JP2023068364A - Radiation evaluation device - Google Patents

Abstract

To provide a radiation evaluation device that can accurately evaluate radiation of waste generated from a nuclear power generation facility, reflecting an actual contamination distribution of the waste.SOLUTION: A radiation evaluation device according to the present invention comprises: a shape data acquisition device 12 that shape data on waste 51 generated from a nuclear power generation facility; a contamination distribution data acquisition unit 11 that acquires contamination distribution data on the waste 51; a conversion coefficient analysis device 13 that inputs the shape data and the contamination distribution data, implements a radiation analysis to obtain, with respect to the waste 51, a conversion coefficient converting a radiation measurement value to radioactive level; a radiation measurement device 101 that measures radioactive level of the waste 51; and a radiation calculation device 103 that calculates the radioactive level of the waste 51, using data on the radioactive level of the waste 51 measured by the radiation measurement device 101 and the conversion coefficient with respect to the waste 51.SELECTED DRAWING: Figure 1

Description

The present invention relates to an apparatus for evaluating radioactivity of waste generated from nuclear power plants.

A large amount of waste such as activated waste or waste contaminated with radioactivity is generated at a nuclear power plant or the like during operation or decommissioning due to the replacement of equipment or the dismantling of the facility. These wastes are classified according to the level of radioactivity concentration, such as the degree of activation or radioactive contamination. Of these, low-level radioactive waste, which has a relatively high concentration of radioactivity, a relatively low concentration of radioactivity, and a waste with an extremely low concentration of radioactivity, shall be disposed of in mid-depth disposal, shallow underground pits, respectively. In-ground disposal such as disposal and trench disposal is performed. In addition, geological disposal is carried out for high-level radioactive waste, which has a higher radioactivity concentration than low-level radioactive waste.

On the other hand, some wastes are exempt from regulations related to radiation protection because the degree of radioactive contamination is sufficiently low compared to the radiation level in the natural world and the risk to human health is negligible. There is something you can do. These are called clearance items.

Waste whose radioactivity concentration is determined to be below the clearance level does not need to be treated as radioactive waste and is treated as a clearance product. For this reason, clearance items can be transported outside the nuclear power plant, reused as resources if they can be reused, and can be disposed of in the same way as ordinary industrial waste if reuse is not rational. be. Determination of whether or not the waste is below the clearance level is carried out by measuring the radiation of the waste to be measured and evaluating the radioactivity from the measurement results.

An example of a conventional method for measuring and evaluating the radioactivity of waste is described in Patent Document 1. The method described in Patent Document 1 virtually divides the inside of a container containing radioactive waste into a plurality of meshes, sets the density of the radiation source and the waste for each mesh, and arranges the radioactive waste around the container. Radiation is measured by a detector, and the radioactivity concentration distribution of the entire waste contained in the container is evaluated from the measurement results.

Japanese Patent Application Laid-Open No. 2019-32208

In the method described in Patent Document 1, for efficiency, a virtual mesh is set inside the container to evaluate the radioactivity concentration distribution inside the container and evaluate the radioactivity of the entire container. That is, in the method described in Patent Document 1, the radioactivity of the entire container is evaluated in mesh units, and the contamination distribution of individual wastes stored in the container is not obtained.

In addition, in the method described in Patent Document 1, the radioactivity concentration distribution is evaluated on the assumption that the radiation source is located at the location where the measurement efficiency of the radiation detector is the lowest. There is a possibility that the radioactivity concentration will be calculated too high and the waste that can be treated as clearance material will be evaluated as having radioactivity higher than the clearance level. Such waste will be treated as radioactive waste even though it is actually clearance material. If waste that can be treated as clearance is treated as radioactive waste, the clearance is treated as radioactive waste, which increases the cost of radioactive waste treatment.

As described above, the conventional technology has a problem in accurately evaluating the radioactivity of the waste generated from the nuclear power plant by reflecting the actual contamination distribution of the waste.

SUMMARY OF THE INVENTION An object of the present invention is to provide a radioactivity evaluation apparatus capable of accurately evaluating the radioactivity of waste generated from a nuclear power plant by reflecting the actual contamination distribution of the waste.

A radioactivity evaluation apparatus according to the present invention includes a shape data acquisition device that acquires shape data of waste generated from a nuclear power plant, a contamination distribution data acquisition device that acquires contamination distribution data of the waste, and the shape data. a conversion factor analysis device for inputting the contamination distribution data and performing radiation analysis to obtain a conversion factor for converting the radiation measurement value into radioactivity for the waste; and a radiation measurement device for measuring the radiation of the waste. and a radioactivity calculation device for calculating the radioactivity of the waste using the radiation data of the waste measured by the radiation measuring device and the conversion factor for the waste.

According to the present invention, it is possible to provide a radioactivity evaluation apparatus capable of accurately evaluating the radioactivity of waste generated from a nuclear power plant by reflecting the actual contamination distribution of the waste.

BRIEF DESCRIPTION OF THE DRAWINGS It is a figure which shows the structure of the radioactivity evaluation apparatus by Example 1 of this invention. 1 is a diagram showing an example of a processing flow for evaluating radioactivity of waste using a radioactivity evaluation device in Example 1. FIG. 1 is a diagram showing an example of a configuration of a conversion factor analysis device in Example 1. FIG. FIG. 10 is a diagram showing the configuration of a shape data acquisition device in Example 2 of the present invention; FIG. 10 is a diagram showing a radiation measuring device that acquires contamination distribution data of dismantled objects in Example 3 of the present invention. It is a figure which shows the structure of the radioactivity evaluation apparatus by Example 4 of this invention. It is a figure which shows the structure of the radioactivity evaluation apparatus by Example 5 of this invention.

The radioactivity evaluation apparatus according to the present invention can accurately evaluate the radioactivity of waste generated from a nuclear power plant by reflecting the actual contamination distribution of the waste. Such wastes include, for example, wastes generated by replacing equipment during operation of nuclear power plants, and dismantled materials generated by dismantling facilities during decommissioning of nuclear power plants.

A radioactivity evaluation apparatus according to the present invention obtains a conversion factor for converting a radiation measurement value into radioactivity from contamination distribution data of waste. The radioactivity evaluation apparatus according to the present invention can obtain this conversion factor for each waste and calculate the radioactivity for each waste. For this reason, the radioactivity evaluation apparatus according to the present invention can accurately evaluate the radioactivity of the waste by reflecting the actual contamination distribution of the waste.

A radioactivity evaluation apparatus according to an embodiment of the present invention will be described below with reference to the drawings. In the following examples, an example will be described in which the waste generated from a nuclear power plant is a dismantled product that is generated as the facility is dismantled. In the drawings used in this specification, the same or corresponding components are denoted by the same reference numerals, and repeated description of these components may be omitted.

A radioactivity evaluation device according to Example 1 of the present invention will be described.

FIG. 1 is a diagram showing the configuration of a radioactivity evaluation apparatus according to this embodiment.

The radioactivity evaluation apparatus according to this embodiment includes a contamination distribution analysis device 11 , a contamination distribution database 21 , a dismantling plan analysis device 12 , and a dismantled CAD database 22 .

The contamination distribution analysis device 11 is a device for estimating the contamination distribution status of a nuclear power plant before it is dismantled. The contamination distribution analysis device 11 outputs contamination distribution data as an analysis result.

The contamination distribution database 21 stores the contamination distribution data output by the contamination distribution analysis device 11 .

The dismantling plan analysis device 12 is a device that analyzes and obtains a dismantling plan such as a dismantling method, a size of a dismantled object, and a construction procedure before dismantling a nuclear power plant. The dismantling plan analysis device 12 outputs CAD data of the dismantled object (dismantled object CAD data) as part of the analysis result. The dismantled object CAD data includes data on the shape and material of the dismantled object. The data about the shape of the dismantled object also include the dimensions of the dismantled object. The dismantling plan analysis device 12 is also a shape data acquisition device that acquires data (shape data) on the shape of the dismantled object from the dismantling plan.

The dismantled object CAD database 22 stores the dismantled object CAD data output by the dismantling plan analysis device 12 .

The contamination distribution data is obtained corresponding to the CAD data of the dismantled product. That is, the contamination distribution analysis device 11 can obtain the contamination distribution (distribution of radioactivity or radiation dose rate) for each dismantled object obtained by the dismantling plan analysis device 12 . The contamination distribution analysis device 11 is a contamination distribution data acquisition device that acquires contamination distribution data of dismantled objects.

The radioactivity evaluation apparatus according to this embodiment further includes a conversion factor analysis device 13 and a conversion factor database 23 .

The conversion factor analyzer 13 uses the contamination distribution data and the CAD data of the dismantled object as input data, performs radiation analysis from generation to detection of radiation, and obtains the conversion factor of the dismantled object based on the results of this radiation analysis. be. The conversion factor analysis device 13 obtains a conversion factor (conversion factor for each dismantled object) corresponding to the CAD data of the dismantled object.

The conversion factor is a factor represented by the counting rate (cps: count per sec) of radiation incident on the radiation detector per unit radioactivity (Bq), and is a factor for converting radiation measurement values into radioactivity. . By preparing a conversion factor in advance, the radioactivity evaluation apparatus can convert the count rate into radioactivity when the count rate, which is the result of radiation measurement, is obtained. This conversion factor varies depending on the shape and material of the object to be measured. Therefore, the conversion factor analysis device 13 obtains a conversion factor corresponding to the CAD data of the dismantled object, that is, a conversion factor for each dismantled object obtained by the dismantling plan analysis device 12 .

The conversion factor database 23 stores the conversion factor of the demolished object obtained by the conversion factor analysis device 13 .

The radioactivity evaluation apparatus according to this embodiment further includes a radiation measurement device 101, a measurement data collection device 102, a measurement database 121, a radioactivity calculation device 103, a radioactivity evaluation result output device 104, and a link information database 26. Prepare.

The radiation measuring device 101 has a radiation detector and measures the radiation of the dismantled object 51 generated from the nuclear power plant. The radiation detector measures the counting rate of radiation (mainly gamma rays) incident from the dismantled object 51 .

The measurement data collection device 102 collects the radiation (count rate) measured by the radiation measurement device 101 .

The measurement database 121 stores measurement data of the radiation measurement device 101 collected by the measurement data collection device 102 .

The radioactivity calculation device 103 inputs radiation data of the disassembled object 51 measured by the radiation measurement device 101 (radiation measurement data of the disassembled object 51) and CAD data of the disassembled object 51 corresponding to the disassembled object 51, and calculates radiation measurement data. , the radioactivity of the disassembled material 51 is calculated. Specifically, the radioactivity calculation device 103 calculates the radiation measurement data of the demolished object 51 and the conversion factor of this demolished object 51 (more precisely, the conversion factor of the demolished object CAD data corresponding to this demolished object 51). is used to calculate the radioactivity of this dismantled product 51 . The radioactivity calculation device 103 can calculate radioactivity for each dismantled object 51 . It is called a “target demolished object 51”.

The radioactivity evaluation result output device 104 outputs the radioactivity of the dismantled object 51 calculated by the radioactivity calculation device 103 . The radioactivity evaluation result output device 104 can output the data calculated by the radioactivity evaluation device, such as the contamination distribution data obtained by the contamination distribution analysis device 11 and the CAD data of the demolished object obtained by the dismantling plan analysis device 12. .

The link information database 26 stores link information (for example, ID information) that associates the dismantled object 51 measured by the radiation measuring device 101 with the dismantled object CAD data corresponding to the dismantled object 51 . This link information will be described later.

FIG. 2 is a diagram showing an example of a processing flow for evaluating the radioactivity of waste using the radioactivity evaluation device according to this embodiment. In FIG. 2, the flow of processing is indicated by solid arrows, and the flow of data is indicated by dashed arrows. The processing flow shown in FIG. 2 includes a decommissioning planning step (step 1100), a conversion factor analysis step (step 1200), a dismantling step (step 1300), a radiation measurement step (step 1400), and a radioactivity evaluation step (step 1500). have

First, in step 1001 , a contamination survey is conducted before the nuclear power plant is dismantled, and survey data is stored in the survey database 24 .

Next, the decommissioning planning step of step 1100 is executed.

In step 1101, the contamination distribution analysis device 11 performs a simulation based on the survey data of the contamination survey to estimate the contamination distribution, and stores the estimated contamination distribution data (contamination distribution data) in the contamination distribution database 21. store in An existing technique can be used for the simulation for estimating the contamination distribution. The contamination distribution analysis device 11 obtains, for example, contamination at the survey point from the survey data of the contamination survey, and obtains contamination at points other than the survey point from the contamination at the survey point (for example, by interpolation), thereby obtaining the contamination distribution to estimate Alternatively, the contamination distribution analysis device 11 can estimate the contamination distribution using the operation history of the nuclear power plant.

At step 1102, the dismantling plan analysis device 12 performs a simulation of the dismantling plan for the nuclear power plant based on the contamination distribution data, and generates dismantling plan data. The dismantling plan analysis device 12 draws up a dismantling plan including a dismantling method, a dismantling procedure, a transport procedure for dismantled objects, etc., in consideration of contamination distribution data, work efficiency, exposure dose, etc., in the dismantling plan simulation, and prepares a dismantling plan. Generate data. The dismantling plan analysis device 12 stores the generated dismantling plan data in the dismantling plan database 25 .

At step 1103 , the dismantling plan analysis device 12 generates a model of the dismantled object as CAD data using the generated dismantling plan data, and stores the generated CAD data (dismantled object CAD data) in the dismantled object CAD database 22 . A unique identification number is assigned to each dismantled product CAD data.

Next, the conversion factor analysis step of step 1200 is performed. The processing of the conversion factor analysis step is performed by the conversion factor analysis device 13 . The conversion factor analysis device 13 obtains a conversion factor for each dismantled object, that is, for each dismantled object CAD data.

At step 1201 , the conversion factor analysis device 13 converts the dismantled CAD data of the dismantled object for which the conversion factor is to be obtained into input data (dismantled object analysis model) for the simulation executed by the conversion factor analysis device 13 .

In step 1202, in parallel with the processing in step 1201, the conversion factor analysis device 13 retrieves the CAD data of the dismantled object for which the conversion factor is to be obtained from the contamination distribution database 21 (that is, the dismantled object converted into the analysis model in step 1201). CAD data) to extract contamination distribution data. The conversion factor analysis device 13 then converts the extracted contamination distribution data into input data (radiation source model) for the simulation executed by the conversion factor analysis device 13 .

A radiation source model is generated as a distribution of radioactivity (Bq). The value of radioactivity in the radiation source model may be a distribution of absolute values of radioactivity with respect to space, or a distribution of radioactivity represented by relative values. When the distribution of radioactivity is represented by relative values, the shape of the graph when the distribution of radioactivity is represented by a graph (distribution shape) is defined, and the values of the distribution are relative values.

At step 1203, the conversion factor analysis device 13 performs a simulation using the demolition analysis model and the radiation source model, analyzes the transport of radiation emitted from the radiation source model for the demolition analysis model, and calculates the count rate (cps ). The conversion factor analyzer 13 uses, for example, a Monte Carlo simulation code, which is often used for radiation transport calculations, for the simulation. The conversion factor analysis device 13 can also use a simple shielding calculation code when the Monte Carlo simulation code takes a long time to calculate.

At step 1204 , the conversion factor analyzer 13 calculates the conversion factor ε from the counting rate (cps) obtained from the simulation at step 1203 and stores the calculated conversion factor ε in the conversion factor database 23 . The conversion factor analysis device 13 can calculate the conversion factor ε using an existing method.

The conversion factor analysis device 13 calculates a conversion factor ε for each dismantled object (dismantled object CAD data) and stores the calculated conversion factor ε in the conversion factor database 23 in association with the dismantled object (dismantled object CAD data). Further, as described above, the conversion factor analyzer 13 can use the distribution of radioactivity represented by relative values as the radiation source model (contamination distribution data) when calculating the conversion factor.

Next, the dismantling step of step 1300 will be described. The dismantling step is executed after the decommissioning planning step (step 1100), and may be executed in parallel with the conversion factor analysis step (step 1200), for example.

In step 1301 , workers dismantle (for example, cut, process, etc.) the nuclear power plant based on the dismantling plan data stored in the dismantling plan database 25 . Due to the dismantling in step 1301, a dismantled object 51 is generated. Since this dismantled object 51 is generated based on the dismantling plan data, the corresponding dismantled object CAD data exists.

At step 1302 , the radiation measuring device 101 assigns an identifier to the dismantled object 51 . The identifier assigned to the dismantled object 51 can be displayed by, for example, a two-dimensional barcode.

At step 1303 , the radiation measuring apparatus 101 generates link information that associates the identifier assigned to the dismantled object 51 with the dismantled object CAD data corresponding to this dismantled object 51 . This link information is information that associates the dismantled object 51 specified by the identifier with the dismantled object CAD data corresponding to the dismantled object 51 having this identifier, and is, for example, ID information. Then, the radiation measuring apparatus 101 stores this link information in the link information database 26. FIG. For example, if the identifier assigned to the disassembled object 51 is displayed as a two-dimensional barcode, the link information is set by registering the identification number assigned to the dismantled object CAD data in the two-dimensional barcode. can do. As described above, a unique identification number is assigned to the dismantled CAD data.

Next, the radiation measurement step of step 1400 will be described. In the radiation measurement step, radiation measurement is performed on the dismantled object 51 generated in the dismantling step (step 1300). The dismantled object 51 is generated whenever the dismantling step (step 1300) is executed. Therefore, the radiation measurement step is performed at any time after the dismantling step is started.

Hereinafter, the dismantled object 51 whose radiation is to be measured (that is, the dismantled object 51 whose radioactivity is to be evaluated) will be referred to as a “target dismantled object 51”.

At step 1401, the worker carries the target dismantled object 51 into the radiation measurement facility.

In step 1402, the worker recognizes the identifier assigned to the target dismantled object 51 and confirms the target dismantled object 51 for which radiation measurement is to be performed.

At step 1403 , the worker installs the target dismantled object 51 on the radiation measuring device 101 .

In step 1404 , the radiation measurement device 101 performs radiation measurement on the target dismantled object 51 . Radiation measurement data of the object to be demolished 51 measured by the radiation measurement device 101 is collected by the measurement data collection device 102 and stored in the measurement database 121 .

At step 1405 , the radiation measuring apparatus 101 extracts the link information of the target dismantled object 51 from the link information database 26 using the identifier given to the target dismantled object 51 . Then, the radiation measuring device 101 associates the link information of the target dismantled object 51 with the radiation measurement data of the target dismantled object 51 . By the processing of step 1405 , the radiation measurement data of the target dismantled object 51 and the dismantled object CAD data corresponding to the target dismantled object 51 are associated.

Thereafter, the radioactivity evaluation step of step 1500 is performed.

At step 1501 , the radioactivity calculation device 103 uses the link information extracted at step 1405 to read the conversion factor ε for the dismantled object CAD data corresponding to the target dismantled object 51 from the conversion factor database 23 .

In step 1502, the radioactivity calculation device 103 uses the conversion factor ε read from the conversion factor database 23 to calculate the radioactivity of the target disassembled object 51 from the radiation measurement data of the target disassembled object 51 measured by the radiation measurement device 101. calculate. The radioactivity calculation device 103 can calculate radioactivity for the target dismantled object 51 , that is, for each individual dismantled object 51 .

FIG. 3 is a diagram showing an example of the configuration of the conversion factor analysis device 13. As shown in FIG. The conversion factor analysis device 13 includes an analysis model conversion input device 130 , a radiation analysis device 140 and a conversion factor calculation device 145 .

The analytical model conversion input device 130 includes a data conversion device 131 and a radiation source model conversion device 132 .

The data conversion device 131 inputs CAD data (dismantled object CAD data 72) of the dismantled object 51 for which conversion coefficients are to be obtained, and converts the input dismantled object CAD data 72 into input data (dismantled object analysis model 141) to the radiation analysis device 140. ). The data conversion device 131 has a function of converting the data on the shape and material of the dismantled object 51 contained in the CAD data 72 of the dismantled object in accordance with the input format to the radiation analysis device 140 and generating the dismantled object analysis model 141. . The dismantled object analysis model 141 is input data for the simulation performed by the radiation analysis apparatus 140 in step 1203 of FIG.

The radiation source model conversion device 132 inputs the contamination distribution data 71 for the dismantled CAD data 72 of the dismantled object 51 for which the conversion coefficient is to be obtained, and converts the input contamination distribution data 71 into the input data (radiation source model 142). The radiation source model conversion device 132 has a function of converting the radiation source intensity information and the spatial distribution information of the contamination distribution data 71 according to the input format to the radiation analysis device 140 and generating a radiation source model 142 . As already described, the radiation source distribution (radioactivity value) in the radiation source model 142 may be a distribution of absolute values of radioactivity with respect to space, or a distribution of radioactivity represented by relative values. may The radiation source model 142 is input data for the simulation performed by the radiation analysis apparatus 140 in step 1203 of FIG.

The radiation analysis apparatus 140 inputs the dismantled object analysis model 141 and the radiation source model 142 as described above. A radiation detector model 143 is further set in the radiation analysis apparatus 140 . The radiation detector model 143 is an analysis model of the radiation detector provided in the radiation measuring apparatus 101, and is created based on the specifications of this radiation detector.

The radiation analysis apparatus 140 executes a simulation using the dismantled object analysis model 141 , the radiation source model 142 and the radiation detector model 143 to analyze the transport of radiation emitted from the radiation source model 142 . Specifically, the radiation detector model 143 is given a position relative to the dismantled object analysis model 141, the dismantled object analysis model 141 is given a radiation source model 142, and the radiation analysis apparatus 140 receives the The transport of emitted radiation 144 (eg, gamma rays) is analyzed, and the number of counts per unit time (counting rate) of radiation 144 incident on the radiation detector model 143 is obtained.

The conversion factor calculation device 145 calculates a conversion factor ε from the counting rate (cps) obtained by the radiation analysis device 140 and stores the calculated conversion factor ε in the conversion factor database 23 . The conversion factor database 23 stores a conversion factor ε for each dismantled object 51 (dismantled object CAD data 72). The conversion factor calculation device 145 can calculate the conversion factor ε using an existing method.

The radioactivity evaluation apparatus according to the present embodiment has the configuration described above, and the radioactivity of dismantled materials (waste) generated from a nuclear power plant is reflected in the actual contamination distribution of the dismantled materials. Each object 51 can be evaluated accurately. In this embodiment, the conversion factor analyzer 13 calculates the conversion factor ε using the contamination distribution data 71 and the CAD data 72 of the dismantled object. and can be reasonably evaluated.

A radioactivity evaluation apparatus according to Example 2 of the present invention will be described with reference to FIG. In the following, the radioactivity evaluation apparatus according to the present embodiment will be mainly described in terms of differences from the radioactivity evaluation apparatus according to the first embodiment. The radioactivity evaluation apparatus according to Example 1 acquires data on the shape of the dismantled object 51 from the dismantled object CAD data 72 generated using the dismantling planning data. The dismantling plan data is generated by the dismantling plan analysis device 12 through a dismantling plan simulation.

The radioactivity evaluation apparatus according to this embodiment acquires data (shape data) on the shape of the dismantled object 51 by measuring the dismantled object 51 rather than from the dismantling planning data. The radioactivity evaluation apparatus according to the present embodiment includes a shape data acquisition device, and before executing the conversion factor analysis step of step 1200 shown in FIG. do.

FIG. 4 is a diagram showing the configuration of the shape data acquisition device in this embodiment. The shape data acquisition device in this embodiment includes a shape measurement device 150, a control device 151, and a shape database 152, and acquires shape data of the demolished object 51. FIG.

The shape measuring device 150 measures the shape of the demolished object 51 . The control device 151 controls the shape measuring device 150 and acquires shape data of the demolished object 51 from the shape measuring device 150 . The shape database 152 stores the shape data of the demolished object 51 acquired by the control device 151 .

The shape measuring device 150 acquires shape data of the demolished object 51 by measuring the shape of the demolished object 51 . An arbitrary device can be used as the shape measuring device 150. For example, a laser is irradiated to a plurality of points of the demolished object 51, and shape data of the demolished object 51 is obtained from differences in arrival times of reflected signals from each point. A device that acquires point cloud data, a stereo camera that measures a shape using parallax, or the like can be used. Even with a stereo camera, it is common to acquire the shape data of the demolished object 51 as point group data. In this embodiment, it is assumed that the shape data of the demolished object 51 stored in the shape database 152 is represented by a point group.

The shape data acquisition device in this embodiment further includes a point cloud CAD data conversion device 153 . The point cloud CAD data conversion device 153 inputs the shape data (point cloud data) of the demolished object 51 stored in the shape database 152, and converts the input point cloud data into CAD data. Then, the point cloud CAD data conversion device 153 stores this CAD data in the dismantled object CAD database 22 as the dismantled object CAD data 72 . This dismantled product CAD data 72 can be handled in the same manner as the dismantled product CAD data 72 in the first embodiment.

In this embodiment, the shape data of the demolished object 51 is obtained by measuring the demolished object 51 with the shape measuring device 150 rather than from the dismantling plan data. For this reason, in the radioactivity evaluation apparatus according to this embodiment, for example, when the disassembled object 51 has a different shape from the dismantling plan data at the time of dismantling in the dismantling step of FIG. However, the radioactivity of the dismantled object 51 can be accurately evaluated by obtaining the conversion factor ε of the dismantled object 51 .

Further, in this embodiment, when dismantling the dismantled object 51, the shape of the dismantled object 51 can be measured by the shape measuring device 150 to obtain the dismantled object CAD data 72. FIG. Then, in the radiation measurement step (step 1400 in FIG. 2), the shape of the target dismantled object 51 is measured by the shape measuring device 150 before the radiation measurement (step 1404) is performed on the target dismantled object 51, and the CAD data of the disassembled object is obtained. 72 can be acquired, and this dismantled object CAD data 72 can be compared and collated with the dismantled object CAD data 72 obtained at the time of dismantling. By collating this data, the radiation measurement data of the target dismantled object 51 and the dismantled object CAD data 72 corresponding to the target dismantled object 51 can be associated (step 1405).

The radioactivity evaluation apparatus according to the present embodiment has the configuration described above, and by directly measuring the shape of the dismantled object, even if the dismantled object has a different shape than planned, the radioactivity of the dismantled object can be evaluated. Accurate and rational evaluation is possible in accordance with the actual condition of the object. Moreover, even when the dismantling plan analysis device 12 cannot be used, the radioactivity evaluation apparatus according to the present embodiment obtains shape data by directly measuring the shape of the dismantled object. Radioactivity of dismantled objects can be evaluated immediately. In addition, by measuring the shape of the dismantled object at the time of dismantling and radiation measurement, it is possible to associate the dismantled object with the CAD data of the dismantled object, and to evaluate the radioactivity of the object to be dismantled without mistaking it for other dismantled objects.

A radioactivity evaluation apparatus according to Example 3 of the present invention will be described with reference to FIG. In the following, the radioactivity evaluation apparatus according to the present embodiment will be mainly described in terms of differences from the radioactivity evaluation apparatus according to the first embodiment. In the radioactivity evaluation apparatus according to Example 1, the contamination distribution analyzer 11 estimates the contamination distribution data 71 .

The radioactivity evaluation apparatus according to the present embodiment acquires the contamination distribution data 71 by measuring the dismantled object 51 instead of estimating the contamination distribution data 71 with the contamination distribution analysis apparatus 11 . The radioactivity evaluation apparatus according to this embodiment includes a radiation measuring instrument, and before executing the conversion factor analysis step of step 1200 shown in FIG. Obtain distribution data 71 .

FIG. 5 is a diagram showing the radiation measuring device 161 that acquires the contamination distribution data 71 of the dismantled object 51. As shown in FIG. The radiation measuring device 161 measures the measurement points set on the surface of the demolished object 51 while moving along the arrows in FIG. 5, for example. The radiation measuring device 161 is a contamination distribution data acquisition device that acquires contamination distribution data of the dismantled object 51, and can be configured using, for example, a survey meter that measures the dose rate.

In the radioactivity evaluation apparatus according to this embodiment, the radiation measuring instrument 161 generates contamination distribution data 71 from measured values at each measurement point of the dismantled object 51 . The contamination distribution data 71 may be a distribution of absolute values of radioactivity with respect to space, or a distribution of radioactivity represented by relative values. This contamination distribution data 71 can be handled in the same manner as the contamination distribution data 71 in the first embodiment.

The radioactivity evaluation apparatus according to the present embodiment has the configuration described above, and directly measures the contamination distribution of the dismantled object. Even if the contamination distribution obtained by the method cannot be used, the radioactivity of the dismantled material can be evaluated accurately and rationally according to the actual state of the dismantled material.

A radioactivity evaluation apparatus according to Example 4 of the present invention will be described with reference to FIG. In the following, the radioactivity evaluation apparatus according to the present embodiment will be mainly described in terms of differences from the radioactivity evaluation apparatus according to the first embodiment. In the radioactivity evaluation apparatus according to Example 1, the contamination distribution analyzer 11 estimates the contamination distribution data 71 .

The radioactivity evaluation apparatus according to the present embodiment acquires the contamination distribution data 71 not by estimating the contamination distribution data 71 by the contamination distribution analysis apparatus 11, but by using monitoring information of the corrosive environment in the reactor system and evaluation results based thereon. .

FIG. 6 is a diagram showing the configuration of the radioactivity evaluation apparatus according to this embodiment. The radioactivity evaluation apparatus according to the present embodiment is the radioactivity evaluation apparatus according to Embodiment 1, wherein the contamination distribution data acquiring device for acquiring the contamination distribution data of the dismantled object includes a corrosion potential measuring device 201 and a corrosion potential evaluating device 202 .

The corrosion potential measuring device 201 is a device that measures the corrosion potential in the reactor system of the nuclear power plant. A device for measuring the corrosion potential is installed at the corrosion potential measurement point in the reactor system. This device can be used as the corrosion potential measuring device 201 in this embodiment.

The corrosion potential evaluation device 202 is a device that obtains the distribution of corrosion potential in the reactor system based on the measurement result of the corrosion potential measurement device 201 . The corrosion potential evaluation device 202 obtains the corrosion potential at points other than the corrosion potential measurement points in the reactor system, for example, by interpolating the corrosion potential values at the corrosion potential measurement points. Since it is difficult to install the corrosion potential measurement device 201 throughout the reactor system, the corrosion potential measurement device 201 analyzes the corrosion potential measurement points at the corrosion potential measurement points, and analyzes the corrosion potential measurement device 202 to determine the Obtain the distribution of the corrosion potential of The corrosion potential evaluation device 202 obtains the distribution of the corrosion potential in the reactor system using an existing method based on the corrosion potential at the corrosion potential measurement points and the corrosion potentials at points other than the corrosion potential measurement points.

The corrosion potential is an index of the corrosive environment in the nuclear reactor, and is correlated with the deposition rate of Co-60, which is a radionuclide. Therefore, the Co-60 adhesion amount distribution can be estimated from the corrosion potential distribution.

The corrosion potential evaluation device 202 can estimate the Co-60 adhesion amount distribution from the corrosion potential distribution using an existing method, and obtain the contamination distribution data 71 from the Co-60 adhesion amount distribution.

The corrosion potential measuring device 201 stores the measured corrosion potential in the contamination distribution database 21 . The corrosion potential evaluation device 202 stores calculated data such as the contamination distribution data 71 in the contamination distribution database 21 . This contamination distribution data 71 can be handled in the same manner as the contamination distribution data 71 in the first embodiment.

The radioactivity evaluation apparatus according to the present embodiment has the configuration described above, and utilizes the monitoring information of the corrosive environment in the reactor system and the evaluation results based on this information to determine the actual state of the disassembled material. can be evaluated accurately and rationally in accordance with

A radioactivity evaluation apparatus according to Example 5 of the present invention will be described with reference to FIG. In the following, the radioactivity evaluation apparatus according to the present embodiment will be mainly described in terms of differences from the radioactivity evaluation apparatus according to the first embodiment.

The radioactivity evaluation apparatus according to this embodiment can improve the accuracy of the contamination distribution data 71 obtained by accumulating past data and learning the relationship between the reactor operation data and the contamination distribution data 71 .

FIG. 7 is a diagram showing the configuration of the radioactivity evaluation apparatus according to this embodiment. The radioactivity evaluation apparatus according to the present embodiment is the same as the radioactivity evaluation apparatus according to the first embodiment, and further includes a radioactivity evaluation performance database 302 , a reactor operation database 303 , and a learning estimation device 301 .

The radioactivity evaluation performance database 302 stores radioactivity evaluation performance data. The radioactivity evaluation performance data includes the contamination distribution data 71, the dismantling plan data, the shape data of the dismantled objects 51, and the radiation calculated by the radioactivity calculation device 103 for each of the dismantled objects 51, which are data obtained in the past. data on radioactivity, measured data on radiation distribution, and measured data on distribution of radioactive contamination.

The reactor operation database 303 stores reactor operation data, which is the operation data of the nuclear reactor of the nuclear power plant. The nuclear reactor operation data includes data on the past operation results of the nuclear reactor, such as the operation history of the nuclear reactor and the time when the equipment of the nuclear reactor was replaced.

The learning estimation device 301 is a device that inputs the reactor operation data and radioactivity evaluation performance data, which are past performance data, and learns the relationship between the reactor operation data and the contamination distribution data 71 by a method such as deep learning. is. The learning estimation device 301 holds the relationship between the learned reactor operation data and the contamination distribution data 71 as learning data. The learning estimation device 301 inputs the reactor operation data, the contamination distribution data 71, and the dismantled CAD data 72 of this nuclear power plant when evaluating the radioactivity of the dismantled object 51 generated from the nuclear power plant, and learns. By using the data, the contamination distribution data 71 can be obtained with high accuracy.

That is, the learning estimation device 301 learns the relationship between the reactor operation data and the contamination distribution data 71 from the previously obtained reactor operation data and the contamination distribution data 71, and uses this learning data to The contamination distribution data 71 of the disassembled material 51 can be obtained with high accuracy from the reactor operation data of the nuclear power plant for evaluating the radioactivity of the waste. If the contamination distribution data 71 is highly accurate, the accuracy of the conversion factor ε obtained by the conversion factor analysis device 13 can be improved, and the radioactivity of the dismantled object 51 can be evaluated more accurately.

For example, if the operating history of a nuclear reactor that is newly subject to decommissioning is similar to the operating history of a nuclear reactor that has undergone decommissioning in the past, the contamination distribution data 71 will show similar trends. It is considered to indicate For this reason, if the radiation distribution or contamination distribution of the dismantled object 51 is obtained by actually measuring it in the decommissioning implemented in the past, and this is learned by associating it with the operation history, the accuracy of the contamination distribution data 71 will be further improved, and the conversion This leads to further improvement in the accuracy of the coefficient ε.

The radioactivity evaluation apparatus according to this embodiment can improve the accuracy of the contamination distribution data and the conversion factor by accumulating and learning the results of dealing with the decommissioning of nuclear power plants, and the radioactivity of dismantled objects can be improved. It can be evaluated more accurately and rationally according to the actual condition of the dismantled object.

It should be noted that the present invention is not limited to the above embodiments, and various modifications are possible. For example, the above embodiments have been described in detail in order to facilitate understanding of the present invention, and the present invention is not necessarily limited to aspects having all the described configurations. Also, part of the configuration of one embodiment can be replaced with the configuration of another embodiment. It is also possible to add the configuration of another embodiment to the configuration of one embodiment. Moreover, it is possible to delete a part of the configuration of each embodiment, or to add or replace another configuration.

11... Contamination distribution analysis device, 12... Dismantling plan analysis device, 13... Conversion factor analysis device, 21... Contamination distribution database, 22... Dismantled object CAD database, 23... Conversion factor database, 24... Survey database, 25... Dismantling plan database , 26... Link information database, 51... Disassembled object, 71... Contamination distribution data, 72... Disassembled object CAD data, 101... Radiation measuring device, 102... Measurement data collecting device, 103... Radioactivity calculating device, 104... Radioactivity evaluation Result output device 121 Measurement database 130 Analysis model conversion input device 131 Data conversion device 132 Radiation source model conversion device 140 Radiation analysis device 141 Demolition analysis model 142 Radiation source model 143... Radiation detector model, 144... Radiation, 145... Conversion factor calculation device, 150... Shape measurement device, 151... Control device, 152... Shape database, 153... Point group CAD data conversion device, 161... Radiation measuring device, 201 ... Corrosion potential measuring device, 202 ... Corrosion potential evaluating device, 301 ... Learning estimating device, 302 ... Radioactivity evaluation performance database, 303 ... Reactor operation database.

Claims (9)

A shape data acquisition device for acquiring shape data of waste generated from a nuclear power plant;
a contamination distribution data acquisition device for acquiring contamination distribution data of the waste;
a conversion factor analysis device for inputting the shape data and the contamination distribution data and performing radiation analysis to obtain a conversion factor for converting the radiation measurement value into radioactivity for the waste;
a radiation measuring device for measuring the radiation of the waste;
a radioactivity calculation device that calculates the radioactivity of the waste using the radiation data of the waste measured by the radiation measuring device and the conversion factor for the waste;
A radioactivity evaluation device comprising: The shape data acquisition device is a dismantling plan analysis device,
The dismantling plan analysis device performs a simulation of the dismantling plan of the nuclear power plant to generate CAD data including the shape data.
The radioactivity evaluation device according to claim 1. The shape data acquisition device includes a shape measurement device that measures the shape of the waste,
The shape measuring device acquires the shape data as point cloud data by measuring the shape of the waste.
The radioactivity evaluation device according to claim 1. The radiation measuring device generates link information that associates an identifier assigned to the waste with the CAD data corresponding to the waste having the identifier.
The radioactivity evaluation device according to claim 2. The contamination distribution data acquisition device is a contamination distribution analysis device,
The contamination distribution analysis device performs a simulation based on the contamination status of the nuclear power plant to acquire the contamination distribution data.
The radioactivity evaluation device according to claim 1. The contamination distribution data acquisition device is a radiation meter,
The radiation measuring device acquires the contamination distribution data from measurements obtained by measuring the waste.
The radioactivity evaluation device according to claim 1. The contamination distribution data acquisition device includes a corrosion potential measurement device and a corrosion potential evaluation device,
The corrosion potential measuring device measures the corrosion potential inside the nuclear power generation facility,
The corrosion potential evaluation device acquires the contamination distribution data from the distribution of the corrosion potential.
The radioactivity evaluation device according to claim 1. A radioactivity evaluation performance database that stores the contamination distribution data obtained in the past;
a reactor operation database storing reactor operation data, which is the operation data of the reactor of the nuclear power plant;
Learning for learning the relationship between the reactor operation data and the contamination distribution data by inputting the reactor operation data stored in the reactor operation database and the contamination distribution data stored in the radioactivity evaluation database an estimating device;
with
The learning estimation device utilizes the relationship between the learned reactor operation data and the contamination distribution data to evaluate the radioactivity of the waste from the reactor operation data of the nuclear power plant to the contamination distribution data. ask for
The radioactivity evaluation device according to claim 1. The conversion factor analysis device uses radioactivity distribution data expressed in relative values as the contamination distribution data when obtaining the conversion factor.
The radioactivity evaluation device according to claim 1.

Images