contribute to reuse of the decontaminated waste (for example, refer to Patent Document 1). . In this technology, five types of processing flow are shown depending on the object, including the necessity of cutting before decontamination, necessity of volume reduction of the disposal object, necessity of measurement after packing the container for disposal object, etc. ing. The main steps in these processes are cutting, decontamination, measurement and the like.

  In addition, a method has been proposed in which periodic inspections at a nuclear power plant are carried out in a separate building adjacent to the power plant or a remote building in the site of the power plant (for example, see Patent Document 2). In this technique, decontamination work is also performed in a separate building as the first stage of inspection work.

In addition, it has been proposed to recycle parts generated at a nuclear power plant at a decontamination plant or a recycling plant outside the site of the nuclear power plant (see, for example, Patent Document 3). Furthermore, a technique for recycling radioactive solid waste generated at a nuclear power plant with a plant owner, a dismantling company, a decontamination company, a raw material company, a product processor, and a plant owner has been proposed (for example, Patent Document 4). reference). Furthermore, it has also been proposed to decontaminate and melt metal waste generated at a nuclear power plant to reduce the volume or make it a reuse product (for example, see Patent Document 5).
Japanese Patent No. 2507477 JP 11-118984 A JP 2004-37231 A JP 2002-3111197 A JP 2003-307591 A

  All of the above-described conventional techniques include decontamination, measurement, and a transport process associated therewith. For this reason, the disposal cost for decontaminating radioactive metal waste and making it non-radioactive is high, and a large radioactive waste storage area is required. Furthermore, because the work is performed at individual facilities regardless of the amount of periodic inspection work, periodic inspection work, etc., including work performed at other locations when there are many periodic inspection work, etc. There are cases in which the work scale fluctuates year by year, which makes it difficult to secure personnel.

  Furthermore, when the periodic inspection work overlaps with other work, there may be a limitation in securing an area necessary for the periodic inspection, and it may be difficult to obtain a margin for formulating the periodic inspection plan. Furthermore, there is a case where the processing of reusing non-radioactive metal waste is affected, and the efficiency of processing work for effective utilization of metal resources may be reduced.

  In nuclear power plants, there are needs for decontamination and measurement for various purposes as described above. Conventionally, it is general to prepare equipment individually for these needs.

  This invention is made | formed in view of such a situation, and can perform the shared process about the process of a decontamination, a measurement, etc. which have the objective different from this with the process of a radioactive metal waste. It aims at providing the processing method and processing equipment of a radioactive metal waste.

  In addition, the present invention can perform the work in the common facility much during the time when there is little work in the power plant, and can reduce the work in the common facility during the time when there is a lot of work in the power plant, thereby achieving leveling of the work in the year. An object of the present invention is to provide a radioactive metal waste treatment method and treatment facility that are possible and advantageous from the viewpoint of securing personnel.

  Furthermore, in the present invention, by carrying out part of the periodic inspection work at the common facility, it is possible to reduce the area required for periodic inspection, reduction, time reduction, etc. To provide a method and facility for treating radioactive metal waste that can provide a margin for inspection planning, and that enables the effective utilization of metal resources by reusing metal waste. Objective.

In order to achieve the above object, in the present invention, radioactive metal volume decontamination treatment for decontamination of radioactive metal waste and confirmation measurement that the radioactive metal waste has become non-radioactive, and removal from the nuclear facility are performed . A common building that allows equipment or parts discharged from nuclear facilities to be stored in accordance with their respective radioactivity levels when equipment or parts removed from this nuclear facility are updated with equipment inspection processing for inspecting equipment A reusable product manufacturing process is carried out by a processing facility for forming a radiation control area, and a metal waste made non-radioactive by the radioactive metal volume reduction process is solidified after being melted to produce a reusable product . Provided is a method for treating radioactive metal waste, which is performed by a treatment facility that is arranged adjacent to a radiation control area and forms a non-control area .

  Further, in the present invention, it is composed of a management building that forms a radiation management area and a non-management building that is arranged adjacent to the management building and forms a non-management area. Radioactive metal volume reduction processing system that performs decontamination of metal waste and confirmation that radioactive metal waste has become non-radioactive, and non-radioactive metal waste is solidified after melting to produce reusable products There is provided a processing facility for radioactive metal waste, characterized in that a reusable product production processing system and an equipment inspection processing system for inspecting equipment removed from a nuclear facility for reuse are arranged.

  According to the present invention, shared processing can be performed for processing (decontamination, measurement, etc.) having different purposes, and efficient workability can be ensured from the viewpoint of securing facilities and personnel.

  Further, according to the present invention, it is possible to shorten the periodic inspection of the nuclear facilities, particularly the nuclear power plant, level the construction amount, and effectively use the area in the nuclear power plant.

  DESCRIPTION OF THE PREFERRED EMBODIMENTS Embodiments of a radioactive metal waste treatment method and treatment equipment according to the present invention will be specifically described below with reference to the drawings.

[First Embodiment (FIG. 1)]
1st Embodiment of this invention demonstrates the processing method of the radioactive metal waste which performs three types of processes with the processing equipment installed in the radiation control area or non-control area in a common building.

  That is, in this embodiment, radioactive metal waste decontamination and radioactive metal volume reduction treatment (first treatment), which is confirmation measurement that radioactive metal waste is non-radioactive, and non-radioactive metal waste Recycled product production process (second process) that solidifies after melting, and equipment inspection process (third process) that inspects equipment removed from nuclear facilities such as nuclear power plants All processing is performed.

  FIG. 1 is a process flow diagram illustrating a method for treating radioactive metal waste according to the present embodiment. As shown in FIG. 1, the radioactive metal volume reduction process (first process) is performed in the radiation control area A and the non-control area B. In this radioactive metal volume reduction treatment (first treatment), first, in the radiation control area A, a first cutting step for cutting radioactive metal waste into a predetermined size suitable for decontamination (hereinafter referred to as “cutting A step”). 1) is performed. That is, in this cutting A step 1, the metal waste is cut into a size applicable to the decontamination apparatus.

  Next, the decontamination process 2 which makes the cut | disconnected radioactive metal waste non-radioactive is performed. In this decontamination process 2, decontamination work is performed until the radioactive metal waste becomes non-radioactive (below the clearance level).

  After the decontamination process 2, a second cutting process (hereinafter referred to as “cutting B process”) 3 for cutting the decontaminated radioactive metal waste into a predetermined size in order to further reduce the size as necessary. Is done. That is, in this cutting B step 3, the metal waste is cut into a size that can be applied to a measuring device, and is performed as necessary.

  After the decontamination process 2 or the cutting B process 3, a first measurement process (hereinafter referred to as “measurement A process”) 4 is performed for confirming that the radioactive metal waste has become non-radioactive. In this measurement A step 4, it is measured and confirmed that the metal waste after decontamination has become non-radioactive (below the clearance level). Here, the metal waste whose non-radioactivity could not be confirmed is returned to the decontamination process 2 again.

  Finally, a storage process (hereinafter referred to as “storage B process”) 8 is performed in which the metal waste confirmed to be non-radioactive is stored in the unmanaged area B.

  Thus, in this embodiment, as a radioactive metal volume reduction treatment (first treatment), after cutting A step 1, radioactive metal is decontaminated in decontamination step 2, and non-contamination of the metal waste after decontamination is performed. Radioactivity (being a clearance level or less) is confirmed and measured in measurement A step 4, and the metal waste that has been confirmed to be non-radioactive is moved to the non-managed area B and stored in storage B step 8. The stored non-radioactive metal waste is paid out for production of reusable products at a general factory outside the facility, or as a reusable product in the following reusable product production process (second process). The manufacturing process is performed.

  Next, the reuse product production process (second process) will be described. In the reuse product manufacturing process (second process), the metal waste reduced in volume by the first process or the metal waste carried in from other places such as the outside is processed. That is, this reuse product manufacturing process (second process) is a process step for manufacturing a reuse product in the non-managed area B.

  In this reusable product manufacturing process (second process), in order to insert the non-radioactive metal waste into the melting furnace, first, a process of cutting the metal waste into a predetermined dimension (hereinafter referred to as “cutting C process”). .) 9 is performed.

  And the metal waste cut | disconnected by the cutting | disconnection C process 9 is inserted in a melting furnace in the melting process 10, and is fuse | melted. The molten metal melted in the melting step 10 is cast into a reusable product by being poured into a mold and cooled and solidified in the productizing step 11.

  Thus, in the reusable product production process (second process), the metal waste that has become non-radioactive in the radioactive metal volume reduction process (first process), or other than the shared processing facility according to this embodiment, Non-radioactive metal waste is also acceptable. Then, the metal waste is melted in the melting step 10, cast in the productizing step 11, and commercialized as a reused product. In this reuse product manufacturing process (second process), the cutting C process 9 is a cutting for loading into the melting furnace, and is performed as necessary.

  The equipment inspection process (third process) is a processing process in which the equipment of the nuclear power plant is removed and inspected at the time of periodic inspection or the like, and is performed in the radiation control area A. This equipment inspection process (third process) includes the same decontamination process 2 as in the first process, a measurement B process 5 for measuring the radioactivity of the equipment, an inspection process 6 for performing a predetermined inspection, and after the inspection. And a storage A step 7 for temporarily storing in the radiation control area A for reusing the device.

  In this way, in the third processing step, the inspection target device is removed from the nuclear power plant, transferred to the common processing facility, inspected in the inspection step 6, and then used in the storage A step 7 for the next use. It is stored until the equipment to be inspected is returned to the power station.

  In the above process, the cutting A process 1, the cutting B process 3 and the cutting C process 9 are processes that are cut to sizes applicable to a decontamination apparatus, a measuring apparatus, and a melting apparatus, respectively. If the sizes can be unified, the cutting process can be made more efficient.

  According to the present embodiment described above, by decontaminating radioactive metal waste and making it non-radioactive, radioactive waste can be reduced, and disposal costs can be reduced. In addition, by decontaminating radioactive metal waste and making it non-radioactive, it is possible to reduce the radioactive waste storage area. In addition, it is possible to standardize the annual periodic inspection work by performing a lot of work at the common facility when there is little periodic inspection work and reducing the work at the common facility when there is much periodic inspection work. This is advantageous from the viewpoint of securing personnel. Furthermore, by carrying out part of the periodic inspection work at the common facility, the necessary area for the periodic inspection can be reduced. That is, since the restriction on the periodic inspection area can be eliminated, a margin can be obtained for the regular inspection plan. Furthermore, by reusing non-radioactive metal waste, metal resources can be effectively utilized.

[Second Embodiment (FIG. 2)]
The second embodiment of the present invention is a method that is substantially the same as the first embodiment, but in the case of performing a reusable product manufacturing process, a method of storing the molten solidified body before becoming a reusable product in a building. is there.

  That is, in this embodiment, in the same manner as in the first embodiment described above, the radioactive metal volume reduction process (first operation) for performing decontamination of radioactive metal waste and confirming that the radioactive metal waste has become non-radioactive (first Treatment), reusable product production process (second process) to solidify the non-radioactive metal waste after melting, and equipment inspection process (second process) to inspect equipment removed from nuclear facilities All the three processes are performed by the processing equipment installed in the radiation control area A or the non-control area B in the common building. However, in the present embodiment, unlike the first embodiment, when a process for manufacturing a reused product is performed, the melted solid before becoming the reused product is stored in the building.

  FIG. 2 is a process flow diagram illustrating the radioactive metal waste processing method according to the present embodiment. As shown in FIG. 2, also in the case of this embodiment, the process of performing the radioactive metal volume reduction process which is a 1st process is performed in the radiation control area A and the non-control area B. FIG. In this process, first, in the radiation control area A, a cutting A process 1 for performing a first cutting for cutting the radioactive metal waste into a predetermined size suitable for decontamination, a decontamination process for making the radioactive metal waste non-radioactive. 2. Cutting B process 3 for performing the second cutting for further cutting the radioactive metal waste after decontamination into a predetermined size, and measurement A process for performing confirmation measurement that the radioactive metal waste has become non-radioactive 4 is included. Next, a storage B process 8 for storing the metal waste that has been confirmed to be non-radioactive in the unmanaged area B is included. In addition, when a non-radioactive property cannot be confirmed in the measurement A step 4, the metal waste is returned to the decontamination step 2 again.

  In the process of producing a reused product, which is the second treatment, the metal waste reduced in volume by the first treatment or the metal waste carried from another place is treated. This step is a processing step for producing a reusable product in the unmanaged area B. In this step, a cutting C step 9 for cutting the metal waste into a predetermined size for insertion into the melting furnace, a melting step 10 for melting the cut metal waste in the melting furnace, and pouring the molten metal into the mold. And a commercialization step 11 in which the reusable product is cast by cooling and solidification.

  The process of performing the equipment inspection process, which is the third process, is a process process in which the equipment of the nuclear power plant is removed and inspected during periodic inspections, etc., and is performed in the radiation control area A. This process includes the same decontamination process 2 as the first treatment, the measurement B process 5 for measuring the radioactivity of the equipment, the inspection process 6 for performing the predetermined inspection, and the radiation control area for reusing the apparatus after the inspection. A storage A step 7 for temporary storage in A is included.

  In this case, in this embodiment, in the third processing step, the reuse step in the general factory is deleted from the storage B step 8 in the first processing step. And in the above-mentioned 1st Embodiment, in the 2nd processing process, while the process following the melting process 10 was the productization process 11, in this embodiment, it is set as the melt solidification process 12 in the 2nd processing process, Intermediate storage after melting and solidification.

  In the second embodiment described above, the metal that has been decontaminated and made non-radioactive is used as a melt-solidified material, and by performing reduced storage, in addition to the effects shown in the first embodiment, the storage capacity can be reduced. Can be expected. Usually, the amount of waste filled in the container is about 10 to 20%, so that volume reduction of 1/5 to 1/10 can be achieved by melting and solidifying.

[Third Embodiment (FIG. 3)]
In the third embodiment of the present invention, a method and a processing facility for processing radioactive metal waste using a building facility will be described. FIG. 3 is a plan view for explaining the present embodiment, and shows a case where two adjacent buildings are used.

  As shown in FIG. 3, in the shared building 100 of the present embodiment, a building that forms a radiation management area (hereinafter referred to as “managed building”) 13 and a building that forms a non-managed area (hereinafter referred to as “non-managed building”). 14) are installed adjacent to each other.

  The management building 13 and the non-management building 14 have, for example, a rectangular shape in plan view, and are installed adjacent to each other so that one surface faces each other. The entrance / exit ports 15 and 16 are provided on the wall surfaces of the buildings 13 and 14 facing each other, and the device carry-in / out ports 17 and 18 for carrying in / out devices from the outside are provided on the opposite wall surfaces. Central passages 19 and 20 communicated with each other are provided at the central positions of both buildings 13 and 14.

  In the management building 13, a plurality of processing areas are arranged on both sides of the central passage 19. First, on one side (lower side in FIG. 3) of the central passage 19 on the equipment loading / unloading port 17 side, a receiving, unloading, and unpacking area 22 is provided for receiving the equipment to be loaded. It has been. On the side facing the receiving, unloading, and unpacking area 22 across the central passage 19 (upper side in FIG. 3), there is a first cutting area (hereinafter referred to as “cutting A” for cutting equipment). 23) is provided. On the side where the cutting A area 23 is arranged, the decontamination area 24 for performing the decontamination work and the cutting area for performing the second cutting process (hereinafter referred to as “cutting B”) in order toward the communication entrance 15. Area 25 ”) and a measurement area 26 for radiation measurement.

  In addition, on the side where the unloading area 22 is received and unloaded in the management building 13 (the lower side in FIG. 3), the equipment is temporarily stored in order toward the communication entrance 15. An equipment temporary storage area 27, an inspection area 28 for equipment inspection, and a spare parts storage area 29 for storing spare parts are provided.

  On the other hand, a plurality of processing areas are also arranged on both sides of the passage 20 in the unmanaged building 14. First, in order from the equipment loading / unloading port 18 side to one side of the passage 20 (upper side in FIG. 3), an equipment temporary placement area 30 for temporarily placing equipment and a third cutting area for cutting equipment. (Hereinafter referred to as “cutting C area”) 31, a material discrimination area 32 for discriminating the material, and a discrimination material storage area 33 for storing the discriminated material.

  Further, on the other side of the passage 20 in the unmanaged building 14 (the lower side in FIG. 3), a melting furnace area 34 in which a melting furnace for melting metal is installed in order from the connecting entrance 16 side; A casting area 35 for casting with molten metal, a product processing area 36 for processing the casting as a reused product, and a product storage area 37 for storing the reused product are provided.

  And in this embodiment, as shown by the solid line arrow (thick line arrow), the radioactive metal volume reduction process (first process) is performed in the management building 13. In addition, as shown by a solid line arrow (thin line arrow), a reusable product production process (second process) is performed in the unmanaged building 14. Furthermore, as indicated by a broken line arrow, an equipment inspection process (third process) is performed in the management building 13.

  First, in the step of radioactive metal volume reduction processing (first processing), radioactive metal waste is carried into the management building 13 from the equipment loading / unloading port 21 in a state of being stored in the container (arrow a1). The carried radioactive metal waste is received, unloaded, unloaded in the unpacking area 22 and unpacked. The unpacked radioactive metal waste is transferred to the cutting A area 23, the decontamination area 24, and the cutting B area 25 (arrows a2, a3, a4), and necessary cutting is performed as in the first embodiment. In the decontamination area 24, decontamination is performed.

  The decontaminated radioactive metal waste is transferred to the measurement area 26 (arrow a5), and the confirmation measurement and the carry-out inspection that it has become non-radioactive are performed. Thereafter, the metal waste that has been confirmed to be non-radioactive is transferred from the management building 13 that is the radiation management area A to the non-management building 14 that is the non-management area B through the contact entrances 15 and 16 ( Arrow a6) is temporarily stored in the device temporary storage area 30. Thereafter, when the temporarily stored metal waste is processed as a reused product in the unmanaged building 14 that is a common facility, the following second processing step is performed. Moreover, when it is commercialized as a reusable product in a general factory or the like, it is unloaded from the device loading / unloading port 38 of the unmanaged building 14 (arrow a7).

  Next, in the reuse product manufacturing process (second process), non-radioactive metal waste temporarily stored in the equipment temporary storage area 30 by the radioactive metal volume reduction process (first process), or other The metal waste (arrow b1) that has been decontaminated and made non-radioactive in this place and carried into the unmanaged building 14 becomes the object to be treated.

  The metal waste to be treated is stored in the equipment temporary storage area 30, and then cut into a predetermined size as needed by the cutting c area 32 (arrow b2), and is separated for each material in the material discrimination area 32. Discriminated (arrow b3). The discriminated material is sent to the discriminating material storage area 33 (arrow b4), and is sorted and stored for each material.

  Of the material stored in the discrimination material storage area 33, an amount of material necessary for the processing is taken out and transferred to the melting furnace area 34 (arrow b5), where the melting processing is performed. Then, the melt of the material melted in the melting furnace area 34 is cast in the casting area 35 (arrow b6), and a cast product as a recycled product is formed. Thereafter, the cast product is transferred to the product processing area 36 (arrow b7), surface finish is applied, coating is performed, and the product is completed. The completed product is stored in the product storage area 37 for shipment (arrow b8). At the time of shipment, each recycled product is unloaded from the device loading / unloading port 18 of the unmanaged building 14.

  Further, in the equipment inspection process (third process), the equipment to be inspected taken out from the power plant or the like is transferred to the management building 13 in a state of being stored in a container, and is transferred from the equipment loading / unloading port 17 into the management building 13. (Arrow c1). The loaded equipment is received, unloaded, unloaded in the unpacking area 22 and unpacked, and temporarily stored in the equipment temporary storage area 27 (arrow c2). Thereafter, when the inspection work is performed, it is transferred from the equipment temporary storage area 27 to the decontamination area 24 and the measurement area 26 as necessary (arrows c3 and c4), and when the dose of the equipment to be inspected is high, Decontamination is performed in the decontamination area 24 for the purpose of reducing the exposure of inspection workers, and the decontamination effect is measured in the measurement area 26. After the necessary decontamination and measurement are performed, the device to be inspected is transferred to the inspection area 28 (arrow c5), and after a predetermined inspection, it is transferred as a spare part to the spare part storage area 29 (arrow). c6), stored until the next use in a nuclear power plant. At the time of use, it is transferred from the equipment loading / unloading port 17 to a power plant or the like (arrow c7).

  As described above, in this embodiment, the processing facility includes a management building that forms a radiation management area and a non-management building that is arranged adjacent to the management building and forms a non-management area. The management building has a radioactive metal volume reduction system that performs decontamination of radioactive metal waste and confirms that the radioactive metal waste has become non-radioactive, and solidifies after melting the non-radioactive metal waste. A reusable product production processing system for manufacturing reusable products and an equipment inspection processing system for inspecting equipment removed from the nuclear facility for reuse are arranged.

  According to the third embodiment described above, in addition to the operational effects shown in the first and second embodiments, the economic efficiency can be improved by sharing the decontamination device, the measurement device, the cutting device, and the like. That is, since an apparatus is not prepared for each process, the initial investment can be reduced and the equipment utilization rate can be improved. Moreover, compared with the case where a plurality of different processing buildings are provided corresponding to each processing, by using a common processing building, it is possible to reduce the number of processing buildings, reduce the number of buildings, and the like.

[Fourth Embodiment (FIG. 4)]
4th Embodiment of this invention demonstrates the processing method of the radioactive metal waste which uses the processing equipment movable between the same building, an adjacent building, or these and another building as a processing facility.

  FIG. 4 is a plan view for explaining the present embodiment. As shown in FIG. 4, this embodiment is basically a method of using a building and processing equipment substantially the same as the common building 100 and processing equipment shown in the third embodiment, and is common to the third embodiment. About a structure and an effect | action, the code | symbol same as FIG. 3 is attached | subjected to FIG. 4, and description is abbreviate | omitted. In the case of the present embodiment, the steps (arrows c3 and c4) transferred to the decontamination area 24 and the measurement area 26 in the third embodiment are omitted.

  As shown in FIG. 4, the present embodiment is different from the third embodiment in that it is installed in a treatment facility, for example, a decontamination apparatus 39 installed in the decontamination area 24 in the management building 13 and a measurement area 26. The measuring device 40 is movable. The decontamination device 39 and the measurement device 40 can be moved to another area in the management building 13, such as the inspection area 29 (arrow d).

  In addition, the decontamination device 39 and the measurement device 40 can be moved to other than the management building 13, for example, can be moved to the non-management building 14 and can be moved to another building. Has been.

  According to this embodiment, the movement route of the inspection object is simplified by moving the decontamination device 39 and the measurement device 40 in the same building, adjacent buildings, or moving between different buildings. The inspection process can be shortened accordingly. Therefore, in addition to the operational effects achieved by the third embodiment, there is an operational effect that the inspection process can be further shortened.

[Fifth Embodiment (FIG. 5)]
5th Embodiment of this invention demonstrates the case where a chemical decontamination apparatus is applied as the decontamination apparatus 39 used by embodiment mentioned above. FIG. 5A is a system configuration diagram illustrating an example of the chemical decontamination apparatus according to the present embodiment, and FIG. 5B is a system configuration diagram illustrating another example of the chemical decontamination apparatus.

  In the example of FIG. 5 (A), the system configuration | structure in the case of performing immersion type chemical decontamination of the apparatus used as a process target in a common facility is shown. In the immersion type chemical decontamination apparatus 39 shown in this figure, a decontamination tank 52 for accommodating a decontamination target device 51 is provided in a loop-shaped system pipe 50. A circulation pump 53 is connected to the decontamination tank 52, and water is circulated to the decontamination tank 52 via the system pipe 5 by the circulation pump 53.

  A system pipe 50 located between the circulation pump 53 and the decontamination tank 52 is sequentially provided with a heater 54, a cation resin tower 55, a mixed bed resin tower 56, and an organic acid decomposition apparatus 57. A chemical injection tank 58 and a chemical injection pump 59 are connected to the decontamination tank 52 via a system pipe 50 and a separate pipe so that a predetermined amount of chemical solution can be supplied to the decontamination tank 52.

  In such a configuration, when immersion chemical decontamination is performed, the decontamination target object 51 is immersed in the decontamination tank 52, and the water in the decontamination tank 52 is passed through the heater 54 by the circulation pump 53 and the decontamination tank 52. The temperature is raised while circulating in a circulation loop that returns to When the system reaches a prescribed temperature, the organic acid decontamination agent in the chemical injection tank 58 is injected into the decontamination tank 52 by the chemical injection pump 59. Thereby, chemical decontamination is started. Radioactive metal ions dissolved by chemical decontamination are captured by the cation resin tower 55. When the chemical decontamination is completed, the organic acid decontaminating agent is decomposed by the organic acid decomposing apparatus 57, and the system water after decontaminating is finally purified by the mixed bed resin tower 56 and drained. According to this embodiment, scientific decontamination of radioactive metal waste can be performed effectively.

  The system configuration shown in FIG. 5 (B) is suitable when the system is chemically decontaminated in the nuclear power plant, and the decontamination target system 60 in which the decontamination target is incorporated in a part of the system piping 50. It is said that. The description of other structures is omitted because it is similar to that of the example of FIG. According to the example shown in FIG. 5B, the decontamination target system 60 included in the system piping 50 can be continuously decontaminated.

[Sixth Embodiment (FIG. 6)]
In the sixth embodiment of the present invention, equipment or parts removed from the nuclear power plant are inspected in a common building, and the equipment and parts after the inspection are stored as spare parts, while another equipment that replaces the removed equipment or parts is stored. Alternatively, a method for treating radioactive metal waste in which parts are carried into a nuclear power plant will be described. FIG. 6 is an explanatory diagram (plan view) of a process using this method.

  As shown in FIG. 6, a PLR pump or the like is installed as a device 113 in the building 112 of the nuclear power plant 111. In the periodic inspection, the parts 114a of the large equipment 113 such as PLR pumps are removed from the building 112 of the nuclear power plant 111 and transferred to the radiation control area A of the common building 100 (take-out routes x1, x2). ) Conduct inspections. And after completion | finish of inspection, the components 114a of this large sized apparatus 113 are stored in the common building 100. FIG.

  On the other hand, in the common building 100, an adjusted part 114b is stored in place of the part 114a of the equipment 113 to be taken out in advance, and this part 114b is used as a process for taking out the part 114a from the building 112 of the nuclear power plant 111. In parallel, it is transported to the building 112 of the nuclear power plant 111 (carry-in route y1, y2).

  That is, in the present embodiment, the process of taking out the inspected equipment and parts 114a from the nuclear power plant 111, inspecting and storing them, and replacing the equipment or parts 114b in place of the removed equipment or parts 114a with the building of the nuclear power plant 111. The step of carrying in and installing in 112 can be performed at substantially the same time. In addition, after taking out, repairing, decontaminating, etc., the part 114a of the device 113 that has been taken out, it can be stored in the common building 100 and used as a spare part for next inspection.

  According to the present embodiment, the parts 114a and 114b can be carried in and out at the same time, and the removed part 114a can be transported to the common building 100 for inspection and storage. The inspection period can be shortened by 114a. Further, in the common building 100, work such as inspection of the removed component 114a can be systematically performed. This greatly improves the time spent on the inspection of the equipment, and can lead to shortening of the process.

[Seventh Embodiment (FIG. 7)]
In the seventh embodiment of the present invention, when the equipment or parts removed from the nuclear power plant are updated, the equipment is removed in the common building (the waste discharged from the nuclear facilities is adjusted to each radioactivity level). We will explain how to dispose of radioactive metal waste by bringing in alternative equipment that corresponds to the removed equipment to the nuclear power plant. FIG. 7 is an explanatory diagram (plan view) of a process using this method.

  As shown in FIG. 7, the devices installed in the building 112 of the nuclear power plant 111 include a removal target device 115a to be removed after a predetermined period. The device 115a to be removed is removed from the building 112 of the nuclear power plant 111 and transferred to the radiation management area A of the common building 100 (unloading route x3), cut, etc., and stored in the container 116 or the like during periodic inspection.

  On the other hand, the device 115b replaced with the device 115a to be removed is transported to the building 112 of the nuclear power plant 111 in parallel with the process of taking out the component 114a from the building 112 of the nuclear power plant 111 (carry-in route y3).

  That is, in this embodiment, the process of taking out the removal target device 115a from the nuclear power plant 111 and removing it and the step of carrying in and installing another device 115b replacing the removal target device 115a in the building 112 of the nuclear power plant 111 are omitted. It can be done at the same time.

  According to this embodiment, since the equipment 115a and 115b can be carried in and out at the same time, the removal period of the equipment 115a in the nuclear power plant can be shortened by the inspection period of the parts 115a. Further, the removal target device 115a or parts are carried out to the common building 100, and stored and managed as waste after the removal.

  Furthermore, by removing and storing in the common building 100, the inspection period can be shortened, and at the same time, the removed equipment and parts are carried into the common building 100, thus avoiding pressure on the work area in the nuclear power plant. can do.

[Eighth Embodiment (FIG. 8)]
In the eighth embodiment of the present invention, there is provided a method for treating radioactive metal waste as a product by decontaminating equipment and parts that can be removed from a nuclear power plant, decontaminating them in a common building, performing clearance inspection. explain. FIG. 8 is an explanatory view (plan view) showing the steps of this method.

  As shown in FIG. 8, in this embodiment, the equipment removal process 121 from the building 112 of the nuclear power plant 111, the carrying-out process 122 to the common building 100, the cutting process 123, the decontamination process 124, the confirmation process 125, the clearance detection A recognition step 126 is performed. Thereafter, it is carried out as a clearance utilization product 127. The confirmation process may be performed as a prior confirmation of clearance verification.

  That is, according to the present embodiment, after removing the devices and parts, they are carried into the common building 100, where they are cut, decontaminated, and checked for clearance. In the clearance processing factory 116, the clearance utilization product 127 can be manufactured.

  According to this embodiment, the place where the nuclear power plant is used can be reduced by removing the device or part from the nuclear power plant 111 immediately after the device or component is removed. In addition, since a series of operations up to clearance verification can be performed in the shared building 100, the regular inspection period at the nuclear power plant 111 can be shortened.

  Further, since the work can be smoothed, it is possible to lead to stable employment, and furthermore, it is possible to reduce radioactive waste, effectively use metal resources, and avoid waste pressure in the waste storage area.

[Ninth Embodiment (FIG. 9)]
In the ninth embodiment of the present invention, when inspecting temporary equipment used at a nuclear power plant after use, the equipment is inspected and arranged, and then transferred to a common building for storage, and the radioactive metal waste processing method is performed. explain. FIG. 9 is an explanatory view (plan view) showing the steps of this method.

  As shown in FIG. 9, in the present embodiment, in the nuclear power plant 111, the periodic inspection equipment 132 that is the equipment used at the time of the periodic inspection for contamination is taken out from the cask 133 and used. After use, it is stored again in the cask 133 and carried out of the nuclear power plant 111 (unloading route x4).

  The cask 133 is transported to the common building 100, the contaminated regular inspection equipment 132 is taken out from the cask 133, inspected, and stored in the common building storage place 137 (storage route x5). In use, it is further brought into the nuclear power plant 111 (carry-in route y4).

  Conventionally, the regular inspection equipment warehouse is intended only for the storage of equipment, but according to the present embodiment, the inspection at the common building 100 reduces the work at the nuclear power plant 111.

[Tenth Embodiment (FIG. 10)]
In the tenth embodiment of the present invention, a tool or other equipment used for inspection, modification or other construction carried out at a nuclear power plant, for example, equipment such as a scaffold or a turntable (tool, etc.) is used after use. The processing method of the radioactive metal waste stored in will be described. FIG. 10 is an explanatory view (plan view) showing the steps of this method.

  As shown in FIG. 10, in this embodiment, a tool 135 or the like stored in the storage site of the nuclear power plant 111 is brought in and used during periodic inspections. After use, the tool 135 or the like is taken out, surveyed, and carried out to the common building 100, which is an unmanaged area. Then, when necessary, it is carried into the nuclear power plant 111 and installed. Note that the third building can be used as the non-management area.

  According to this embodiment, since the tools and the like are placed in the shared building in the power plant by organizing and storing in the shared building 100, the efficiency of tool transportation can be improved. Further, by storing the tools 135 in the common building 100, the work place can be widely used in the nuclear power plant 111, and the area pressure in the nuclear power plant 111 can be avoided.

[Other Embodiments]
In addition to the above embodiments, various modifications and applications are possible in the present invention. For example, in the above embodiment, the method of performing all the processes of the radioactive metal volume reduction process, the reuse product production process and the equipment inspection process has been described. However, these radioactive metal volume reduction process, reuse product production process and equipment inspection are described. Any two or more processes selected from among the processes can be performed by the processing equipment in the common building.

  In the above embodiment, as an example of a building, a method of using facilities in two adjacent buildings has been described. However, the number and arrangement of buildings, and the type, number, and arrangement of facilities in the building, etc. Various changes can be made.

  Furthermore, although the case where only the chemical decontamination apparatus is used has been described in the above embodiment, the present invention is not limited to the case where the chemical decontamination apparatus is used, and other decontamination apparatuses such as a mechanical decontamination apparatus, a measurement apparatus, A cutting device or the like can be used, and by using these devices, various devices can be effectively used.

The processing flowchart explaining 1st Embodiment of this invention. The processing flowchart explaining 2nd Embodiment of this invention. The building top view explaining 3rd Embodiment of this invention. The building top view explaining 4th Embodiment of this invention. (A), (B) is a system configuration | structure figure explaining 5th Embodiment of this invention. The schematic plan view explaining the process by 6th Embodiment of this invention. The schematic plan view explaining the process by 7th Embodiment of this invention. The schematic plan view explaining the process by 8th Embodiment of this invention. The schematic plan view explaining the process by 9th Embodiment of this invention. The schematic plan view explaining the process by 10th Embodiment of this invention.

Explanation of symbols

1. Cutting A process, 2. Decontamination process, 3. Cutting B process, 4. Measurement A process, 5. Measurement B process,
6 ... Inspection process, 7 ... Storage A process, 8 ... Storage B process, 9 ... Cutting C process, 10 ... Melting process,
DESCRIPTION OF SYMBOLS 11 ... Productization process, 12 ... Melt-solidification process, 13 ... Control building, 14 ... Non-management building, 21 ... Equipment entrance, 22 ... Receipt, unloading, unpacking area, 23 ... Cutting A area, 24 ... Exclusion Dyeing area 25 ... Cutting B area 26 26 Measuring area 27 Equipment temporary storage area 28 Inspection area 29 Spare parts storage area 30 Equipment temporary storage area 31 Cutting C area 32 Material discrimination 33, Discrimination material storage area, 34 Melting furnace area, 35 Casting area, 36 Product processing area, 37 Product storage area, 38 Equipment inlet / outlet, 39 Decontamination equipment, 40 Measuring equipment, 50 System piping, 51 Decontamination object, 52 Decontamination tank (surge tank), 53 Circulation pump, 54 Heater, 55 Cationic resin tower, 56 Mixed bed resin tower, 57 Organic acid decomposition unit 58. Click, 59 ‥ chemical feed pump, 60 ‥ decontamination target system, 100 ‥ shared building, 111 ‥ nuclear power plants, 112 ‥ building.

Claims (14)

Radioactive metal volume decontamination treatment that performs decontamination of radioactive metal waste and confirms that the radioactive metal waste has become non-radioactive, and equipment inspection processing that inspects equipment removed from the nuclear equipment. When the equipment or parts removed from the plant are renewed, the equipment or parts discharged from the nuclear facility can be stored in accordance with the respective radioactivity levels. A reusable product manufacturing process in which a metal waste made non-radioactive by radioactive metal volume reduction is solidified after melting and manufactured a reused product is disposed adjacent to the radiation control area of the common building. A method for treating radioactive metal waste, which is performed by a treatment facility to be formed . The method for treating radioactive metal waste according to claim 1, wherein when the reusable product manufacturing process is performed, the melted and solidified product before becoming the reusable product is stored in an unmanaged area in the common building. 2. The radioactive metal waste according to claim 1, wherein the radiation management area of the common building is a management building , and the non-management area of the common building is a non-management building that is arranged adjacent to the management building to form a non-management area . Processing method. The processing method of the radioactive metal waste of Claim 1 or 3 which uses the processing equipment movable in the said same building or the said adjacent building as said processing equipment. The processing method of the radioactive metal waste of Claim 1 or 3 which uses the processing equipment which can move to another buildings other than the said same building or the said adjacent building as said processing equipment. The radioactivity according to claim 1, wherein, in the equipment inspection process, equipment removed from a nuclear facility or a part thereof is transferred to the shared building, while equipment or a part replacing the removed equipment or part is carried in and installed on the nuclear equipment side. Metal waste disposal method. 2. The radioactive metal according to claim 1, wherein, in the equipment inspection process, when the equipment removed from the nuclear facility is updated, the equipment is removed in the common building, and the equipment replacing the equipment is carried in and installed in the nuclear equipment. Waste disposal method. The method for treating radioactive metal waste according to claim 1, wherein in the equipment inspection process, removable metals of equipment removed from the nuclear facility are decontaminated in the common building, clearance inspection is performed, and the product is processed. The method for treating radioactive metal waste according to claim 1, wherein temporary equipment used in a nuclear facility is transferred to the shared building after use, inspected, arranged and stored. The method for treating radioactive metal waste according to claim 1, wherein tools and other equipment used in inspections, modifications or other works carried out at a nuclear power plant are transferred to the shared building after use and stored. Consists of a management building that forms a radiation management area and a non-management building that is placed adjacent to this management building and forms a non-management area. The management building and the non-management building contain decontamination of radioactive metal waste. And a radioactive metal volume reduction processing system for confirming that radioactive metal waste has become non-radioactive, and a reusable product manufacturing process in which non-radioactive metal waste is solidified after melting to produce a reusable product A radioactive metal waste treatment facility characterized in that a system and an equipment inspection processing system for inspecting equipment removed from a nuclear facility for reuse are arranged. 12. The entrance / exit for connecting each other is provided in the wall surface side which the said management building and a non-management building face each other, The apparatus entrance / exit for carrying in / out an apparatus is provided in the opposite wall surface. Radioactive metal waste treatment facility. The management building has a cutting area for cutting the carried-in equipment, a decontamination area for decontaminating the cut equipment, and a measurement area for confirming that the decontaminated equipment has become non-radioactive. Item 13. A radioactive metal waste treatment facility according to item 11 or claim 12. In the non-managed building, there are a non-radioactive cutting area for cutting the non-radioactive loading equipment, a discriminating material storage area that is stored separately for each material, and a melting furnace area for melting and casting the stored material 14. The radioactive metal waste treatment facility according to claim 11, further comprising a casting area and a product processing area for processing the cast product into a product.

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