JP2020076621A - Equipment processing method of nuclear power plant - Google Patents

Abstract

To provide an equipment processing method of a nuclear power plant that can improve workability while managing a radiation exposure during dismantlement of radioactive equipment used in a pressurized-water reactor.SOLUTION: In an equipment processing method of a nuclear power plant, radioactive equipment 130 has been disposed in a controlled area A of a pressurized-water nuclear power plant 1 is dismantled in the controlled area of a boiling-water nuclear power plant 101.SELECTED DRAWING: Figure 4

Description

  The present disclosure relates to an apparatus processing method for a nuclear power plant.

  In general, a nuclear power plant using a pressurized water reactor (hereinafter, a pressurized water nuclear plant) and a nuclear plant using a boiling water reactor (hereinafter, a boiling water nuclear plant) containing a radioactive material ( After that, the radioactive equipment) is removed during maintenance or decommissioning, and is processed such as dismantling while suppressing the scattering of radioactive materials. Various studies have been made so far on methods of treating such radioactive devices.

  For example, Patent Document 1 discloses a method of sequentially disassembling the steam generator from above in order to disassemble the steam generator in an upright state.

Patent No. 5955173

  The dismantling of radioactive devices as described above is required to be performed within the controlled area. In this controlled area, in order to prevent the radiation exposure of workers and the surrounding public from exceeding the specified limit, work management including radiation monitoring, and management of radioactive waste discharge, discharge, etc. are strictly conducted. It is an area where it takes place. However, in the pressurized water nuclear power plant, the area divided into the control area is limited to the reactor building, auxiliary building, etc., so the dismantling work of the radioactive equipment generated in the pressurized water nuclear power plant can be performed smoothly. However, there is a problem that workability is reduced.

  Therefore, an object of at least one embodiment of the present disclosure is, in view of the above circumstances, when dismantling a radioactive device used in a pressurized water nuclear reactor, while managing radiation exposure, while maintaining the workability of a nuclear plant capable of improving workability. An object of the present invention is to provide a device processing method.

(1) A device processing method for a nuclear power plant according to some embodiments of the present invention is
Radioactive equipment located in the controlled area of a pressurized water nuclear plant is dismantled in the controlled area of a boiling water nuclear plant.

  Generally, the controlled area of a boiling water nuclear power plant is larger than the controlled area of a pressurized water nuclear power plant. According to the method of (1) above, since the dismantling work of the radioactive equipment arranged in the control area of the pressurized water nuclear power plant is performed in the management area of the boiling water nuclear power plant, it is dismantled in a wider management area. It becomes possible to perform work. Therefore, the workability of the disassembling work can be improved while controlling the radiation exposure during the disassembling work.

(2) In some embodiments, in the method of (1) above,
The controlled area of the pressurized water nuclear power plant includes a controlled area in the reactor building of the pressurized water nuclear power plant.

  Since cooling water containing radioactive substances circulates in the reactor building of the pressurized water nuclear power plant, the equipment arranged in the reactor building contains radioactive substances. According to the method of (2) above, since the dismantling of the radioactive equipment placed inside the reactor building of the pressurized water nuclear power plant is performed within the control area of the boiling water nuclear power plant, radiation exposure is managed at the time of dismantling. At the same time, the workability of disassembling can be improved.

(3) In some embodiments, in the above method (1) or (2),
The radioactive device includes a steam generator.

  The steam generator of a pressurized water nuclear plant is a large piece of equipment that can be replaced regularly with new ones. Along with the replacement work of the steam generator, a management area is required as a dismantling site for the existing steam generator. In this respect, according to the above method (3), since the steam generator can be disassembled by utilizing the large management area of the boiling water nuclear power plant, the replacement work of the steam generator can be smoothly performed.

(4) In some embodiments, in any one of the above methods (1) to (3),
The controlled area of the boiling water nuclear power plant includes a controlled area in a turbine building of the boiling water nuclear power plant.

  The control area of the boiling water nuclear power plant includes the control area of the reactor building as well as the control area of the turbine building. Compared to the reactor building, the turbine building often has fewer structures, and it is easier to secure a large space. Therefore, according to the above method (4), workability can be further improved when disassembling the radioactive device disposed in the controlled area of the pressurized water nuclear power plant.

(5) In some embodiments, in any one of the methods (1) to (4) above,
A step of taking out the radioactive device from the controlled area of the pressurized water nuclear plant;
A transportation step of transporting the radioactive device taken out of the controlled area of the pressurized water nuclear power plant into the controlled area of the boiling water nuclear power plant,
And a disassembling step of dismantling the radioactive device transported in the controlled area of the boiling water nuclear power plant in the controlled area of the boiling water nuclear power plant.

  According to the above method (5), the taken out radioactive device can be transported to the boiling water nuclear power plant, and the dismantling work can be performed in the management area of the boiling water nuclear power plant. Therefore, it is possible to improve the workability of disassembling while controlling the radiation exposure when disassembling the radioactive device by using the existing equipment.

(6) In some embodiments, in the above method (5),
The method further includes a temporary storage step of storing the radioactive device in a temporary storage facility for a certain period of time after the extraction step and before the transportation step.

  According to the above method (6), by storing the radioactive device before the dismantling in the temporary storage facility, the radioactive device can be newly taken out from the pressurized water nuclear plant without waiting for the completion of the dismantling of the radioactive device.

(7) In some embodiments, in the method of (5) or (6) above,
Before the extraction step, the method further includes an operation step of operating the radioactive device and an operation stop step of stopping the operation of the radioactive device.

  According to the method of (7) above, when exchanging or discarding a radioactive device after use, that is, a radioactive device that has undergone the operation process and the operation stop process, the radioactive device is transported to a boiling water nuclear power plant to generate boiling water. The dismantling work can be performed in the controlled area of the nuclear power plant.

(8) In some embodiments, in any one of the above methods (1) to (7),
The controlled area of the boiling water nuclear power plant includes the controlled area of the boiling water nuclear power plant which is out of operation.

  According to the above method (8), the boiling water type nuclear power plant that is out of operation can be effectively used to manage the radiation exposure during dismantling and be placed in the pressurized water nuclear power plant management region. It is possible to smoothly dismantle the used radioactive equipment.

  According to at least one embodiment of the present invention, it is possible to provide a device processing method for a nuclear power plant capable of improving workability while managing radiation exposure when dismantling a radioactive device used in a pressurized water reactor.

It is a typical sectional view showing the whole pressurized water nuclear power plant composition concerning one embodiment. It is a typical sectional view showing the whole boiling water nuclear power plant composition concerning one embodiment. 6 is a flowchart of a device processing method according to an embodiment. It is a figure explaining the flow of the apparatus processing method which concerns on one Embodiment and the modification of one Embodiment. It is a flowchart of the apparatus processing method which concerns on the modification of one Embodiment.

Hereinafter, some embodiments of the present invention will be described with reference to the accompanying drawings. However, the dimensions, materials, shapes, relative positions, etc. of the components described as the embodiments or shown in the drawings are not intended to limit the scope of the present invention thereto, but are merely illustrative examples. Absent.
FIG. 1 is a schematic cross-sectional view showing the overall configuration of a pressurized water nuclear power plant according to an embodiment. FIG. 2 is a schematic cross-sectional view showing the overall configuration of the boiling water nuclear power plant according to the embodiment.

  In the device treatment method according to one embodiment, the radioactive device that has been arranged in the controlled area of the pressurized water nuclear power plant 1 (Fig. 1) is dismantled in the controlled area of the boiling water nuclear power plant 101 (Fig. 2).

As shown in FIG. 1, the pressurized water nuclear power plant 1 includes a reactor facility 3 and a turbine facility 33.
The nuclear reactor equipment 3 includes a nuclear reactor 2, a primary cooling loop 10, a pressurizer 14, a steam generator 16, and a reactor containment vessel 50.

  The nuclear reactor 2 generates thermal energy by a fission reaction. The reactor 2 includes a reactor vessel 11, fuel rods 12, control rods 13, and other reactor internals (not shown). The reactor vessel 11 is a pressure vessel that houses the fuel rods 12, the control rods 13, and other reactor internals. The fuel rod 12 contains a nuclear fuel in pellet form (for example, uranium fuel or MOX fuel). The control rod 13 absorbs neutrons generated in the core containing nuclear fuel and adjusts the number of neutrons to control the reactor output.

The primary cooling loop 10 forms a flow path between the reactor vessel 11 and the steam generator 16 to circulate primary cooling water that is a heat medium. The primary cooling loop 10 has a primary cooling pump 18 for circulating the primary cooling water.
The pressurizer 14 pressurizes the inside of the primary cooling loop 10 so that the primary cooling water does not boil. The pressurizer 14 is connected so as to branch from the primary cooling loop 10, for example.

  The steam generator 16 heat-exchanges the secondary cooling water flowing through the turbine equipment 33 with the primary cooling water circulating through the primary cooling loop 10 to heat the secondary cooling water to generate steam.

  The reactor containment vessel 50 stores the reactor 2, the primary cooling loop 10, the pressurizer 14, and the steam generator 16 described above, respectively. The reactor containment vessel 50 is a pressure-resistant container made of concrete or the like, and even if the radioactive substance leaks from the reactor vessel 11, this radioactive substance can be contained inside. The reactor containment vessel 50 of the pressurized water nuclear power plant 1 according to this embodiment also serves as a reactor building. In other words, the reactor containment vessel 50 is formed integrally with the reactor building.

  The pressurized water nuclear power plant 1 may be provided with an auxiliary building (not shown) adjacent to the reactor containment vessel 50. In this auxiliary building, there are generally provided a central control room for operating the pressurized water nuclear power plant 1, a fuel handling room for exchanging nuclear fuel in the reactor 2, a fuel pit for storing the nuclear fuel in water, and the like. Be done.

The turbine equipment 33 converts the thermal energy generated in the nuclear reactor 2 into rotational energy and uses it. The turbine equipment 33 of the present embodiment further converts rotational energy into electric energy.
The turbine equipment 33 includes a steam turbine 22, a generator 24, a secondary cooling loop 20, a condenser 21, a low pressure feed water heater 26, a deaerator 27, a high pressure feed water heater 29, and a turbine building. 51 is provided.

  The steam turbine 22 converts the thermal energy of the steam supplied from the steam generator 16 into rotational energy. In other words, the steam turbine 22 is driven by steam to rotate the rotating shaft. The rotating shaft of the steam turbine 22 is connected to the rotor of the generator 24, and the rotor of the generator 24 rotates to generate electric power.

  The secondary cooling loop 20 forms a flow path between the steam generator 16 and the steam turbine 22 for circulating the secondary cooling water that is a heat medium. The secondary cooling loop 20 has a condensate pump 25 and a water supply pump 28 that circulate the secondary cooling water. The condensate pump 25 and the water supply pump 28 allow secondary cooling water to circulate between the steam generator 16 and the steam turbine 22.

  The condenser 21, the low-pressure feed water heater 26, the deaerator 27, and the high-pressure feed water heater 29 are arranged downstream of the steam turbine 22 in the secondary cooling loop 20, respectively. The condenser 21, the low-pressure feed water heater 26, the deaerator 27, and the high-pressure feed water heater 29 sequentially condense and heat the steam that has worked in the steam turbine 22. The secondary cooling water that has passed through the condenser 21, the low-pressure feed water heater 26, the deaerator 27, and the high-pressure feed water heater 29 returns to the steam generator 16.

  The turbine building 51 includes the above-described steam turbine 22, part of the secondary cooling loop 20, the condenser 21, the low-pressure feed water heater 26, the deaerator 27, the high-pressure feed water heater 29, and the generator. 24 and the like are stored. The turbine building 51 is arranged adjacent to the reactor containment vessel 50.

  Here, in general nuclear power plants including the pressurized water nuclear power plant 1 of the present embodiment, a control area is provided in order to prevent the radiation exposure of workers and the public around the limit from exceeding a predetermined limit. This controlled area limits access to people. In the controlled area, in order to safely carry out various operations such as operation, inspection, and maintenance of the nuclear reactor, work management including radiation monitoring and management of radiating and discharging radioactive waste are strictly performed. .. Equipment located in controlled areas is called radioactive equipment. When dismantling radioactive equipment due to decommissioning or maintenance, disassembly within the controlled area is required.

  In the pressurized water nuclear power plant 1 as in the present embodiment, the inside of the reactor containment vessel 50 is the management area A, and the inside of the turbine building 51 is the non-management area B. That is, in the pressurized water nuclear power plant 1, the reactor 2, the steam generator 16, the pressurizer 14, and the like are radioactive devices. When the radioactive equipment is dismantled on the premises of the pressurized water nuclear power plant 1, since the control area A of the pressurized water nuclear power plant 1 is small, a building for dismantling treatment of the radioactive equipment other than the reactor containment vessel 50. It will be necessary to establish a separate area and make it a controlled area.

The entire pressurized water nuclear power plant 1 is divided into a conservation area C and is separately managed. The maintenance area C is a place that requires special management for the maintenance of the nuclear reactor facility and is an area other than the management area.
For example, in the auxiliary building (not shown) of the pressurized water nuclear power plant 1, since water containing radioactive substances circulates or is stored, a part thereof is included in the controlled area A. On the other hand, even in the auxiliary building, areas such as the central control room that do not contain radioactive substances are classified as non-controlled areas B.

As shown in FIG. 2, the boiling water nuclear power plant 101 includes the nuclear reactor equipment 103 and the turbine equipment 133, like the pressurized water nuclear power plant 1 described above.
The nuclear reactor facility 103 includes a nuclear reactor 102, a nuclear reactor containment vessel 150, and a nuclear reactor building 160.
The nuclear reactor 102 generates thermal energy by a nuclear fission reaction, and the thermal energy causes the cooling water to boil to generate steam. The nuclear reactor containment vessel 150 stores the nuclear reactor 102, and even if the radioactive substance leaks from the nuclear reactor 102, the radioactive substance can be contained inside. The reactor building 160 houses the reactor containment vessel 150. The reactor building 160 is provided with facilities such as a spent fuel pool.

  The turbine equipment 133 converts thermal energy generated in the nuclear reactor 102 into rotational energy and uses the rotational energy. The turbine equipment 133 of the present embodiment, like the turbine equipment 33 described above, further converts rotational energy into electric energy. The turbine equipment 133 includes a cooling loop 110, a steam turbine 122, a generator 124, a condenser 121, and a turbine building 151.

The cooling loop 110 forms a flow path between the nuclear reactor 102 and the steam turbine 122 to circulate cooling water as a heat medium. The cooling loop 110 includes a water supply pump 125 that circulates cooling water.
The steam turbine 122 converts the thermal energy of water vapor into rotational energy, similar to the steam turbine 22 described above. The generator 124 is connected to the steam turbine 122 and is driven by the steam turbine 122. The steam that has worked in the steam turbine 122 is condensed by the condenser 121 and returned to the nuclear reactor 102.

The turbine building 151 stores the steam turbine 122, a part of the cooling loop 110, the condenser 121, the generator 124, and the like. The turbine building 151 is arranged adjacent to the reactor building 160.
That is, the boiling water nuclear power plant 101 includes all of the pressurizer 14, the steam generator 16, the primary cooling loop 10, and other devices that are housed in the reactor containment vessel 50 of the pressurized water nuclear power plant 1. Not not.

  In the boiling water nuclear power plant 101, the cooling water of the nuclear reactor 102 is in a state of containing a radioactive substance, for example, by activating the cladding. Therefore, in the boiling water nuclear power plant 101, it is necessary to strictly manage radiation exposure even in the vicinity of the steam turbine 122 that uses cooling water. Therefore, the inside of the turbine building 51 of the pressurized water nuclear power plant 1 is the non-management area B, but the inside of the turbine building 151 of the boiling water nuclear power plant 101 is the management area A. That is, in the boiling water nuclear power plant 101, both the reactor building 160 and the turbine building 151 are the management area A, and generally the management area A is wider than the pressurized water nuclear power plant 1. Note that, like the pressurized water nuclear power plant 1, the entire boiling water nuclear power plant 101 is divided into the maintenance area C and is separately managed.

Hereinafter, the device processing method according to the embodiment will be described with reference to FIGS. 3 and 4. FIG. 3 is a flowchart of a device processing method according to an embodiment and a modification of the embodiment. FIG. 4 is a diagram illustrating a flow of the device processing method according to the embodiment.
As shown in FIG. 3, the device processing method of this embodiment includes an operation step (step S1), an operation stop step (step S3), an extraction step (step S5), a transportation step (step S7), and disassembly. The process (step S9) and the process (step S11) are included.

  In the operation process (step S1), the pressurized water nuclear power plant 1 is operated to generate power. By going through this operating state, the equipment of the steam generator 16 arranged inside the reactor containment vessel 50 becomes the radioactive equipment 130 (see FIG. 4) containing the radioactive material. In the following description, the case where the radioactive device 130 is the steam generator 16 will be described as an example. The radioactive device 130 may be a device other than the steam generator 16.

  In the operation stop step (step S3), the pressurized water nuclear power plant 1 in the operating state is stopped. Then, the steam generator 16 is brought into a state of being removed from the primary cooling loop 10 and the secondary cooling loop 20. The steam generator 16 may be covered with a sheet or the like.

  In the take-out step (step S5), the steam generator 16 is taken out from the control area A of the pressurized water nuclear power plant 1. In this take-out step (step S5), for example, an opening of a size that allows the steam generator 16 to pass through is provided above the reactor containment vessel 50. Then, the steam generator 16 is lifted by using a large-sized lifting machine or the like arranged outside the reactor containment vessel 50. Further, the steam generator 16 is taken out of the reactor containment vessel 50 through the opening.

  In the transportation step (step S7), the steam generator 16 taken out of the reactor containment vessel 50 is loaded on a transportation ship or a large vehicle. Then, as shown in FIG. 4, the water is transported to a boiling water nuclear power plant 101 located in a different place from the pressurized water nuclear power plant 1 via a sea route, a land route, or the like. Further, the steam generator 16 transported to the boiling water nuclear power plant 101 is carried into the management area A of the boiling water nuclear power plant 101. In this embodiment, the steam generator 16 is carried into the turbine building 151. At this time, the steam generator 16 may be carried in using an existing carry-in / carry-out port or the like without newly forming an opening or the like in the turbine building 151.

  In the dismantling process (step S9), the steam generator 16 is dismantled in the control area A of the turbine building 151. This dismantling work is performed using dismantling equipment such as a robot and a cutting device. As the dismantling equipment, existing equipment may be used in the boiling water nuclear power plant 101, or new dismantling equipment may be provided before the dismantling step. The boiling water nuclear power plant 101 that performs the dismantling step of the present embodiment is the boiling water nuclear power plant 101 that is not in operation, but is not limited to this. Here, the operation stopped state means that the operation has been terminated for the purpose of decommissioning the boiling water nuclear power plant 101, or that the operation has been temporarily stopped for repair work or investigation. including.

  In the processing step (step S11), in the management area A of the turbine building 151, the waste material that has been disassembled from the steam generator 16 is decontaminated, and then is disposed in a shielding container. By this waste disposal treatment, when the dismantled waste is transported outside the controlled area A, leakage of radioactive material can be suppressed. The demolition waste processed by this treatment process is stored in a predetermined storage area (not shown) on the plant site for a certain period of time, and then transported to a buried facility (not shown) installed outside the plant site. And buried. The storage area described above may be provided within the premises of the pressurized water nuclear power plant 1 or within the premises of the boiling water nuclear power plant 101. As the storage area, for example, the space of the management area A of the turbine building 151 in which the dismantling process is performed may be used.

(Operation effect of one embodiment)
In the equipment treatment method of the above-described embodiment, the radioactive equipment 130 arranged in the management area A of the pressurized water nuclear power plant 1 is disassembled in the management area A of the boiling water nuclear power plant 101.
The management area A of the boiling water nuclear power plant 101 is wider than the management area A of the pressurized water nuclear power plant 1 because it includes the reactor building 160 and the turbine building 151. Therefore, the dismantling work of the steam generator 16 (radioactive device 130) arranged in the control area A of the pressurized water nuclear power plant 1 can be performed in the control area A of the wider boiling water nuclear power plant 101. Therefore, it is possible to improve the workability of the disassembling work while managing the radiation exposure during the disassembling.

In the device treatment method of one embodiment, the controlled area A of the pressurized water nuclear power plant 1 includes the controlled area A in the reactor containment vessel 50.
Since the primary cooling water containing the radioactive substance circulates in the reactor containment vessel 50 of the pressurized water nuclear power plant 1, the equipment arranged in the reactor containment vessel 50 contains the radioactive substance. However, since the dismantling of these radioactive devices 130 is performed within the management area A of the boiling water nuclear power plant 101, it is possible to improve the workability of dismantling while managing radiation exposure during dismantling.

In the device treatment method of one embodiment, the radioactive device 130 is the steam generator 16.
The steam generator 16 of the pressurized water nuclear power plant 1 is a large device that may be periodically replaced with a new one for the purpose of improving performance such as output. Therefore, it becomes difficult to secure a large management area A, which is a dismantling place of the existing steam generator 16 in the pressurized water nuclear power plant 1, due to the replacement work of the steam generator 16. In this case, the dismantling work does not go smoothly, many steam generators 16 waiting for dismantling are generated, and there is no space for temporary storage although the steam generator 16 needs to be removed. The replacement work itself may be hindered. In this respect, according to the equipment treatment method of one embodiment, by dismantling the steam generator 16 by effectively utilizing the management area A of the boiling water nuclear power plant 101, workability of dismantling can be improved, and the steam generator can be improved. The replacement work of 16 can be performed smoothly.

  As described above, since the steam generator 16 of the pressurized water nuclear power plant 1 needs to be replaced regularly, it is often designed to withstand long-distance transportation. For example, a drop test or the like is performed, and it is made so as not to be easily deformed even when dropped due to its strength. Therefore, when the radioactive device 130 is the steam generator 16, when the radioactive device 130 is transported to the boiling water nuclear power plant 101 which is located away from the pressurized water nuclear power plant 1 or the temporary storage facility 140, it may withstand impact, drop, or the like. It is advantageous in that it can be done.

In the device processing method of one embodiment, the management area A of the boiling water nuclear power plant 101 is the management area A in the turbine building 151.
In general, the turbine building 151 often has a smaller number of structures arranged than the reactor building 160, and it is easy to secure a large space. Therefore, according to the present embodiment, workability can be further improved when disassembling the radioactive device 130 arranged in the management area A of the pressurized water nuclear power plant 1.

In the device processing method of one embodiment, the extraction step of extracting the radioactive device 130 from the management area A of the pressurized water nuclear power plant 1 (step S5), and the extraction of the radioactive device 130 in the management area A of the boiling water nuclear power plant 101. It includes a transportation step (step S7) of transporting the radioactive material to the boiling water type nuclear plant 101 in the controlled area A (step S9).
According to this embodiment, the taken out radioactive device 130 can be transported to the boiling water nuclear power plant 101, and the dismantling work can be performed in the management area A of the boiling water nuclear power plant 101. Therefore, even if the controlled area A of the pressurized water nuclear power plant 1 does not have a desired area for performing the disassembling operation of the radioactive device 130, the dismantling process is performed while managing the radiation exposure during the dismantling of the radioactive device 130. The workability of can be improved. Further, in order to expand the controlled area A in the pressurized water nuclear power plant 1, it is not necessary to make the non-controlled area B a new controlled area, so that the cost for making the controlled area can be reduced.

In the device processing method of one embodiment, before the extraction process (step S5), an operation process (step S1) for operating the radioactive device 130 and an operation stop process (step S3) for stopping the operation of the radioactive device 130 are performed. Contains.
According to the present embodiment, when exchanging or discarding the radioactive device 130 containing the radioactive substance after the operation stop, the radioactive device 130 is transported to the boiling water nuclear power plant 101, and the boiling water nuclear power plant 101 is managed. The dismantling work can be performed in the area A.

In the device processing method of one embodiment, the management area A of the boiling water nuclear power plant 101 includes the management area A of the boiling water nuclear power plant 101 which is out of operation.
According to the present embodiment, the controlled area A of the boiling water nuclear power plant 101, which has stopped operating, is effectively utilized to manage the radiation exposure at the time of dismantling, while the controlled area A of the pressurized water nuclear power plant 1 is controlled. The installed radioactive device 130 can be disassembled smoothly.

(Modification of one embodiment)
FIG. 5 is a flowchart of a device processing method according to a modified example of the embodiment.
In the transportation step (step S7) of the above-described embodiment, the radioactive device 130 was transported from the pressurized water nuclear power plant 1 to the boiling water nuclear power plant 101. However, for example, like the device processing method according to the modified example of the embodiment shown in FIG. 5, the temporary storage step (step S6) is performed between the extraction step (step S5) and the transportation step (step S17). You may do it.
In the device processing method of this modified example, the operation process (step S1), the operation stop process (step S3), and the removal process (step S5) are performed as in the above-described embodiment, and then the temporary storage process (step S6). )I do.

  In the temporary storage step (step S6), the radioactive device 130 is transported to the temporary storage facility 140 and stored for a certain period of time, as indicated by a dashed arrow in FIG. The temporary storage facility 140 is capable of temporarily storing a plurality of radioactive devices 130 at the same time. In the transportation step (step S17) of the present modification, the radioactive device 130 stored in the temporary storage facility 140 is transported from the temporary storage facility 140 to the boiling water nuclear power plant 101, as indicated by the dashed arrow in FIG. .. Here, the temporary storage facility 140 may be in any location, for example, inside or outside the premises of the pressurized water nuclear power plant 1. The transportation step (step S17) is different from the transportation step (step S7) of the above-described embodiment only in the transportation start point. In this modified example, thereafter, similarly to the above-described embodiment, the disassembling process (step S9) and the processing process (step S11) are performed.

(Operation and effect in modified example of one embodiment)
In the modified example of the embodiment, after the extraction step (step S5) and before the transportation step (step S7), a temporary storage step (step S6) of storing the radioactive device 130 in the temporary storage facility 140 for a certain period is further added. Contains.
According to the modified example of the present embodiment, since the radioactive device 130 before dismantling can be stored in the temporary storage facility 140, the radioactive device 130 is newly taken out from the pressurized water nuclear power plant 1 without waiting for the dismantling of the radioactive device 130 to be completed. be able to.

(Other embodiments)
Although one embodiment of the present disclosure has been described above, the present disclosure is not limited to the above-described embodiment, and includes a modified form of the above-described embodiment and a combination of these forms as appropriate. ..
In the embodiment, the steam generator 16 is described as an example of the radioactive device 130, but the radioactive device 130 of the present invention is not limited to the steam generator 16. Any device may be used as long as it is a device included in the controlled area A of the pressurized water nuclear power plant 1, and may be, for example, the pressurizer 14 arranged in the reactor containment vessel 50 or a tank in the auxiliary building.

  In one embodiment, a case has been described in which the radioactive device 130 is transported from one pressurized water nuclear power plant 1 or one temporary storage facility 140 to one boiling water nuclear power plant 101 to be dismantled. However, the radioactive device 130 is transported from the plurality of pressurized water nuclear power plants 1 or the plurality of temporary storage facilities 140 to one boiling water nuclear power plant 101 for dismantling, or the plurality of radioactive devices included in one pressurized water nuclear power plant 1 are disposed. The equipment 130 and the radioactive equipment 130 temporarily stored in one temporary storage facility 140 may be transported to different boiling water nuclear power plants 101 and disassembled. Further, the radioactive devices 130 of the plurality of pressurized water nuclear power plants 1 may be collected in one temporary storage facility 140 and temporarily stored.

In the present specification, the expression indicating relative or absolute arrangement is not limited to such an arrangement strictly, and is relatively displaced by relative tolerance or an angle or distance at which the same function can be obtained. It also indicates the state of being present.
The expression that things are in the same state not only means that they are in exactly the same state, but also that there is a tolerance or a state in which there is a difference such that the same function can be obtained.
Further, in the present specification, the expression representing a shape not only represents a shape in a geometrically strict sense, but also represents a shape including an uneven portion, a chamfered portion, etc. within a range in which the same effect can be obtained. To do.
In this specification, the expressions “comprising”, “including”, or “having” one element are not exclusive expressions excluding the existence of other elements.

1 Pressurized Water Nuclear Power Plant 2,102 Reactor 10 Primary Cooling Loop 11 Reactor Vessel 12 Fuel Rod 13 Control Rod 14 Pressurizer 16 Steam Generator 18 Primary Cooling Pump 20 Secondary Cooling Loop 21,121 Condenser 22,122 Steam Turbine 24,124 Generator 25 Condensate pump 26 Low-pressure feed water heater 27 Deaerator 28 Water feed pump 29 High-pressure feed water heater 50,150 Reactor containment vessel 51,151 Turbine building 101 Boiling water nuclear plant 110 Cooling loop 125 Feed water Pump 130 Radioactive equipment 160 Reactor building A Control area B Non-control area C Conservation area

Claims (8)

  A method for treating equipment in a nuclear power plant, in which radioactive equipment that has been placed in the controlled area of a pressurized water nuclear power plant is disassembled in the controlled area of a boiling water nuclear power plant.   The method for treating equipment of a nuclear power plant according to claim 1, wherein the controlled area of the pressurized water nuclear power plant includes a controlled area in a reactor building of the pressurized water nuclear power plant.   The said radioactive device is an apparatus processing method of the nuclear power plant of Claim 1 or 2 containing a steam generator.   The equipment processing method for a nuclear power plant according to any one of claims 1 to 3, wherein the management area of the boiling water nuclear power plant includes a management area in a turbine building of the boiling water nuclear power plant. A step of taking out the radioactive device from the controlled area of the pressurized water nuclear plant;
A transportation step of transporting the radioactive device taken out of the controlled area of the pressurized water nuclear power plant into the controlled area of the boiling water nuclear power plant,
The dismantling step of dismantling the radioactive device within the management area of the boiling water nuclear power plant, the device processing method of the nuclear power plant according to any one of claims 1 to 4.   The apparatus treatment method for a nuclear power plant according to claim 5, further comprising a temporary storage step of storing the radioactive equipment in a temporary storage facility for a certain period of time after the extraction step and before the transportation step.   7. The equipment processing method for a nuclear power plant according to claim 5, further comprising, before the extraction step, an operation step of operating the radioactive equipment and an operation stop step of stopping the operation of the radioactive equipment.   The method for treating equipment of a nuclear power plant according to any one of claims 1 to 7, wherein the management area of the boiling water nuclear power plant is a management area of the boiling water nuclear power plant that is not in operation.

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