JP2004037231A - Reconditioning component discrimination method, component manufacturing method, component reconditioning system and shaft seal - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide a component reconditioning system capable of sufficient confirmation test with an external reconditioning equipment by providing the equipment outside a nuclear power station. <P>SOLUTION: In a nuclear power station 1, when replaced components are carried in a decontamination factory 14, they are separated into decontamination available components, decontamination unnecessary components and decontamination improper components. After decontaminating the decontamination available components, they are carried out to an external reconditioning firm 2 together with the contamination unnecessary components. In the reconditioning factory 23 in the firm 2, dimensions of the introduced decontamination available components and the decontamination unnecessary components are measured and reconditioning process is applied to the components classified in reconditioning available. Then, the reconditioning-processed components and deficient components newly manufactured in a production factory 22 are assembled and carried to the power station 1. <P>COPYRIGHT: (C)2004,JPO

Description

[0001]
TECHNICAL FIELD OF THE INVENTION
The present invention relates to a component recycling system for recycling components used in facilities handling radioactive waste such as a nuclear power plant, and particularly to a feedwater pump, a boiler circulation pump, a cooling water pump, and a recirculation pump. The present invention relates to a component recycling system for recycling each component in a shaft seal applied in, for example, the invention.
[0002]
[Prior art]
In a nuclear power plant, a primary coolant pump that circulates a primary coolant is used to transfer thermal energy generated in a nuclear reactor to a steam generator. The primary coolant pump is provided with a shaft seal for preventing the primary coolant from leaking from the shaft to the outside. And since the O-ring provided as one of the parts in this shaft seal has a life, conventionally, when the life of the O-ring is confirmed, the entire shaft seal is replaced, and the old shaft seal is converted into radioactive waste. Had been discarded.
[0003]
As described above, conventionally, the shaft seal provided in the primary coolant pump has been treated as a consumable, but in recent years, such a consumable has been used as a consumable for the purpose of reducing waste disposal costs and effectively using resources. Consideration is being given to the reuse of treated radioactive waste. As one of the methods of reusing the radioactive waste, a method of exchanging an O-ring of a shaft seal in which each part has been radioactively contaminated in a nuclear power plant and regenerating the same is used. At this time, it is not necessary to discard the entire shaft seal, and most of the components constituting the shaft seal can be reused.
[0004]
[Problems to be solved by the invention]
As described above, when the O-ring is replaced in the nuclear power plant to regenerate the shaft seal, the recycling process can be performed without moving the radioactively contaminated parts to the outside of the power plant. It is necessary to set up a regeneration factory for regenerating the shaft seal and a test factory for confirming the operation of the regenerated shaft seal before mounting it on the pump. However, such a test plant needs to perform various tests of high temperature and high pressure for the operation check test of the shaft seal, so that the scale of the test equipment becomes large.
[0005]
As described above, in order to install a regeneration facility in a nuclear power plant, not only a regeneration plant but also a test plant having a large facility scale is required, and the installation place for the original power generation facility is limited. Also, in the above description, an example was given in which a regeneration factory and a test factory for laying down shaft seals were laid, but similar regeneration factories and test factories were required for other parts, and the scale was large. Become. Therefore, it is inefficient to provide a regeneration facility that is used only periodically in a nuclear power plant with a limited site area.
[0006]
In view of such a problem, an object of the present invention is to provide a component recycling system in which a recycling facility is provided outside a nuclear power plant and a sufficient confirmation test can be performed by an external recycling facility. It is another object of the present invention to provide a component manufacturing method and a recycled component sorting method in the component recycling system. It is a further object of the present invention to provide a shaft seal regenerated or manufactured by the part regenerating system.
[0007]
[Means for Solving the Problems]
In order to achieve the above object, the method for separating recycled parts according to claim 1 is used when a used part in a radiation generating facility which is a radioactively contaminated environment is disassembled into a plurality of constituent parts constituting the used part. According to the method for separating each component into a reproducible component and a non-reproducible component, the regenerating process is obviously not performed in the radiation generating facility due to the structure and properties of the components. A first step of disposing of the non-renewable parts that are possible as radioactive waste, and a second step of measuring the dose of radioactivity for each of the first components excluding the non-renewable components among the components. Step, the decontamination-impossible part having a portion in which the dose of the radioactivity is in a range that cannot be carried out to the outside and which is difficult to decontaminate due to its structure and properties. A third step of discarding as waste, and a decontamination treatment of the second component excluding the non-decontamination-removable part of the first component is within a range in which the dose of the radioactivity can be carried out to the outside; And a fourth step of separating the component into a component that does not need to be decontaminated and a component that can be easily decontaminated due to its structure and properties while the radiation dose is in a range that cannot be carried out to the outside. By performing decontamination processing on the decontaminated parts, the decontaminated parts are separated as recyclable parts together with the decontamination unnecessary parts.
[0008]
At this time, in the first step, for example, when the used component is a shaft seal, a component that cannot be used beyond the service life caused by the material, such as an O-ring that is one of the components, Structures that use ceramics that are difficult to decontaminate because radioactive contamination is significant or that radioactive substances enter into the micropores on the surface, or carbon that is difficult to regenerate due to large wear on the sliding parts Parts and components that lose their functions when disassembled, such as cup washers, are discarded as first decontamination-impossible parts. In step 3, components that cannot be decontaminated because the internal thread portion is thin and does not penetrate or has a complicated configuration are discarded as second decontamination-impossible components.
[0009]
In such a method for separating recycled components, as described in claim 2, in the third step, for a component whose radioactivity dose measurement cannot be performed after completion of the decontamination process due to its structure and properties. Are also considered as non-decontaminated parts and discarded as radioactive waste.
[0010]
In addition, as described in claim 3, the decontamination-removable parts and the decontamination unnecessary parts which are classified as reproducible in the radiation generating facility are carried out to a parts company that manufactures parts, and the parts company is provided with the parts. By measuring the dimensions of the decontamination-removable part and the decontamination-necessary part, it is determined whether or not the decontamination-removable part can be incorporated after the reprocessing. Separate unnecessary dyeing parts as recyclable parts.
[0011]
At this time, by performing dimensional measurement on the decontamination-removable parts and decontamination unnecessary parts that are brought into the parts company and subjected to reprocessing, after performing reprocessing such as lapping of the surface and cutting of the internal thread part It is determined whether or not it can be incorporated at the time of reproduction to the original used part.
[0012]
Further, in the component manufacturing method according to claim 4, in the component manufacturing method for manufacturing a used component in a radiation generating facility which is an environment contaminated with radioactivity, the use of the component having a service life that has passed in the radiation generating facility is performed. A first step of decontaminating, in the radiation generating facility, a first component that has been determined to be capable of decontamination to remove a radioactively contaminated portion of a plurality of components constituting the component; And carrying out the second step of unloading the first component to a parts company that manufactures the component. By measuring the dimensions of the first component at the parts company, it can be determined whether the component can be incorporated after reprocessing. A third step of determining whether or not the second component part of the first component part that can be incorporated is reworked, and a second step of the used component part. Components A fifth step of newly manufacturing the third component part, a sixth step of assembling the second component part and the third component part, and the performance of the used part assembled and reproduced in the sixth step And a seventh step of performing a confirmation test, whereby the used component is manufactured.
[0013]
At this time, the first component obtained by performing the decontamination process until the radiation dose reaches a range that can be carried out outside in a radiation generating facility such as a nuclear power plant is carried out to a parts company. Then, after the used component is regenerated by incorporating the first component in the component company, a performance confirmation test for checking whether or not the used component operates normally is performed.
[0014]
In such a component manufacturing method, as described in claim 5, in the second step, a component whose radiation dose is within a range capable of being carried out to the outside is defined as a first component and the first step is excluded. It is carried out to the parts company without performing dyeing processing.
[0015]
According to a sixth aspect of the present invention, there is provided a shaft seal for sealing a main shaft in a pump, wherein the shaft seal is manufactured by the component manufacturing method according to the fourth or fifth aspect.
[0016]
Also, in the component recycling system according to claim 7, in the component recycling system for recycling used components in a radiation generating facility that is an environment contaminated with radioactivity, it is determined that the used life of the used components has elapsed from the usage status. Upon confirmation, in the radiation generating facility, the used parts are replaced, and among the plurality of constituent parts constituting the replaced used parts, a decontamination process for removing a radioactively contaminated part is possible. The determined components are decontaminated and the decontamination process is not possible if the decontamination process is not necessary if the amount of radioactive contamination is within the range that can be carried out to the outside. The separated components are separated as non-decontaminated parts, the non-decontaminated parts are discarded as radioactive waste, the decontaminated parts are decontaminated, and the decontaminated decontaminated parts and the decontaminated parts are decontaminated. Unnecessary part Is carried out to a parts company that performs parts recycling, and the parts company performs dimensional measurement of the decontaminated parts and the decontamination unnecessary parts carried in from the radiation generating facility, and can be incorporated after the reprocessing. It is determined whether or not there is, and among the decontamination-removable parts and the decontamination-free parts, the third component that is determined to be able to be incorporated is reprocessed, and among the components of the used part, the third component is used. By newly manufacturing a second component other than the three components and assembling the third component and the fourth component, the used component is reproduced, and a performance confirmation test of the reproduced used component is performed. The used parts determined to be good are carried out to the radiation generating facility, the used parts reproduced by the parts company carried into the radiation generating facility are temporarily stored, and the used parts are replaced later. Characterized in that it treated as a replacement part.
[0017]
At this time, when the radiation generating facility is a nuclear power plant, the decontamination plant and the used parts are destocked inside the nuclear power plant in addition to the power plant, which decontaminate the components used for the power plant. A storage to be stored is installed. In addition, in the parts company, besides the manufacturing plant that manufactures new used parts and the test factory that performs the performance confirmation test of the manufactured used parts, the component parts that are delivered from the nuclear power plant, which is a radiation generating facility, are recycled. A remanufacturing plant for processing is set up.
[0018]
In such a component recycling system, the service life of the used component may be confirmed by performing characteristic evaluation based on data indicating the performance of the used component, or may be confirmed when the use period has passed a predetermined period. Absent. In addition, the progress of the service life of the used parts may be managed by the radiation generating facility or by the parts company, and further, may be managed by a third party other than the radiation generating facility and the parts company. It does not matter.
[0019]
Further, as described in claim 8, when the radiation-generating facility separates each of the non-decontamination-capable component, the decontamination-capable component, and the decontamination-unnecessary component, the separation is performed according to claim 1 or 2. Each component is separated using the recycled part sorting method described above.
[0020]
A shaft seal according to a ninth aspect is a shaft seal for sealing a main shaft in a pump, wherein the shaft seal is regenerated by the component regeneration system according to the seventh or eighth aspect.
[0021]
BEST MODE FOR CARRYING OUT THE INVENTION
First, the system configuration of the component reproduction system of the present invention will be described with reference to FIG. FIG. 1 is a block diagram showing the configuration of the component reproduction system of the present invention.
[0022]
<Configuration of parts recycling system>
The component recycling system shown in FIG. 1 includes a nuclear power plant 1 having a primary coolant pump 11 as a part of a power generation system, and a component company 2 that manufactures and regenerates a shaft seal incorporated in the primary coolant pump 11. Is done. In the nuclear power plant 1, a terminal device 12 that receives operation data from the primary coolant pump 11 and evaluates the characteristics of the shaft seal, and a renewable part of the shaft seal removed from the primary coolant pump 11 A decontamination factory 13 for performing decontamination work and a storage 14 for storing various parts including a shaft seal carried in from the parts company 2 are installed.
[0023]
In the parts company 2, a server 21 that receives the evaluation of the characteristics of the shaft seal by the terminal device 12 and determines when to replace the shaft seal, a manufacturing plant 22 that newly manufactures the shaft seal, and the nuclear power plant 1 A regeneration factory 23 that regenerates the shaft seal using the components of the decontaminated shaft seal, and a test factory that performs a performance confirmation test on the shaft seal manufactured or regenerated at each of the manufacturing factory 22 and the regeneration factory 23 24 are installed.
[0024]
In the component recycling system having such a configuration, the primary coolant pump 11 in the nuclear power plant 1 has a configuration as shown in FIG. FIG. 2 is an example of a schematic configuration diagram showing the relationship between the components of the primary coolant pump 11.
[0025]
<Configuration example of primary coolant pump>
The primary coolant pump 11 in FIG. 2 includes a main shaft 31, a pump main body 32 having an impeller (not shown) to which rotation is transmitted by the main shaft 31, and a shaft seal fixed to an upper portion of the pump main body 32 and sealing the main shaft 31. A seal casing 33 provided therein, a motor 34 installed above the seal casing 33 and rotating the main shaft 31, a suction pipe 35 connected to a suction port 32 a provided at a lower part of the pump body 32, And a discharge pipe 36 connected to a discharge port 32b provided on a side portion of the pump body 32.
[0026]
At this time, a shaft 34a provided in the motor 34 is coaxially connected to the main shaft 31 by a coupling 34b, and rotation from the motor 34 is provided in the pump main body 32 via the shaft 34a and the main shaft 31 (not shown). To the impeller. Then, by rotation of an impeller (not shown) in the pump body 32, the primary coolant is sucked into the suction port 32a of the pump body 32 from the suction pipe 35, and then discharged from the discharge port 32b to the discharge pipe 36.
[0027]
In order to prevent leakage of the primary coolant sucked from the suction pipe 35 and discharged from the discharge pipe 36, seal water (water sealing) is supplied from the seal injection water pipe 37 at a higher pressure than the primary coolant, and a part thereof is provided. Merges with the primary coolant via a labyrinth (not shown), and is discharged from the discharge pipe 36 together with the primary cooling water. Most of the seal water (sealing water) supplied from the seal injection water pipe 37 at a pressure higher than the primary coolant passes through the first shaft seal, is collected and circulated through the seal return pipe 38.
[0028]
Most of the seal water (sealing water) that has passed through the first shaft seal is recovered via the seal return pipe 38, but only a small part passes through the second shaft seal. Purge water is supplied from a purge water injection pipe 39 to the low pressure side of the second shaft seal, and merges with the seal water (sealing water) that has passed through the second shaft seal. Collected through.
[0029]
A small portion that is not collected through the purge water return pipe 40 passes through the third shaft seal, but is also collected through the third shaft seal leak-off pipe 41. Further, a part passes through the third shaft seal, and these are also collected through the third shaft seal leak-off pipe 41.
[0030]
<Structural example of shaft seal>
In such a primary cooling pump, a configuration example of a shaft seal provided in the seal casing 33 will be described with reference to FIGS. The shaft seal shown below is an example for explaining the component recycling system of the present invention, and may have another configuration.
[0031]
As shown in FIG. 3, inside the seal casing 33, a first shaft seal 51, a second shaft seal 52, and a third shaft seal 53 are fitted to the main shaft 31 in order from the pump body 32 side (lower side). You. The seal casing 33 includes a first shaft seal casing 33a having a first shaft seal therein, a second shaft seal casing 33b having a second shaft seal therein, and a third shaft seal having a third shaft seal therein. And a casing 33c.
[0032]
A part of the seal water (sealing water) supplied from the seal injection water pipe 37 joins the primary coolant through a labyrinth (not shown), and the remaining part (the flow indicated by an arrow a in FIG. 3). Are collected and circulated through the first shaft seal (the flow is indicated by the arrow b in FIG. 3) and through the seal return pipe 38 (the flow is indicated by the arrow C in FIG. 3). Most of the seal water (sealing water) that has passed through the first shaft seal is recovered and circulated through the seal return pipe 38 as described above, but only a small part passes through the second shaft seal (arrow in FIG. 3). D shows the flow).
[0033]
Purge water is supplied to the low pressure side of the second shaft seal from a purge water injection pipe 39 (the flow is indicated by an arrow E in FIG. 3), and the above-described seal water (water sealing) passing through the second shaft seal is After merging, most is collected via the purge water return pipe 40 (the flow is indicated by arrow F in FIG. 3). Also, the purge water supplied from a small part of the purge water injection pipe 39 and the seal water that has passed through the second shaft seal (sealing water) that is not collected via the purge water return pipe 40 passes through the third shaft seal. (The flow is indicated by an arrow G in FIG. 3), and these are also collected via the third shaft seal leak-off pipe 41 (the flow is indicated by an arrow H in FIG. 3).
[0034]
At this time, the first shaft seal 51 includes a seal runner 51a fitted on the main shaft 31 and rotating with the main shaft 31, and a slipper attached to the O-ring 59b with respect to the insert 55 fastened to the first shaft seal casing 33a. A seal ring 51b fitted so as to be able to relatively displace in the axial direction with the seal 59c as a sliding portion.
[0035]
Then, as shown in FIG. 4, the seal runner 51a is connected via a retainer 56a fitted to the main shaft 31 via an O-ring 59a provided on the inner wall surface and an O-ring 60a provided on the upper surface of the retainer 56a. A bolt (not shown) for the purpose of restricting the face plate 57a installed on the upper surface of the retainer 56a and the stepped portion installed on the inner peripheral side surface thereof to restrict the movement of the retainer 56a in the axial direction of the face plate. ) And a holder 58a attached to the retainer 56a. That is, the face plate 57a is fitted to the main shaft 31 via the retainer 56a and the holder 58a.
[0036]
Further, as shown in FIG. 4, a seal ring 51b is provided on a retainer 56b fitted to the insert 55 via a slipper seal 59c mounted on an O-ring 59b provided on the inner wall surface, and is provided on a lower surface of the retainer 56b. By contacting the face plate 57b provided on the lower surface of the retainer 56b via the O-ring 60b provided and the stepped portion provided on the inner peripheral side surface thereof, it is possible to restrain the movement of the face plate axial direction with respect to the retainer 56b. And a holder 58b attached to the retainer 56b by bolts (not shown) for the purpose.
[0037]
The second shaft seal 52 is mounted on a main shaft 31 and a seal runner 52a that rotates together with the main shaft 31 via a sleeve (shown here integrally with the retainer 63a) and a second shaft seal casing 33b. A seal ring 52b is fitted to the insert 62 so that the O-ring 64b can be relatively displaced in the axial direction with the O-ring 64b as a sliding portion.
[0038]
As shown in FIG. 5, the seal runner 52a has a ring-shaped upper peripheral surface fitted to the main shaft 31 via a sleeve (shown here integrally with the retainer 63a), and a retainer 63a. And a face plate 65a inserted inside the ring-shaped portion of the retainer 63a via an O-ring 64a installed on the inner wall surface of the ring-shaped portion. That is, the face plate 65a is in a state of being fitted to the main shaft 31.
[0039]
Also, as shown in FIG. 5, a seal ring 52b is provided with a retainer 63b fitted on an insert 62 mounted on the second shaft seal casing 33b via an O-ring 64b installed on the upper inner wall surface, and a bolt (see FIG. 5). (Not shown), the holder 66 is inserted into the inside of the ring-shaped portion of the holder 66 via an O-ring 67 installed on the inner wall surface of the ring-shaped portion of the holder 66, and the retainer is retained by the holder 66. And a face plate 65b mounted on the frame 63b.
[0040]
As shown in FIG. 6, the third shaft seal 53 includes a seal runner 53a (here, a face plate 74a corresponds to this) which is fitted to the main shaft 31 via a sleeve and rotates together with the main shaft 31, and a seal casing. And a seal ring 53b fitted so as to be able to move relative to 33c in the axial direction by using a contact surface with the O-ring 70 as a sliding portion. Further, the third shaft seal 53 is provided via a retainer 71, a holder 73 attached to the retainer 71 by bolts (not shown), and an O-ring 72 installed on an inner wall surface of a ring-shaped portion of the holder 73. And a face plate 74b inserted inside the ring-shaped portion 73.
[0041]
<Operations in the parts reproduction system>
The operation of each block of the component recycling system according to the present invention will be described below by taking the first to third shaft seals 51 to 53 provided in the seal casing 33 as an example. FIG. 7 is a flowchart showing the operation in the component reproduction system.
[0042]
First, in the nuclear power plant 1, various data for confirming the seal characteristics of the first to third shaft seals 51 to 53 are measured (STEP 1). In addition, this data includes a dimensional record of each part of the seal (for example, a wear amount of a sliding portion) measured at the time of a periodic inspection, a seal water temperature in the vicinity of the first shaft seal during the plant operation of the first shaft seal, or The seal water temperature and the flow rate passing through the first shaft seal at the measurement point corresponding to this.
[0043]
When the various data thus measured are given to the terminal device 12, the data is transmitted from the terminal device 12 to the server 21 of the parts company 2 through a network line (STEP 2). In the parts company 2, when the server 21 receives various data for the first to third shaft seals 51 to 53 transmitted from the terminal device 12 (STEP 3), the received various data are analyzed and the first to third data are analyzed. The seal characteristics of the triaxial seals 51 to 53 are evaluated (STEP 4).
[0044]
When various data are analyzed in STEP 4, for example, in the case of the first shaft seal, it is determined whether or not the seal has changed with time from the change rate of the flow rate of the first shaft seal with respect to the change in the temperature of the seal water.
[0045]
After the data is analyzed in the server 21, it is confirmed whether or not the seal needs to be inspected based on the seal characteristic evaluation as the analysis result and the usage time of the first to third shaft seals 51 to 53 (STEP 5). . At this time, when it is predicted that the wear amount of the sliding portion exceeds the predetermined value during the next operation cycle after the periodic inspection, or that the characteristic change due to aging is predicted to exceed the predetermined value, It is determined that the shaft seal needs to be inspected or replaced. Also, when it is confirmed that a predetermined use time has elapsed after the replacement of the first to third shaft seals 51 to 53, it is determined that the shaft seal needs to be replaced.
[0046]
Then, in STEP5, when the server 21 determines that there is no need to check or replace the shaft seal (No), a network line is transmitted to the terminal device 12 of the nuclear power plant 1 so as to continuously perform various data measurements. (Step 6). Then, when the notification of the continuation of the data measurement is confirmed in the nuclear power plant 1 (STEP 7), the operations from STEP 1 are repeated again in the nuclear power plant 1 and the parts company 2.
[0047]
If the server 21 determines in step 5 that the shaft seal needs to be inspected or replaced (Yes), the network is transmitted to the terminal device 12 of the nuclear power plant 1 so that the shaft seal is inspected or replaced. Notification is made via the line (STEP 8). When the notification of the periodic inspection is confirmed in the nuclear power plant 1 (STEP 9), the first to third shaft seals 51 to 53 of the primary coolant pump 11 are replaced with those stored in the storage 14. (STEP 10). The first to third shaft seals 51 to 53 that have been replaced and removed from the primary coolant pump 11 are disassembled into respective parts (STEP 11).
[0048]
That is, the first shaft seal 51 is made up of retainers 56a, 56b, face plates 57a, 57b, O-rings such as holders 58a, 58b, 59a and 59b, 60a, 60b, bolts and cups for fastening components (not shown). Decomposed into washers. Further, the second shaft seal 52 is disassembled into O-rings such as retainers 63a and 63b, face plates 65a and 65b, 64a and 64b and 67, a holder 66, a bolt, and a cup washer. Further, the third shaft seal 53 is disassembled into a retainer 71, face plates 74a and 74b, O-rings 70 and 72, bolts, cup washers, and the like. At this time, the inserts 55 and 62 are also disassembled.
[0049]
When the first to third shaft seals 51 to 53 are disassembled in this way, it is determined whether they can be regenerated (STEP 12). At this time, for example, O-rings such as 59a, 59b, 60a, 60b, 64a, 64b, 67, 70, 72, etc., which are considered to have a life, a cup washer which loses its function when disassembled, or a porous material Thus, ceramics that are difficult to decontaminate and face plates 57a, 57b, 65a, 65b, 74a, 74b, etc., whose sliding surfaces are worn, are classified as discarded parts, and parts that do not meet these conditions are classified as recycled parts. You.
[0050]
Then, the components separated as waste components are disposed of as radioactive waste (STEP 13). In addition, with respect to the parts classified as the reproduction parts in STEP 12, the radiation dose of each part is confirmed (STEP 14). At this time, the radiation detector such as a survey meter and the data analyzer may be separated from each other, and the terminal device 12 may be operated as the data analyzer. In this manner, the radiation detection device can be remotely controlled by the terminal device 12, and the amount of radioactive contamination of each component can be remotely measured. In addition, it is also possible to arrange a radiation detection device on the opposite side of the straight pipe of the cavity passed through the shield toward the measurement object and use a telemetry technique such that measurement is performed without being disturbed by surrounding radioactivity. I do not care.
[0051]
When the radiation dose is confirmed for each component as described above, it is determined from the dose and the shape of the contaminated part that there is no need to perform the decontamination work described below (hereinafter referred to as “decontamination-free component”) and decontamination. Parts that can be worked on (hereinafter referred to as “decontamination-capable parts”) and parts that are difficult to decontamination work (hereinafter referred to as “decontamination-impossible parts”) are separated (STEP 15).
[0052]
At this time, components that are less exposed to radioactivity and whose radiation dose is equal to or less than a predetermined value (a value that can be carried out of the power plant) are regarded as components that do not require decontamination. Also, for parts that have only a small hole in the female screw, such as when the depth of the female screw hole is small or the part has a complicated structure, such as a part that has difficulties in decontamination or radiation detection Are parts that cannot be decontaminated.
[0053]
Therefore, for example, a component that has a radiation dose equal to or higher than a predetermined value and has no parts that are difficult to decontaminate or detect radiation is regarded as a decontaminated component. In other words, components without internal threads or components with internal threads penetrated are easier to decontaminate and detect radiation than components with internal threads that penetrate only partway, and are decontaminated parts. It is said. If the female screw has a large hole and it is determined that decontamination or radiation detection is possible, it is regarded as a decontaminated part.
[0054]
The parts separated as non-decontaminated parts in STEP 15 are disposed of as radioactive waste (STEP 13). The components separated as decontaminable components in STEP 15 are subjected to a chemical decontamination method such as acid dissolution, reduction dissolution, or oxidative dissolution for dissolving and removing the surface film in the decontamination factory 13, and the surface film is peeled off. Physical decontamination method using ultrasonic cleaning, high pressure water cleaning, blasting, etc., electrochemical decontamination method using electropolishing technology for polishing metal surface, or wiping with a wet rag (STEP 16) .
[0055]
In the decontamination factory 13 again, the radiation dose of the decontaminated parts is confirmed (STEP 17), and it is confirmed whether the confirmed radiation dose is within the range that can be carried out to the outside (STEP 18). ). At this time, if the confirmed dose of the radioactivity is not within the range that can be carried out outside (No), the operations after STEP 16 are performed again in the decontamination factory 13.
[0056]
When it is determined in STEP 15 that the radiation dose is a decontamination-free component having a radiation dose within the range that can be externally exported, or when it is confirmed in STEP 18 that the radiation dose is within the range that can be externally exported (Yes), these components are used. Are carried out of the nuclear power plant 1 as parts for regeneration (STEP 19). Then, the parts for reproduction carried out from the nuclear power plant 1 are carried into the parts company 2 (STEP 20).
[0057]
The dimensions of each part of the parts for reproduction carried into the parts company 2 are first measured in the reproduction factory 23 (STEP 21). Then, by confirming the result of the dimension measurement, it is confirmed whether or not the reclaimed component that has been decontaminated and surface-removed or surface-melted can be processed into a reproducible state (STEP 22). At this time, if it is determined that processing is not possible (No), it is discarded as non-radioactive waste that does not need to be treated as radioactive waste (STEP 23).
[0058]
If it is determined in STEP 22 that the part for reproduction can be processed (Yes), the part for reproduction is reproduced in the reproduction factory 23 by lapping the surface of the part or cutting the female screw hole, etc. ( (STEP 24). Then, the remanufactured remanufactured parts and, for example, face parts 57a, 57b, 63a, 63b, 74a, 74b, etc., which are insufficient for assembly, are carried in from the manufacturing plant 22, and the first to third shaft seals 51 are provided. To 53 are assembled (STEP 25). At this time, in the step 24, with respect to the part regenerated by cutting the female screw hole or the like, a bolt larger than the bolt originally inserted into the female screw is carried in from the manufacturing factory 22 and assembled. In STEP 25, the reprocessed parts may be carried into the manufacturing plant 22, and the first to third shaft seals 51 to 53 may be assembled in the manufacturing plant 22.
[0059]
The first to third shaft seals 51 to 53 assembled and regenerated in the regeneration factory 23 as described above are carried into the test factory 24 and required for use in plants such as seal water temperature and seal flow rate tests. Various performance confirmation tests are performed to confirm the sealing characteristics of the above (STEP 26). Then, whether or not the performance is good is confirmed based on the results of the various performance confirmation tests (STEP 27). At this time, when it is determined that the performance is poor (No), it is carried into the recycling factory 23 and assembled again (STEP 25). If the performance is poor, the dimensions may be measured in STEP 21 and the steps subsequent to STEP 22 may be performed, or the regeneration processing may be performed again in STEP 24.
[0060]
When it is determined in STEP 27 that the assembled first to third shaft seals 51 to 53 have good performance (Yes), they are carried out from the parts company 2 (STEP 28). When the first to third shaft seals 51 to 53 regenerated by the parts company 2 are carried into the nuclear power plant 1 (STEP 29), they are stored in the storage 14 (STEP 30). The first to third shaft seals 51 to 53 regenerated by the parts company 2 stored in the storage 14 are subjected to a periodic inspection next time, and the first to third shaft seals of the primary coolant pump 11 are checked in STEP10. It is attached to the primary coolant pump 11 when the shaft seals 51 to 53 are replaced.
[0061]
In the present embodiment, whether or not the periodic inspection is performed by the server of the parts company is managed. However, the server may be managed by the terminal device of the nuclear power plant. At this time, the operations of STEP 4 and STEP 5 in the flowchart of FIG. 7 are performed at the nuclear power plant, and when performing a periodic inspection thereafter, the server of the parts company is notified that the periodic inspection is to be performed. In addition, the data exchange between the server and the terminal device via the network is performed. For example, the characteristic data of the primary coolant pump is recorded on the recording medium by the terminal device of the nuclear power plant, and this recording medium is It may be sent to a parts company to evaluate the seal characteristics.
[0062]
Further, in the present embodiment, the component regeneration system has been described by taking the shaft seal provided in the primary coolant pump in the nuclear power plant as an example. Alternatively, the part to be reproduced may be a part contaminated with radiation at another location.
[0063]
【The invention's effect】
ADVANTAGE OF THE INVENTION According to this invention, a decontamination-removable part, a decontamination unnecessary part, and a decontamination impossible part can be distinguished. In other words, after decontamination processing is performed on decontaminated parts, and without decontamination processing, decontamination unnecessary parts can be carried out of the radiation generating facility, respectively. To perform the reproduction process. Therefore, it is necessary to set up a recycling company just by setting up a recycling factory at a parts company, without setting up a recycling factory to perform new component recycling or a test factory to perform performance confirmation tests in the radiation generation facility. Can be. In addition, since such renewable components are recycled and used as much as possible, radioactive waste can be reduced.
[Brief description of the drawings]
FIG. 1 is a block diagram showing a configuration of a component reproduction system according to the present invention.
FIG. 2 is a schematic configuration diagram showing a configuration example of a primary coolant pump.
FIG. 3 is a schematic configuration diagram showing a configuration relationship of a shaft seal provided in a primary coolant pump.
FIG. 4 is a schematic configuration diagram showing a configuration of a first shaft seal.
FIG. 5 is a schematic configuration diagram showing a configuration of a second shaft seal.
FIG. 6 is a schematic configuration diagram showing a configuration of a third shaft seal.
FIG. 7 is a flowchart showing a process order in the component reproduction system of the present invention.
[Explanation of symbols]
1 Nuclear power plant
2 Parts company
11 Primary coolant pump
12 Terminal device
13 decontamination factory
14 Storage
21 Server
22 Manufacturing Factory
23 Regeneration plant
24 test factory

Claims (9)

When a used part in a radiation generating facility that becomes a radioactively contaminated environment is disassembled into a plurality of constituent parts that make up the used part, the respective parts are separated into renewable parts and non-renewable parts. In the part sorting method,
In the radiation generating facility,
A first step of discarding, as radioactive waste, a non-reproducible component that cannot be clearly reprocessed due to its structure and properties among the respective components;
A second step of measuring the dose of radioactivity for each of the first components excluding the non-reproducible component among the components;
Among the first component parts, the decontamination-impossible parts having a part in which the dose of the radioactivity is in a range in which decontamination treatment is difficult due to their structure and properties are discarded as radioactive waste. 3 steps,
A decontamination-free component in which the radiation dose of the second component excluding the non-decontamination-removable component of the first component is in a range that can be carried out to the outside and decontamination processing is unnecessary; A fourth step of separating the radiation into a decontamination-capable part that can easily be decontaminated due to its structure and properties while the radiation dose is in a range that cannot be externally transported;
Is done,
A method for separating recycled components, wherein the decontaminated components are subjected to a decontamination process to be separated as recyclable components together with the components that do not require decontamination. In the third step, components that cannot be measured for radioactivity after completion of the decontamination process due to their structure and properties are also regarded as non-decontamination components and discarded as radioactive waste. The method for separating recycled components according to claim 1, wherein: The decontamination-removable parts and the decontamination-free parts that have been separated as reproducible in the radiation generating facility are carried out to a parts company that manufactures parts,
The parts company measures the dimensions of the decontaminable parts and the parts that do not require decontamination, determines whether or not the parts can be incorporated after reprocessing, and determines that the decontaminated parts can be incorporated. The method according to claim 1 or 2, wherein the decontamination-unnecessary parts are separated as recyclable parts. In a component manufacturing method for manufacturing used components in a radiation generating facility that becomes a radioactively contaminated environment,
In the radiation generating facility,
Decontaminating, in the radiation generating facility, a first component determined to be capable of decontamination processing to remove a radioactively contaminated portion of a plurality of components constituting the used component whose service life has elapsed; A first step to
A second step of carrying out the first component to a parts company that manufactures parts;
Do
At the parts company,
A third step of determining whether or not the first component can be incorporated after the reprocessing by measuring the dimensions of the first component;
A fourth step of reworking a second component determined to be installable among the first component;
A fifth step of newly manufacturing a third component other than the second component among the components of the used component;
A sixth step of assembling the second component and the third component, a seventh step of performing a performance confirmation test of the used component assembled and reproduced in the sixth step,
By doing
A method for manufacturing a part, comprising manufacturing the used part. In the second step, a component whose radiation dose is in a range that can be externally transported is taken out to the parts company without performing the decontamination process of the first step as a first component. The method of manufacturing a component according to claim 4. A shaft seal for sealing a main shaft in a pump, wherein the shaft seal is manufactured by the component manufacturing method according to claim 4 or 5. In a parts recycling system that recycles used parts in a radiation generating facility that becomes a radioactively contaminated environment,
When confirming that the service life has passed from the use status of the used parts,
In the radiation generating facility,
Replace the used parts,
Of the plurality of components constituting the replaced used component, the components determined to be capable of decontamination processing to remove the radioactively contaminated part are decontaminated, and the amount of radioactive contamination is carried out to the outside. Within the possible range, decontamination components are determined to be unnecessary components as decontamination unnecessary components, component components determined to be decontamination processing is not decontaminated components, respectively, and separated,
Discard the non-decontaminated parts as radioactive waste,
Decontaminating the decontaminated parts,
The decontaminated decontaminated parts and the decontaminated unnecessary parts are carried out to a parts company that performs parts recycling,
At the parts company,
By performing dimensional measurement of the decontaminated parts and the decontamination unnecessary parts carried in from the radiation generating facility, to determine whether it is possible to incorporate after reprocessing,
Of the decontamination-removable parts and the decontamination-unnecessary parts, a third component determined to be incorporable is reprocessed,
Among the components of the used component, a fourth component other than the third component is newly manufactured,
Regenerating the used part by assembling the third component and the fourth component,
Carry out the used parts determined to be good by performing a performance confirmation test of the used parts regenerated to the radiation generating facility,
A parts recycling system, wherein the used parts regenerated by the parts company carried into the radiation generating facility are temporarily stored and treated as replacement parts when the used parts are replaced later. In the radiation generating facility, when the non-decontamination-removable parts, the decontamination-removable parts, and the decontamination-necessary parts are separated from each other, the method for separating recycled parts according to claim 1 or 2 is used. The component reproduction system according to claim 7, wherein A shaft seal for sealing a main shaft in a pump, wherein the shaft seal is regenerated by the component recycling system according to claim 7.

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