JP6863865B2 - Clearance measurement system and method - Google Patents

Description

The present invention relates to a radioactive waste measurement system and method, and more specifically, a clearance suitable for measuring clearances generated during operation or due to decommissioning in a nuclear power generation facility or the like with high efficiency and high accuracy. Regarding measurement systems and methods.

In nuclear power generation facilities, etc., a large amount of waste such as activated waste and waste contaminated by radioactivity is generated due to the dismantling of the facility during operation or at the stage of decommissioning. These wastes are classified according to the degree of pollution, specifically, the level of radioactivity concentration, and the like. Of these, those with a relatively high radioactivity concentration (L1), those with a relatively low radioactivity concentration (L2), those with an extremely low radioactivity concentration (L3), low-level radioactive waste that collectively refers to these, and high-level waste. Level radioactive waste is buried in the ground, such as mid-depth disposal, shallow underground pit disposal, shallow underground trench disposal, and geological disposal, depending on the level.

On the other hand, some of the waste may be excluded from the regulations related to radiation protection because the radiation level is sufficiently small compared to the radiation level in the natural world and the risk to human health is negligible. There is something. These are called clearance objects.

Clearance materials do not need to be treated as radioactive substances, so if the clearance conditions are met, they will be taken out of the nuclear power plant, and those that can be reused will be used as resources, and if reuse is not rational. Can be disposed of in the same way as ordinary industrial waste, not radioactive waste.

The amount of clearance material generated is estimated to be tens of thousands of tons per standard light water reactor for power generation. Therefore, in order to smoothly proceed with the decommissioning of nuclear power plants, it is necessary to treat and dispose of them efficiently. On the other hand, the shape of the clearance object is various, such as a simple shape such as a plate shape or a pipe shape, or a complicated shape such as a bent pipe or a valve. Further, as described above, since the radiation level is very low, a long measurement time is generally required to accurately measure the clearance level. In addition, since clearance items will be distributed to the general public, it is necessary to ensure traceability so that one item of the clearance item and where each item originated can be traced.

As a method for measuring a clearance object, there is a method described in Patent Document 1. In the method described in Patent Document 1, clearance objects of various shapes are processed into a simple shape so as to be easy to measure, and it is confirmed by pre-clearance measurement that there are no highly contaminated parts, and the clearance objects are square-shaped. The clearance is measured from the outside of the container for all gamma rays emitted from the clearance material. Further, in the method described in Patent Document 1, traceability is ensured by attaching a barcode to each dismantled waste and managing it.

JP-A-2007-248066

However, the method described in Patent Document 1 requires a step of processing a clearance object having various shapes into a simple shape in order to facilitate measurement. For this reason, there is a possibility that the number of work processes will increase and efficiency improvement cannot be expected.
When the step of processing into a simple shape is omitted for the purpose of efficiency, the pre-clearance measuring device described in Patent Document 1 has a fixed detector shape when measuring an object having a complicated shape. Since the distance from the detector differs depending on the measurement site, it becomes difficult to measure with high accuracy.

Further, in the clearance measurement described in Patent Document 1, although the efficiency is improved by measuring a large storage container, the radioactivity concentration in the storage container is made almost uniform due to the restrictions of the measurement method and the evaluation method. It is necessary to do so, and it is necessary to set up for that, and there is a possibility that efficiency improvement cannot be expected.

Further, the method described in Patent Document 1 in which a barcode is attached to each dismantled waste in order to ensure traceability is considered to increase the work and cost for a huge amount of waste. In addition, there is a concern that the individual may be mistaken when the barcode is pasted, the barcode may be peeled off, or the barcode may be intentionally replaced, resulting in disguise or replacement of objects.

In view of the above points, an object of the present invention is to provide a clearance measurement system and a method for efficiently measuring and processing a clearance object.

Another object of the embodiment of the present invention is to provide a clearance measurement system and a method for measuring a clearance object with high accuracy. Another object of the embodiment of the present invention is to provide a clearance measurement system and method that ensure traceability.

For the above purpose, in the present invention, "a clearance measuring system for measuring the radioactivity concentration of a clearance substance generated at the time of dismantling a nuclear facility, and the shape of the cut piece after dismantling and cutting the clearance object. A shape measuring device for measuring the shape, a radiation detector for measuring the radiation emitted from the cut piece, a proximity method processing device for determining a method for bringing the radiation detector close to the cut piece based on the result of the shape measurement, and a proximity method. A clearance measurement system characterized by being provided with a detector proximity device that brings the radiation detector closer according to the method of approaching the cut piece of the radiation detector determined by the processing device. "

Further, in the present invention, "a clearance measuring method for measuring the radioactivity concentration of a clearance substance generated at the time of dismantling a nuclear facility, and shape measurement for measuring the shape of the cut piece after dismantling and cutting the clearance object. The treatment, the radiation measurement process for measuring the radiation emitted from the cut piece, the method determination process for determining the method for bringing the radiation detector close to the cut piece based on the result of the shape measurement, and the radiation determined by the method determination process. A clearance measuring method characterized by having a radiation detector proximity process that brings the radiation detector closer according to the method of approaching the cut piece of the detector. "

According to the present invention, it is possible to efficiently process the clearance material.

Further, according to the embodiment of the present invention, it is possible to measure the clearance object with high accuracy. Further, according to the embodiment of the present invention, it is possible to measure the clearance while ensuring traceability.

The figure which shows an example of the processing flow of the clearance measurement method which concerns on Example 1 of this invention. The figure which shows an example of the apparatus configuration of the clearance measurement system which concerns on Example 1 of this invention. The figure which looked at the state which arranged the radiation detector 5 with respect to the bending tube which was divided in half from the top. The figure which shows the AA cross section illustrated in FIG. The figure which shows an example of the processing flow of the clearance measurement method which concerns on Example 2 of this invention. The figure which shows an example of the apparatus configuration of the clearance measurement system which concerns on Example 2 of this invention. The figure which shows an example of the processing flow of the clearance measurement method which concerns on Example 3 of this invention. The figure which shows an example of the processing flow of the clearance measurement method which concerns on Example 4 of this invention. The figure which shows an example of the apparatus configuration of the clearance measurement system which concerns on Example 4 of this invention. The figure which shows an example of the outline of the cutting method in the clearance measurement system which concerns on Example 5 of this invention. The figure which shows the more detailed equipment configuration example of the apparatus part 13 which performs a radiation measurement process.

Hereinafter, examples of the present invention will be described with reference to the drawings.

Hereinafter, the clearance measurement system and method according to the first embodiment of the present invention will be described with reference to FIGS. 1 to 4.

FIG. 1 shows an example of the processing flow of the clearance measurement method according to the first embodiment of the present invention.

In this processing flow, the cut pieces disassembled in the processing step S100 are received, and the shape of the cut pieces is measured in the processing step S101.

After that, in the processing step S102, in order to measure the entire surface of the cut piece with the radiation detector based on the shape measurement result, a process of determining the proximity method and the arrangement method of the radiation detector with respect to the cut piece is performed.

In the processing step S103, a process of actually arranging the radiation detector 5 close to the cut piece 1 is performed according to the proximity method and the arrangement method of the radiation detector 5 determined by the process of step S102.

In the processing step S104, the radiation measurement process is subsequently carried out by the radiation detector.

In the processing step S200, the cut pieces for which the radiation measurement has been completed are carried out for a subsequent process, or are subjected to processing such as primary storage.

It is desirable that the following points be further taken into consideration when specifically executing each process in the process flow shown in FIG.

First, regarding the shape measurement process of the process step S101, when the cut piece is, for example, a pipe divided in half, there is a high possibility that the portion corresponding to the inner surface of the pipe is contaminated with radioactivity. Considering the distribution, it is necessary to measure the radiation on the entire surface of the cut piece. Therefore, it is desirable to measure the shape of the cut piece on the entire surface of the cut piece.

In addition, the following points should be taken into consideration with respect to the process of determining the proximity method and the arrangement method of the radiation detector with respect to the cut piece in the process step S102.

As the first point in the execution of the processing step S102, since the radiation level of the clearance object is very low, a long measurement time is required for highly accurate measurement. In order to shorten the measurement time, that is, to increase the throughput of the measurement process, it is necessary to bring the radiation detector as close to the radiation source as possible. Therefore, determining the proximity method and the arrangement method of the radiation detector leads to the efficiency of the entire measurement.

As a second point in the execution of the processing step S102, as will be described later, the storage container used for the final clearance measurement and storage of the clearance object is a large square shape having a size of about 1.3 m × 1.3 m × 1 m. Since a container is assumed, it is necessary to be able to measure relatively large pieces. Therefore, the radiation detector to be used may be a survey meter, but a detector capable of collectively measuring a wide range is desirable.

Further, as a third point in execution of the processing step S102, since the shape of the clearance object is complicated, high-precision measurement can be realized by measuring along the shape of the cut piece. Therefore, as a radiation measuring instrument, a plastic scintillation fiber (PSF) capable of a wide range of batch measurement and having flexibility is considered as one of the application candidates. PSF is a scintillator material that generates scintillation light by interacting with radiation, and is formed into an optical fiber shape. Due to the difference in arrival time of light incident on the photodetectors installed at both ends of the fiber, it is on the fiber. The light emitting position, that is, the incident position of radiation on the fiber and its intensity are measured. PSFs have a length of 10 m to 20 m, and are characterized by high flexibility like optical fibers.

Further, as the fourth point in the execution of the processing step S102, as one of the processing methods for determining the proximity method and the arrangement method of the radiation detector, a dismantling device, a shape model having dimensional information of the cut piece, and the like are registered in the database. It is advisable to associate each shape model with a predetermined proximity method and arrangement method of the radiation detector to be used. It is advisable to compare the shape measurement result by the shape measuring device with the shape model of the cut piece to determine the method of approaching and arranging the radiation detector with respect to the cut piece.

Further, as the fifth point in the execution of the processing step S102, as already described, since a large amount of clearance is generated, it is not realistic to prepare all the dismantling devices and the shape models of the cut pieces in advance. .. On the other hand, the shape of the clearance object can be classified into plates, pipes, valves and the like. Therefore, at least one shape model is prepared for each classification. The dimensions of this shape model are set to be variable as parameters, and the dimensional parameters are determined by comparing the shape measurement results of the shape measuring device with the cut pieces. The proximity method and the arrangement method of the radiation detector may be determined in advance as before. However, it is desirable to prepare a plurality of radiation detectors, for example, PSFs having different fiber diameters, so that they can be selected according to the dimensions of the cut pieces.

Further, as a sixth point in the execution of the processing step S102, artificial intelligence (AI) can be used as another method of the processing method for determining the proximity method and the arrangement method of the radiation detector. Various shape models are provided to AI, and the proximity method and placement method of the radiation detector are learned in advance. In the actual field, by inputting the shape measurement result by the shape measuring device, the optimum proximity method and arrangement method of the radiation detector are derived by AI. In this case as well, it is desirable to prepare a plurality of radiation detectors having different PSF fiber diameters so that they can be selected according to the dimensions of the cut pieces.

FIG. 2 shows an example of the device configuration of the clearance measurement system according to the first embodiment of the present invention. The configuration of FIG. 2 shows a system configuration for realizing the processing flow of FIG.

In this measurement system, the received cut piece 1 is conveyed to the front of the shape measuring device 2 by a belt conveyor 11a or the like. This transport processing portion corresponds to the processing of the processing step S100 of FIG.

The shape measurement portion 14 of the clearance measurement system that performs the shape measurement process in the process step S101 of FIG. 1 includes a shape measurement device 2, a holding jig 10a that holds the cutting piece 1, and rotation for changing the orientation of the cutting piece 1. It is composed of a stand 12. Here, the cut piece 1 is conveyed from the left side to the right by the belt conveyor 11a, held by the holding jig 10a as shown in the drawing, transferred to the turntable 12, and rotated, whereby the shape measuring device 2 The surface shape of the cut piece 1 is grasped. The surface shape should be grasped three-dimensionally including the front and back sides.

Information on the surface shape of the cut piece 1 is transferred from the shape measuring device 2 to the proximity method processing device 3. The shape measurement result is transferred to the proximity method processing device 3, and based on the shape measurement result, the proximity method and the arrangement method of the radiation detector 5 to the cut piece 1 are determined. During this period, the cut piece 1 is conveyed from the shape measurement position to the front of the radiation measurement position by a belt conveyor 11b or the like. The portion of the proximity method processing device 3 of FIG. 2 corresponds to the detector proximity method determination process of the process step S102 of FIG.

Next, the cut piece 1 is conveyed from the left side to the right by the belt conveyor 11b, and is transferred to the radiation measuring unit 13 by the holding jig 10b. The radiation measuring unit 13 is composed of a radiation detector 5, a detector proximity device 4 to which the radiation detector 5 is attached, and a holding jig 10b for holding a cutting piece 1. Here, the conveyed cutting piece 1 is held by the holding jig 10b as shown in the figure and moved to the radiation measurement position. After the cutting piece 1 is moved, the radiation detector 5 is brought close to the cutting piece 1 by the detector proximity device 4 based on the processing result transferred from the proximity method processing device 3, and radiation measurement is performed. The portion of the radiation measuring unit 13 in FIG. 2 corresponds to the proximity and measurement processing of the processing steps S103 and S104 in FIG.

After the radiation measurement process is completed, the cut piece 1 is conveyed to the place of the post-process by a belt conveyor 11c or the like. This transport portion corresponds to the carry-out or storage process of the process step S200 of FIG.

In configuring each part of the clearance measurement system shown in FIG. 2, it is desirable to further consider the following points.

First, regarding the shape measuring portion, in this figure, a shape measuring device using a laser is shown as the shape measuring device 2, but for example, an optical camera, a stereo camera, or a 3D scanner to which they are applied may be used.

As for the shape measuring portion, as described above, in order to measure the shape of the entire surface of the cutting piece 1, the portion of the holding jig 10a in contact with the cutting piece 1 is rotated in the direction of the arrow in FIG. The front and back surfaces of the cut piece 1 can be measured. However, a part of the surface of the cutting piece 1 is hidden by the portion of the holding jig 10a that is in contact with the cutting piece 1. In order to measure the shape of the hidden part, the cutting piece 1 is once placed on the turntable 12, the turntable 12 is rotated 90 degrees, and then the cutting piece 1 is held again by the holding jig 10a, and the shape is measured in this state. It is better to carry out again.

Next, regarding the device portion 13 that performs the radiation measurement process, the case of PSF is shown as the radiation detector 5 in this figure, but other radiation detectors such as a survey meter may be used. The conveyed cutting piece 1 is held by the holding jig 10b as shown in the figure and moved to the radiation measurement position. After the cutting piece 1 is moved, the radiation detector 5 is brought close to the cutting piece 1 by the detector proximity device 4 based on the processing result transferred from the proximity method processing device 3. In this figure, in order to measure radiation on the entire surface of the cut piece 1, PSFs are arranged above and below the cut piece 1 and brought close to each other. However, as in the case of shape measurement, the holding jig 10 and the holding jig 10 are shown. By using a turntable (not shown), it is possible to measure with a single PSF.

Further, the device portion 13 for performing the radiation measurement process should be as follows. FIG. 11 shows a more detailed equipment configuration example of the device portion 13 that performs the radiation measurement process. Here, the cut piece 1 has a plate shape and is held by the holding jig 10b on the left and right side portions. In this case, radiation measurement is performed from the vertical direction. Further, the radiation detector 5 is configured as a detector having an area spread by arranging the PSF folded back, and the detector proximity device 4 to which the radiation detector 5 is attached can be flexibly configured in shape. .. In the illustrated example, the upper equipment is shown as 4a and 5a, and the lower equipment is shown as 4b and 5b.

In this example, since the cut piece 1 has a plate shape, the detector proximity devices 4a and 4b are arranged in a straight line in a plate shape as shown in 4b1 based on the processing result transferred from the proximity method processing device 3. , Close to the cut piece 1 from the vertical direction. The degree of approach is instructed by the proximity method processing device 3.

The detector proximity devices 4a and 4b can be lifted or suspended at a plurality of points to realize the above-mentioned planar shape or a shape along the half-split pipe shape of the elbow portion.

In the above description, for the sake of simplicity, the shape of the cut piece 1 has been described by taking a plate-like shape as an example. As an example of the proximity and arrangement of the radiation detector 5 in the case of a complicated shape, the case where the bending tube 1'is targeted is shown in FIGS. 3 and 4. FIG. 3 shows a top view of a state in which the radiation detector 5 is arranged with respect to a bent tube divided in half, and FIG. 4 shows a cross section taken along the line AA shown in FIG. Further, as an example of the radiation detector 5, the case of PSF is shown.

In FIGS. 3 and 4, PSFs are reciprocally arranged as a radiation detector 5 inside the elbow-shaped half-split bending tube 1', so that the half-split bending tube 1'is not only in the longitudinal direction but also at the bottom. Regarding the side part, it is possible to measure the radiation of the part.

The device portion 13 for performing the radiation measurement process when the cut piece 1 is in the shape of a half-split pipe of the elbow portion shown in FIGS. 3 and 4 is preferably as follows.

Explaining with reference to FIG. 11, when the cut piece 1 is large and it is difficult to support it on both side surfaces, it is arranged on the pedestal and measurement is performed only from the side surface or the upper portion. The radiation detector 5a on the upper side at this time is configured as a detector having a planar spread by arranging the PSF folded back, and the detector proximity device 4a to which the radiation detector 5a is attached has a half-split pipe shape. It is formed into a shape that is bent in a U shape along the elbow and bends along the elbow. In this case, the lower equipments 4b and 5b may not be used, but it is conceivable that the lower equipments are used and applied to the measurement from the side surface. This shape and the proximity position are determined based on the processing result transferred from the proximity method processing apparatus 3.

Not limited to bent pipes, pipe-shaped pipes are often handled in a half-split state because it is required for clearance measurement to expose the contaminated surface when the inner surface is contaminated. From the shape measurement result for the bent pipe 1', the proximity method processing device 3 determines the proximity and arrangement method. For example, by arranging the radiation detector 5 as shown in FIG. 3, the contaminated surface can be measured all over.

Further, as already described, in order to carry out the measurement with high accuracy and high efficiency, it is desirable to measure the radiation detector 5 as close as possible to the radiation source. For a shape like a pipe, the distance from the inner surface of the pipe to the radiation detector 5 can be shortened and kept constant by arranging the shape as shown in FIG. That is, it is possible to measure with high accuracy and high throughput without the need for conversion processing due to the difference in distance. Measurement becomes possible.

According to the first embodiment of the present invention described above, since it is possible to measure with high throughput, it is possible to efficiently process the clearance material.

Further, according to the above-described embodiment of the present invention, it is possible to measure the clearance object with high accuracy.

The clearance measurement system and method according to the second embodiment of the present invention will be described with reference to FIGS. 5 and 6. In the first embodiment, it is assumed that the individual cut pieces are measured, but in reality, a plurality of cut pieces are stored and carried out in a large square container, and at that time, a large square type is used. Since the radiation concentration of the entire container is measured, Example 2 proposes a clearance measurement system and method including the subsequent treatment of Example 1.

FIG. 5 shows an example of the processing flow of the second embodiment of the clearance measurement method in the present invention. Steps S100 to S104 are the same as in the first embodiment of FIG.

In the second embodiment, after the radiation measurement process in the process step S104, the cut piece 1 measured in the process step S105 is stored in the storage container.

After the plurality of cut pieces 1 are stored in the storage container, the radioactivity concentration measurement and evaluation process is performed in the process step S106.

In the treatment step S200, the cut piece 1 for which the radioactivity concentration measurement evaluation has been completed is carried out for a subsequent process, or is subjected to a treatment such as primary storage.

It is desirable that the following points be further taken into consideration when specifically executing each process in the process flow shown in FIG.

First, regarding the container storage process of the cut pieces in the processing step S105, a large square container of about 1.3 m × 1.3 m × 1 m is assumed as the storage container used for the final clearance measurement and storage of the clearance object. ing. A plurality of cutting pieces 1 are stored in the storage container. The amount of the plurality of cut pieces 1 that can be stored in the storage container is limited by the load limitation of the device that conveys the storage container including the plurality of cut pieces 1, but a certain amount can be stored.

Further, regarding the radioactivity concentration measurement and evaluation process in the processing step S106, the gamma rays emitted from the cut pieces are measured by the radiation measuring instrument arranged outside the storage container for the plurality of cut pieces stored in the storage container. From the result, the average radioactivity concentration of a plurality of cut pieces stored in the storage container is calculated and evaluated. Since a large storage container is measured, it is conceivable to use a large-area plastic scintillator or the like for the radiation measuring instrument. By measuring this facing the six sides of the storage container, it is possible to collectively process large storage containers and improve efficiency.

On the other hand, when measuring a large storage container with a detector such as a large-area plastic scintillator, the average value of each detector is used for evaluation, so the setup is such that the radioactivity concentration in the storage container becomes almost uniform. There is a concern that it will be necessary. If such a setup is required, efficiency may be hindered.

On the other hand, it is conceivable to apply a method capable of measuring and evaluating the radioactivity concentration distribution in the storage container by using a plurality of gamma ray spectrum detectors as radiation measuring instruments. In this method, the gamma ray spectrum is measured, and the spatial distribution of the radioactivity concentrations of Co-60 and Cs-137, which are the main nuclides to be measured (Key nuclides) in the clearance substance measurement, is evaluated. By making it possible to evaluate the radioactivity concentration distribution, it is not necessary to set up to make the radioactivity concentration in the storage container uniform, and efficiency can be improved. In addition, in order to make the radioactivity concentration uniform, it is conceivable to shred the cut pieces as much as possible to make them uniform. However, if the radioactivity concentration distribution can be evaluated, the cut pieces can be stored. It can be disassembled and cut to a size that can be stored in a container, and the cutting man-hours can be reduced. In addition, since the average radioactivity concentration is evaluated in consideration of the distribution of the radioactivity concentration, highly accurate evaluation is possible.

FIG. 6 shows an example of the device configuration of the clearance measurement system according to the second embodiment of the present invention. The upper part of the figure is the same as the clearance device configuration of the first embodiment.

After the radiation measurement process is completed, the cut piece 1 is stored in the storage container 21 by means such as a crane 51. After that, gamma rays are measured by a plurality of radiation measuring instruments 22 arranged on the outer surface of the storage container 21, and the radioactivity concentration distribution and the average radioactivity concentration are evaluated. The radiation measuring instrument 22 shown here represents a gamma ray spectrum detector. In this case, the radioactivity concentration measurement and evaluation device evaluates the radioactivity concentration distribution of the cut pieces stored in the container based on the measurement results of at least one gamma ray spectrum detector and the gamma ray spectrum detector. It is equipped with an evaluation device.

According to the second embodiment of the present invention described above, it is possible to efficiently process the clearance object by reducing the setup and cutting man-hours.

Further, according to the above-described embodiment of the present invention, it is possible to measure the clearance object with high accuracy.

The clearance measuring method according to the third embodiment of the present invention will be described with reference to FIG. In the second embodiment, it has been described that the radiation concentration measurement of the entire large square container is performed, but since it is necessary to perform the second radiation concentration measurement before the actual unloading, the second embodiment is performed. Section 3 clarifies the processing of this part.

FIG. 7 shows a processing flow of the clearance measuring method according to the third embodiment of the present invention. Steps S100 to S105 are the same as in the second embodiment. In Example 3, the radioactivity concentration measurement evaluation database DB1 is provided.

In this flow, it is assumed that after evaluating the radioactivity concentration of the storage container 21 in the processing step S106, the radioactivity concentration is reconfirmed at a later date. Here, the evaluation result data of the radioactivity concentration in the radioactivity concentration measurement evaluation processing step S106 is stored in the radioactivity concentration measurement evaluation database DB1 which is a storage device. In the treatment step S201, after the cut pieces are temporarily stored, a second radioactivity concentration measurement and evaluation process (second radiation concentration measurement by a public institution) is performed in the treatment step S106'for reconfirmation. At this time, the evaluation result data of the radioactivity concentration stored in the radioactivity concentration measurement evaluation database DB1 and the evaluation result data of the radioactivity concentration evaluated in the processing step S106'are compared, and there should be no discrepancy between the two data tubes. For example, the traceability of the storage container 21 has been confirmed, and the cut pieces are carried out of the power plant in the processing step S202.

In this case, it is preferable to provide a radioactivity concentration measurement evaluation data storage device for storing the radioactivity concentration measurement evaluation data and a second radioactivity concentration distribution evaluation device.

According to the third embodiment of the present invention described above, traceability can be ensured.

The clearance measurement method according to the fourth embodiment of the present invention will be described with reference to FIGS. 8 and 9. In the fourth embodiment, since the clearance material is reused after being carried out, a process that enables confirmation of the source of the clearance material at the time of reuse at the carry-out destination is provided.

FIG. 8 shows an example of the processing flow of the clearance measurement method according to the fourth embodiment of the present invention, and shows an example of a method for ensuring traceability of the cut piece 1 after being carried out of the power plant. is there. In the fourth embodiment, in addition to the radioactivity concentration measurement evaluation database DB1, the shape measurement database DB2, the export source device information database DB3, and the radiation measurement database DB4 are provided.

Steps S100 to S202 are the same as in the third embodiment. However, in the shape measurement processing step S101, the unloading source device information data indicating from which device the cut piece 1 to be measured is disassembled after the processing is stored in the unloading source device information database DB3 which is a storage device. , The shape measurement data is stored in the shape measurement database DB2 which is a storage device. Further, in the radiation measurement processing step S104, the radiation measurement data is stored in the radiation measurement database DB4 which is a storage device after the processing.

In FIG. 8, processing steps S100 to S106 (S106') and processing steps S201 and S202 are processing contents at, for example, a power plant, which is a source of carrying out the cut pieces, and processing steps S401 newly added in the fourth embodiment. From S404, it is a process at the delivery destination. At the delivery destination, when reusing the cut piece, it is assumed that the source and the measured value are to be confirmed, and the flow of the confirmation process is shown.

In order to backtrace the cut pieces at the carry-out destination, the second shape measurement process is performed in the process step S401. Here, since it is assumed that the cut pieces are used at a place other than the power plant (the source of the cut pieces 1), it is considered that a tablet terminal, an optical camera, or the like can be used as the shape measurement processing device. Of course, it is also possible to apply the method / apparatus described in the first embodiment.

Next, in the processing step S402, the shape measurement database DB2, which is a storage device, is referred to in response to the result of the second shape measurement processing, and the shape measurement data stored therein and the shape measurement obtained by the second shape measurement processing are performed. Perform the process of comparing the data and collating / identifying the cut pieces.

In the process step S403, when the cut piece to be measured is identified, the carry-out source device information database DB3, which is a storage device, is referred to, and the device information data related to the cut piece is called from there. Further, the radiation measurement database DB4, which is a storage device, is referred to, the radiation measurement data of the cut piece is called from there, and a process of associating these information is performed. Further, in the process step S402, a process of displaying the associated information is performed. The display may be, for example, a tablet terminal, a mobile terminal such as a notebook PC, or a desktop PC.

FIG. 9 shows an example of the device configuration of the clearance measurement system according to the fourth embodiment of the present invention. The carry-out source is provided with a shape measurement database DB2, a carry-out source device information database DB3, and a radiation measurement database DB4, which are communication equipment such as a network 30 under the control of the collation identification device 402 and the information-related device 403. It is linked with the delivery destination via. There are cut pieces brought in for reuse at the carry-out destination, and the reuser of the carry-out destination wants to confirm the source of the cut pieces and the measured value before reuse. Reference numeral 404 is a display processing device.

For this confirmation process, the reusable user at the delivery destination uses a tablet terminal as an example of the shape measurement processing device 31. Here, the camera function of the tablet terminal is used to take a picture of the cut piece 1 whose traceability is to be confirmed. At least one photograph is required for shape measurement, but it is desirable from the viewpoint of shape measurement accuracy that there are a plurality of photographs taken from different directions.

These photographs are integrated into shape measurement data 1v, which is transferred to each processing device and storage device of the carry-out source via the network 30.

The transferred shape measurement data 1v is compared with the shape measurement data stored in the shape measurement database DB 2 in the collation identification device 402 to collate and identify the cut piece 1. Regarding the identified cut piece 1, in the information-related device 403, the device information data of the cut piece 1 stored in the export source device information database DB3 and the radiation measurement data of the cut piece 1 stored in the radiation measurement database DB4. To perform data association. This information is organized by the display processing device 404, transmitted to the tablet terminal which is the shape measurement processing device 31 again, and displayed on the screen as the related information 32.

As described above, by using the shape information as the unique information of the cut piece 1, for example, the work and cost of attaching the barcode or IC tag to the cut piece 1 can be reduced, and the barcode or IC tag can be attached. It is possible to eliminate the concern that the individual may be mistaken for attachment, the barcode or IC tag may be peeled off, or the barcode or IC tag may be disguised or replaced.

According to the fourth embodiment of the present invention described above, traceability can be ensured.

Example 5 of the present invention will be described with reference to FIG.

FIG. 10 shows an example of an outline of the cutting method in the clearance measuring method according to the fifth embodiment of the present invention.

In Examples 1 to 4, the cut surface of the cut piece 1 is described as being cleanly treated. Since the measurement accuracy of shape measuring devices such as laser shape measuring instruments and 3D scanners has been improved in recent years, there is a possibility that it is possible to measure the difference in dimensions of individuals whose cut surfaces have been cleanly processed. However, the difference is slight, and it cannot be denied that the processing time may be long in order to identify individuals having almost the same shape, which may be an obstacle to efficiency improvement.

FIG. 10 shows a cut piece 1 cut by the cutting device 41. As the cutting device 41, a cutter for heavy machinery is shown as an example. Since the cutter for heavy machinery cuts the object to be cut so as to crush or tear it rather than cutting it cleanly, it is expected that the cut surface of the cut piece 1 has a collapsed shape as shown in the figure. In addition, it can be cut in a shorter time than normal cutting. In addition to the cutter for heavy machinery, a thermal cutting device such as an arc saw can cut at high speed so that the cut surface is in a collapsed state.

In this way, it is possible to relax the shape measurement accuracy required for individual identification by cutting with the cut surface intentionally collapsed by high-speed cutting, and processing for individual identification. The time can also be shortened.

According to the above-described embodiment of the present invention, it is possible to efficiently process the clearance material.

Further, according to the above-described embodiment of the present invention, it becomes easy to ensure traceability.

By using the method of the present invention, it is possible to measure the radioactivity concentration with high efficiency and high accuracy for radioactive waste having various radioactivity concentration levels as well as the clearance level, and to ensure traceability.

1: Cut piece 1': Bending tube 1v: Shape measurement data 2: Shape measuring device 3: Proximity method processing device 4: Detector proximity device 5: Radiation detector 10a, 10b: Holding jig 11: Belt conveyor 12: Turntable 21: Storage container 22: Radiation measuring instrument 30: Network 31: Shape measurement processing device 32: Related information 41: Cutting device 51: Crane DB1 to DB4: Database 402: Collation identification device 403: Information related device 404: Display processing apparatus

Claims (12)

A clearance measurement system that measures the radioactivity concentration of clearance substances generated during the dismantling of nuclear equipment.
With respect to the cut piece after dismantling and cutting the clearance object, a shape measuring device for measuring the shape of the cut piece, a radiation detector for measuring the radiation emitted from the cut piece, and the cut piece based on the result of the shape measurement. A proximity method processing device that determines a method for bringing the radiation detector closer, and a detector proximity device that brings the radiation detector closer according to the method of approaching the cut piece of the radiation detector determined by the proximity method processing device. The radiation detector is a clearance measuring system, characterized in that the radiation detector is a detector having flexibility. The clearance measurement system according to claim 1.
A plurality of the cut pieces measured by the radiation detector are stored in a container, and the radioactivity concentration of each of the containers containing the plurality of cut pieces is measured and evaluated collectively, and the radioactivity concentration measurement evaluation data is obtained. A clearance measurement system characterized by being equipped with a radioactivity concentration measurement and evaluation device. The clearance measurement system according to claim 2.
The radioactivity concentration measurement and evaluation device evaluates the radioactivity concentration distribution of the cut pieces stored in the container based on the measurement results of at least one gamma ray spectrum detector and the gamma ray spectrum detector. A clearance measurement system characterized by being equipped with an evaluation device. The clearance measurement system according to claim 2 or 3.
A clearance measurement system including a radioactivity concentration measurement evaluation data storage device for storing the radioactivity concentration measurement evaluation data and a second radioactivity concentration distribution evaluation device. The clearance measurement system according to any one of claims 1 to 4.
A shape measurement data storage device that stores shape measurement data by the shape measurement device, a radiation measurement data storage device that stores radiation measurement data of the cut piece by the radiation detector, and a second device that measures the shape of the cut piece. The individual cut pieces are identified from the shape measuring device, the shape measurement data stored in the shape measurement data storage device, and the second shape measurement data acquired by the second shape measurement device, and the cutting is performed. It is characterized by being provided with an association processing device that performs association processing with the information of the device in which the piece is generated and the radiation measurement data stored in the radiation measurement data storage device, and a display device that displays the result of the association processing. Clearance measurement system. The clearance measurement system according to any one of claims 1 to 5.
A clearance measurement system characterized by being equipped with a cutting device that cuts each piece into a different shape when disassembling a clearance object. This is a clearance measurement method that measures the radioactivity concentration of clearance substances generated during the dismantling of nuclear equipment.
Based on the shape measurement process that measures the shape of the cut piece after dismantling and cutting the clearance object, the radiation measurement process that measures the radiation emitted from the cut piece with a radiation detector, and the result of the shape measurement. Radiation detection that brings the radiation detector close to the cut piece according to a method determination process for determining a method for bringing the radiation detector close to the cut piece and a method for bringing the radiation detector close to the cut piece determined by the method determination process. both as having vessels close process,
Based on the result of the shape measurement, it is characterized by having a process of deforming the shape of the radiation detector having flexibility according to or following the shape of the cut piece and a process of bringing it close to the cut piece. Clearance measurement method. The clearance measuring method according to claim 7.
It is characterized by having a radioactivity concentration measurement and evaluation process in which the clearance material whose radiation has been measured by the radiation measurement process is stored in a container, and a plurality of the cut pieces are collectively measured and evaluated for the radioactivity concentration of the container. Clearance measurement method. The clearance measuring method according to claim 8.
The result of the measurement and evaluation process of the radioactivity concentration is stored, and the batch evaluation process of the radioactivity concentration is performed again for the evaluated container, and the result of the measurement and evaluation process of the radioactivity concentration and the batch of the radioactivity concentration are recollected. A clearance measuring method comprising a process of comparing evaluation process results. The clearance measuring method according to any one of claims 7 to 9.
The process of acquiring the second shape measurement data of the cut piece, the comparison process of comparing the shape measurement data of the cut piece with the second shape measurement data, and the result of the comparison process are used to identify the cut piece. Clearance measurement comprising the identification process, the process of associating the information of the device in which the cut piece identified by the identification process and the information of the radiation measurement process are associated, and the process of displaying the associated information. Method. The clearance measuring method according to any one of claims 7 to 10.
A clearance measuring method, characterized in that the dismantling of the clearance includes a method of cutting the cut pieces into different shapes. The clearance measurement system according to any one of claims 1 to 6.
The radiation detector is a flexible PSF, and the detector proximity device supports the PSF with a planar spread and deforms the PSF into a shape based on the result of the shape measurement into the cut piece. A clearance measurement system characterized by being close to each other.

Images