JP2013108815A - Three-dimensional radioactivity measurement device, radiation handling work management system and radiation handling work management method - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a three-dimensional radioactivity measurement device capable of measuring an accurate radioactivity distribution in a radiation handling work environment.SOLUTION: A three-dimensional radioactivity measurement device 12 according to an embodiment comprises: a structure DB 8 for storing structure information for each of multiple structures; a visible camera 1 for shooting each two-dimensional visible image of the structures; a gamma camera 2 for measuring an intensity distribution of radiation entering from a shooting direction; a shooting position storage part 3; a three-dimensional structure image generation part 4 for calculating each shape and position of the structures from multiple visible images; a surface radiation distribution conversion part 5 for converting the visible images and gamma camera images into radiation intensity at each shaped surface position of the structures; a surface radiation distribution different section extraction part 6 for comparing each radiation intensity on the shaped surfaces of the structures with the radiation distribution measured by the gamma camera 2 and extracting a section with the different intensity at a position on the same surface; and a radioactivity estimation part 7 for estimating a radiation generating position with respect to the extracted section and executing conversion into an amount of radioactivity.

Description

  Embodiments described herein relate generally to a radioactivity three-dimensional measurement apparatus, a radiation handling work management system, and a radiation handling work management method.

  At the time of dismantling the nuclear plant, the radioactivity remaining inside the equipment is evaluated, and a dismantling plan is created according to the dose. For this purpose, the radiation amount on the surface of the equipment is measured in advance with a radiation sensor using a measuring device and a measurement system, and the amount of radioactivity on the building surface, equipment surface and inside is estimated.

  In addition, the radiation source position is evaluated in advance, the exposure is predicted at the time of demolition planning, and radiation source information is incorporated into CAD (Computer Aided Design) information of buildings, etc., and the radiation source, equipment layout data, and movement data Based on the above, it is disclosed that a radiation distribution around a work is evaluated by simulation and the distribution is presented to an operator.

  In addition, a dosimeter is installed at the site during work, changes in dose associated with the work are monitored in real time, multiple dose measurement devices are installed around the work site, and the position and dose data of the measurement devices are transmitted wirelessly. In addition, it is disclosed to visualize the radiation distribution of a work place in consideration of surrounding structure information.

  In addition, it is disclosed that a radiation incident distribution at a measurement position is measured by a device called a gamma camera, a distance is calculated from a stereoscopic view of a visible camera, and a radioactivity distribution at an object position is obtained.

JP-A-2005-49148 JP 2008-26185 A US Pat. No. 6,782,123

  The above-described radioactivity measurement apparatus, for example, uses an apparatus called a γ (gamma) camera to identify the incident direction of radiation that comes to the position where the γ camera is located, and the structure of the measurement object from that direction The radioactivity distribution on the object surface is calculated. However, it has been difficult to determine whether a radiation source is present inside the structure to be measured or attached to the surface of the structure.

  Therefore, in the above-described radioactivity measuring apparatus, when performing radiation handling work management, it is possible to measure by determining whether a radiation source is present inside a structure such as a pipe or attached to the surface. Therefore, it was difficult to predict the exact exposure dose of workers in the radiation handling work area.

  Moreover, it may be exposed by the radioactivity adhering to the gaseous radon scattered in the air between structures, and the aerosol in the air, and it was difficult to grasp | ascertain those contributions correctly.

  The problem to be solved by the present invention is to provide a radioactivity three-dimensional measurement apparatus capable of measuring an accurate radioactivity distribution in a radiation handling work environment.

  The problem to be solved by the present invention is to provide a radiation handling work management system and a radiation handling work management method capable of accurately predicting the radiation exposure dose of an operator in a radiation handling work environment.

  In order to solve the above-described problem, the radioactivity three-dimensional measurement apparatus according to the embodiment stores, for each of a plurality of structures to be measured, three-dimensional data including an installation position and a shape, and structure information including a material. A structure database, a visible camera that captures a two-dimensional visible image of the structure to be measured, and a direction that is included in the range of the angle of view of the visible camera, the same direction as the imaging direction of the visible camera A radiation camera that measures a radiation intensity distribution incident from the radiation camera to capture a radiation image, and assigns an identifier to each of the captured visible image and the radiation image, and includes a photographing position and a photographing direction for each identifier. An imaging position storage unit for storing information; a structure three-dimensionalization unit for calculating the shape and position of the structure from the plurality of visible images captured by the visible camera; A surface radiation distribution conversion unit that converts the radiation image taken simultaneously with the visible image in the visible image into a radiation intensity at the surface position in the shape of the structure calculated by the structure three-dimensional unit, and the surface Comparing the radiation intensity of the surface in the shape of the structure converted by the radiation distribution conversion unit with the radiation distribution measured by the radiation camera, the radiation intensity at the compared position of the same surface of the structure The surface radiation distribution difference site extraction unit for extracting different sites, the imaging information stored in the imaging position storage unit, and the structure database for the site extracted by the surface radiation distribution difference site extraction unit A radioactivity estimation unit that estimates a radiation generation position and converts it into a radioactivity amount from the generated structure information, That.

  In order to solve the above problems, a radiation handling work management system according to an embodiment has a structure database, a radioactivity three-dimensional measurement device, and a radiation handling work management device, and includes a work area including a plurality of structures. It is a radiation handling work management system that predicts the radiation dose in the interior. In the radiation handling work management system, the structure database stores, for each of the plurality of structures to be measured, structural information including three-dimensional data including an installation position and a shape and material, and the radioactivity 3 The dimension measuring device is arranged so as to be included in a range of an angle of view of the visible camera, a visible camera that captures a two-dimensional visible image of the structure to be measured, A radiation camera that measures a radiation intensity distribution incident from the same direction and captures a radiation image, and assigns an identifier to each of the captured visible image and the radiation image, and sets an imaging position and an imaging direction for each identifier. A shooting position storage unit that stores shooting information including the structure 3 that calculates the shape and position of the structure from the plurality of visible images shot by the visible camera; A surface for converting the radiation image taken simultaneously with the normalizing unit and the plurality of visible images into a radiation intensity at the surface position in the shape of the structure calculated by the three-dimensional structure unit The radiation distribution conversion part, the surface radiation intensity in the shape of the structure converted by the surface radiation distribution conversion part, and the radiation distribution measured by the radiation camera were compared, and the structure was compared. The surface radiation distribution difference site extraction unit that extracts sites having different radiation intensities at the same surface position, and the imaging information stored in the imaging position storage unit for the site extracted by the surface radiation distribution difference site extraction unit And a radioactivity estimation unit that estimates the radiation generation position and converts it into a radioactivity amount from the structure information stored in the structure database. The radiation handling work management device includes a work condition input unit for inputting work information including an operation position and work time in an area for work management, and a plurality of the structures measured by the radioactivity three-dimensional measurement device. A radioactivity distribution database for storing the radioactivity distribution data, and extracting the radioactivity distribution data based on the work information input from the work condition input unit from a plurality of the structures, and extracting the extracted radiation An exposure dose analysis unit that calculates an exposure dose in the work area based on the performance distribution data.

  Moreover, in order to solve the said subject, the radiation handling operation | work management method of embodiment stores the structural information containing the three-dimensional data containing an installation position and a shape, and material for every some structure used as a measuring object. A radiation handling work management method in a radiation handling work management system that has a structure database, a radioactivity three-dimensional measurement device, and a radiation handling work management device, and that predicts the radiation dose in a work area including a plurality of structures. is there. In the radiation handling work management method, the visible camera of the radioactivity three-dimensional measuring apparatus captures a two-dimensional visible image of the structure to be measured, and a view angle of the visible camera. Radiation image radiographing processing step in which the radiation camera of the radioactivity three-dimensional measuring device arranged to be included in the range measures a radiation intensity distribution incident from the same direction as the imaging direction of the visible camera and captures a radiographic image And the radioactivity three-dimensional measuring device assigns an identifier to each of the captured visible image and the radiographic image, and stores imaging information including an imaging position and an imaging direction in the imaging position storage unit for each identifier. An imaging position storage processing step, and the radioactivity three-dimensional measurement device is configured to detect the shape and the shape of the structure from the plurality of visible images captured by the visible camera. A structure three-dimensionalization processing step for calculating a position, and the radioactivity three-dimensional measurement apparatus, together with the radiation image captured simultaneously by the radiation image capturing processing step in the plurality of visible images, the structure 3 A surface radiation distribution conversion processing step for converting the radiation intensity at the surface position in the shape of the structure calculated by the dimensioning processing step, and the radioactivity three-dimensional measuring device is converted by the surface radiation distribution conversion processing step. The surface which extracts the site | part from which the radiation intensity differs in the position of the same surface compared with the said structure by comparing the radiation intensity of the surface in the shape of the said structure and the said radiation distribution measured with the said radiation camera Radiation distribution difference site extraction processing step and the radioactivity three-dimensional measurement apparatus extract the surface radiation distribution difference site Radiation for estimating the radiation generation position and converting it into a radioactivity amount from the imaging information stored in the imaging position storage unit and the structure information stored in the structure database for the part extracted by the physical step An operation estimation process step, an operation condition input processing step in which the radiation handling operation management device receives input of operation information including an operation position and an operation time in an area to be managed, and the radiation handling operation management device includes the radiation Radioactivity distribution data storage processing step for storing radioactivity distribution data of the plurality of structures measured by the three-dimensional measuring device in a radioactivity distribution database; and the radiation handling work management device includes the work condition input processing step. The radiation from the radioactivity distribution database based on the work information input from among the plurality of structures by And an exposure dose analysis processing step of calculating an exposure dose in the work area based on the extracted radiation distribution data.

  According to the embodiment of the radioactivity three-dimensional measurement apparatus according to the present invention, an accurate radioactivity distribution in a radiation handling work environment can be measured.

  Moreover, according to the embodiment of the radiation handling work management system and the radiation handling work management method according to the present invention, it is possible to accurately predict the radiation exposure amount of the worker in the radiation handling work environment.

The block diagram which shows the structure of 1st Embodiment of the radioactivity three-dimensional measuring apparatus which concerns on this invention. The figure which shows an example of structure DB (database) shown in FIG. The schematic diagram of the measurement of the structure by the radioactivity three-dimensional measuring apparatus of 1st Embodiment. The figure of an example which shows the image which superimposed the visible image and the gamma camera image. The schematic diagram which shows the estimated position of a radiation source. The schematic diagram which shows the estimated position of a radiation source. The flowchart which shows the measurement processing flow of the radioactivity three-dimensional measuring apparatus of 1st Embodiment. It is a measurement process flow of the radioactivity three-dimensional measuring apparatus of 1st Embodiment, Comprising: The flowchart which shows the flow following the flow of FIG. The block diagram which shows the structure of 2nd Embodiment of the radioactive three-dimensional measuring apparatus which concerns on this invention. The figure which shows the measuring method of the amount of radioactivity in the air by the radioactivity three-dimensional measuring apparatus of 2nd Embodiment. The figure which shows an example of the relationship with the distance of radiation intensity. The block diagram which shows the structure of embodiment of the radiation handling work management system which concerns on this invention. The flowchart which shows the whole processing flow of the radiation handling work management system of embodiment.

  Hereinafter, a radioactivity three-dimensional measuring apparatus and a radiation handling work management system according to embodiments of the present invention will be specifically described with reference to the drawings. Here, the same or similar parts are denoted by common reference numerals, and redundant description is omitted. Each of the following embodiments described here will be described by taking an example of a radioactivity three-dimensional measurement apparatus and a radiation handling work management system in a nuclear reactor facility.

[First Embodiment]
FIG. 1 is a configuration diagram of a first embodiment of a radioactivity three-dimensional measurement apparatus according to the present invention. FIG. 2 is a diagram illustrating an example of the structure DB (database) illustrated in FIG. Hereinafter, a first embodiment of a radioactivity three-dimensional measurement apparatus according to the present invention will be described with reference to FIGS. 1 and 2.

  As shown in FIG. 1, the radioactivity three-dimensional measuring device 12 (12a) includes a visible camera 1 (1a), a gamma camera 2 (2a), a signal processing device 11 (11a), and a structure DB (database) 8. Yes. Further, the signal processing device 11 includes an imaging position determination unit 31, an imaging position storage unit 3, a three-dimensional structure unit 4, a surface radiation distribution conversion unit 5, a surface radiation distribution difference site extraction unit 6, and a radioactivity estimation unit 7. ing. The reference numerals 1a, 2a, 11a, and 12a shown in FIG. 1 are the same parts as 1, 2, 11, and 12, and the radioactivity three-dimensional measuring device 12 at a position a shown in FIGS. Is represented as a radioactivity three-dimensional measuring device 12a. Similarly, the same applies to the symbols 1b and 1c, 2b and 2c, 11b and 11c, 12b and 12c.

  The visible camera 1 measures a two-dimensional visible image. The visible camera 1 can generate a three-dimensional configuration from a plurality of two-dimensional visible images to be photographed.

  The gamma camera 2 measures a radiation intensity distribution incident from the same direction as the visible image camera 1. The gamma camera 2 is attached in a positional relationship such that the shooting range of the gamma camera 2 is within the shooting range of the visible camera 1. The gamma camera 2 has a collimator provided with a pinhole or the like that determines the incident direction of radiation, and γ-rays incident through the collimator are detected by a γ-ray detector included in the gamma camera 2.

  The shooting position determination unit 31 determines a shooting position and a shooting direction for each shooting ID (identifier). The reference point of the imaging position for one structure is first input from outside the radioactivity three-dimensional measurement apparatus 12. Receiving this, the photographing position determination unit 31 stores photographing information serving as a reference for the photographing position in the photographing position storage unit 3. Note that the acquisition of the shooting information associated with the determination of the shooting position after the reference point, for example, is obtained by the optical gyro function of the gamma camera 2 and is reflected in each shooting information. Note that the shooting position determination unit 31 may have an optical gyro function.

  The shooting position storage unit 3 stores shooting information including these shooting positions and shooting directions (angles).

  The structure three-dimensionalization unit 4 estimates the three-dimensional structure of the target structure based on the radiation intensity distribution measured by the gamma camera 2 and the data stored in the imaging position storage unit 3.

  The surface radiation distribution conversion unit 5 converts the measurement result of the gamma camera 2 into the radiation intensity (surface radiation distribution) at the position of the structure surface calculated by the structure three-dimensionalization unit 4.

  The surface radiation distribution difference site extraction unit 6 compares the surface radiation distribution at a plurality of positions by the surface radiation distribution conversion unit 5 and extracts a site having a radiation intensity difference of a predetermined level or more.

  The structure DB (database) 8 stores structure information about structures in the area to be measured, for example, for each structure ID (identification number). The structure information includes three-dimensional data including the installation position and shape of the structure, the type of structure, material / material, and the like.

  FIG. 2 shows an example of the structure DB 8. As shown in FIG. 2, the structure DB 8 includes “installation position”, “equipment / structural material type”, “use / piping”, “material / pipe” for each structure ID (denoted as “ID” in FIG. 2). It is composed of tables such as “material” and “contamination amount / activation level”. The “contamination amount / activation amount level” indicates the radiation dose when the structure of the target ID is contaminated by radioactivity.

  For example, in FIG. 2, the structure of “ID: 1” includes “installation position: building A-area A2”, “equipment / structural material type: piping A”, “use / piping: system A”, “material”. “Material: Stainless steel” and “Contamination amount / activation amount level: XXX” are stored. Note that “installation position: building A-area A2” stores, for example, three-dimensional position data with respect to a predetermined reference position. Structure information is similarly stored in other “ID” structures as shown in FIG.

  In the configuration example illustrated in FIG. 1, the radioactivity three-dimensional measurement device 12 includes the structure DB 8, but the structure DB8 may not include the radioactivity three-dimensional measurement device 12. In such a case, the radioactivity three-dimensional measurement apparatus 12 may access the structure DB 8 provided outside via a wired or wireless LAN (Local Area Network).

  The radioactivity estimation unit 7 estimates the radiation generation position from the information of the imaging position storage unit 3, the structure three-dimensionalization unit 4, and the structure DB 8 for the part from which the difference is extracted. Furthermore, the radioactivity estimation unit 7 estimates the radiation source at the radiation generation position. For this purpose, the radioactivity estimation unit 7 includes an internal radiation calculation unit 71, a transmitted radiation calculation unit 72, and a radioactivity position convergence unit 73.

  The internal radiation calculation unit 71 estimates the radiation source candidate position based on the internal structure of the structure, the peripheral device arrangement (adjacent or surrounding structure), etc., in the region where the difference is extracted.

  Specifically, the internal radiation calculation unit 71 captures imaging information from the imaging position storage unit 3, the shape and position of the structure calculated by the structure three-dimensionalization unit 4, and the structure of the structure DB 8 for the extracted part. From the object information, calculate the dose in the structure when radioactivity is contained inside the structure.

  The transmitted radiation calculation unit 72 calculates the transmitted line intensity for each position of the gamma camera 2 at all estimated radiation source candidate positions. Further, the transmitted radiation calculation unit 72 calculates the difference at the same position on the structure surface with respect to the radiation intensity distribution (surface radiation intensity distribution) at the surface position obtained from each gamma camera image.

  The radioactivity position converging unit 73 determines the radiation source candidate position with the smallest difference in the difference in surface radiation intensity distribution at the same position on the structure surface. The radioactivity position convergence unit 73 determines whether or not the difference is equal to or greater than a predetermined value, and estimates the radioactivity amount at the radiation source candidate position from the gamma camera conversion value and the structure shielding rate.

  Hereinafter, the operation of the radioactivity three-dimensional measurement apparatus 12 shown in FIG. 1 will be described with reference to FIGS.

  FIG. 3 is a schematic diagram when the radioactivity three-dimensional measuring device is measured around the pipe 9. In addition, in FIG. 3, the cross section perpendicular | vertical to the longitudinal direction of the piping 9 whose inside is a cavity is shown.

  In FIG. 3, a radiation source 10 is placed inside the pipe 9. The radioactivity three-dimensional measuring device 12 measures a two-dimensional visible image and a radiation intensity distribution incident from the same direction while moving around the target structure (pipe 9).

  For example, in FIG. 3, it is assumed that the measurement is performed several times according to the position where the radioactivity three-dimensional measurement apparatus 12a moves. Among the several measurements, the measurement at the position a, the measurement at the position b and the position c are shown, the radioactivity three-dimensional measurement device 12a at the position a, the radioactivity three-dimensional measurement device 12b at the position b, and the position The radioactivity three-dimensional measuring device 12c in FIG. Similarly, the same applies to the visible cameras 1a, 1b and 1c (1a to 1c), the gamma cameras 2a, 2b and 2c (2a to 2c), the signal processing devices 11a, 11b and 11c (11a to 11c).

  In FIG. 3, the broken lines drawn from the visible cameras 1a, 1b, and 1c indicate the shooting range (view angle) of each camera. The gamma cameras 2a to 2c measure radiation intensity distributions incident from the same direction as the visible cameras 1a to 1c. Here, the same direction is, for example, a direction in which the shooting range of the gamma camera 2a falls within the shooting range of the visible camera 1a.

  Hereinafter, photographing at the time of measurement by the radioactivity three-dimensional measuring devices 12a to 12c will be described with reference to FIG.

  At the beginning of the measurement, the start position of the photographing position around the pipe 9 is determined. In FIG. 3, first, the position a is set as the shooting location. At this position a, a visible image of the pipe 9 is taken by the visible camera 1a. At the same time, a gamma camera image of the pipe 9 is taken by the gamma camera 2a.

  At the time of this photographing, the photographing position / photographing position is acquired by the photographing position determining unit 31 and recorded in the photographing position storage unit 3. Since the visible image and the gamma camera image captured at the position a are captured in the same direction at the same time, the surface radiation distribution conversion unit 5 adjusts the angle of view of each camera in advance. And the pixels of the gamma camera image can be displayed in a superimposed manner in association with each other.

  Next, the radioactivity three-dimensional measuring device 12a is moved from the position a to the position b. At the position b, the radioactivity three-dimensional measuring device 12b performs the same photographing and recording as the position a. Furthermore, the radioactivity three-dimensional measuring device 12c performs the same photographing and recording at the position c. Thus, photographing and recording are performed at a plurality of locations around the target structure.

  FIG. 4 shows images Pa, Pb, and Pc obtained by superimposing the visible image and the gamma camera image taken at positions a, b, and c, respectively.

  At the position a, as shown in FIG. 3, since the radiation source 10 is located approximately at the center of the angle of view of the gamma camera 2a, the captured image is approximately at the center of the image Pa as shown in the image Pa of FIG. It is displayed in light and shade indicating the radiation intensity from the first pseudo radiation source 10a. The first pseudo radiation source 10a in the image Pa is obtained by photographing the actual radiation source 10 by photographing the position a. This is photographed when the radiation from the radiation source 10 passes through the pipe 9. Is.

  At the position b, as shown in FIG. 3, since the radiation source 10 is not included in the angle of view of the visible camera 1b and the gamma camera 2b, the radiation source is not photographed as shown in the image Pb of FIG.

  On the other hand, at the position c, as shown in the image Pc of FIG. 4, the captured image is displayed on the left side of the drawing with light and shade indicating the radiation intensity from the second pseudo radiation source 10c. The second pseudo radiation source 10 c is obtained by photographing the actual radiation source 10 by photographing the position c, and is photographed when the radiation from the radiation source 10 passes through the pipe 9.

  These images Pa, Pb and Pc are shown in white in FIG. 4 except for the portion corresponding to the radiation source, but actually, for example, light and darkness, dirt on the piping surface, etc. are also photographed by photographing light. Their shades are also displayed. In general, the number of pixels of a visible camera for a visible image is one digit or more larger than the number of pixels of a gamma camera. Therefore, when the gamma camera image is superimposed on the visible image, The pixels of the visible camera 1 including the imaging range of the gamma camera 2 are assigned to the pixels of the gamma camera 2, and the images are superimposed.

  Next, the operation in which the radioactivity three-dimensional measurement apparatus according to the first embodiment estimates the actual position of the radiation source will be described.

  In general, a technique for constructing a structure photographed by visible images photographed from different positions as a three-dimensional structure is well known. The structure three-dimensionalization unit 4 uses such a well-known technique, and further, as shown in FIG. 1 described above, captured images taken at a plurality of positions by the visible camera 1 and stored in the imaging position storage unit 3. The 3D (three-dimensional) structure of the structure to be imaged is calculated using the shooting information including the shooting position and shooting direction at each position. In this case, the calculated 3D structure is the surface shape of the structure.

  Here, when the structure three-dimensionalization unit 4 calculates the surface shape of the structure using a plurality of visible images, the gamma ray intensity for each pixel of the gamma camera 2 is assigned in advance to each pixel of the visible image. Then, the surface radiation distribution conversion unit 5 converts the gamma ray intensity distribution at the 3D shape surface position for each gamma camera image by this assignment.

  The structure three-dimensionalization unit 4 obtains the distance between the structure (pipe 9) and the gamma camera 2 from the measurement result of the gamma camera 2 at each photographing position, and corrects the distance. The structure three-dimensionalization unit 4 also corrects the incident direction of the gamma ray intensity from the positional relationship between the pipe 9 and the gamma camera 2. Thereby, the surface radiation distribution conversion unit 5 can convert the gamma ray intensity distribution on the surface of the structure (pipe 9) based on the corrected distance and direction.

  FIG. 5 shows a position where the radiation source is estimated from the superimposed image shown in FIG. The first pseudo radiation source 10a shown in FIG. 5 corresponds to that shown in the image Pa shown in FIG. 4, and the second pseudo radiation source 10c shown in FIG. 5 is shown in the image Pc shown in FIG. Corresponds to things. The operation for estimating the actual position of the radiation source 10 will be described below with reference to FIGS. 4 and 5.

  As shown in FIG. 5, the radioactivity estimation unit 7 determines the position of the radiation source from the image Pa of the gamma camera 2a and the visible camera 1a (the three-dimensional) of the actual radiation source 10 or the first pseudo radiation source 10a. Convert to the position of. Further, the radioactivity estimation unit 7 converts the position of the radiation source from the image Pc of the gamma camera 2c and the visible camera 1c as being at the actual radiation source 10 position or the second pseudo radiation source 10c position.

  However, the radiation source on the surface of the structure obtained in this way is actually gamma rays that pass through the structure as shown in FIG. 2, so when the radiation source exists inside the structure, etc. In some cases, the conventional technology cannot identify the actual radiation source (radiation source) arrangement.

  Therefore, in the first embodiment, in order to narrow down to the actual radiation source arrangement (for example, the radiation source 10 shown in FIG. 5), the following processing is further performed in the radioactivity three-dimensional measurement apparatus 12.

  First, the surface radiation distribution difference site extraction unit 6 is used as the first processing means.

  As described above, the surface radiation distribution conversion unit 5 assigns the radiation intensity distribution to the surface of the three-dimensional surface shape obtained from the visible image of the visible camera 1a for each gamma camera image. That is, a superimposed image is generated.

  For example, as shown in FIG. 5, when the first pseudo radiation source 10a is present and the first pseudo radiation source 10a is an actual radiation source, the gamma camera images captured by the gamma camera 2b are superimposed. For the combined image Pb (shown in FIG. 4), the radiation source needs to be imaged at the same position. That is, it is possible to narrow down (estimate) the actual radiation source position by comparing the superimposed images of these gamma camera images and extracting the difference.

  As described above, regarding the radiation intensity distribution at the surface position obtained from each gamma camera image estimated by the surface radiation distribution conversion unit 5, the difference in the surface radiation distribution difference is obtained at the same position on the structure surface. Extracted by the part extraction unit 6. Further, the surface radiation distribution difference site extraction unit 6 determines whether or not there is a difference in radiation intensity on the surface of the structure depending on the gamma camera imaging position from the radiation intensity distribution of the extracted gamma camera image.

  When the surface radiation distribution difference site extraction unit 6 does not extract a site with a difference, the radioactivity estimation unit 7 emits radiation on the surface of the structure from the distance between the target structure and the gamma camera 2 and the angle of view of the gamma camera 2. Convert to capacity.

  In addition, when the surface of the structure is contaminated, the radioactivity estimation unit 7 extracts a conversion factor from the structure DB 8 to a certain radioactivity according to the measurement target, and multiplies it to obtain the radioactivity amount. It can be converted. Note that the data that is the basis of these conversion factors is included in the structure DB 8. For example, the contamination level / activation level of the structure DB 8 shown in FIG.

  On the other hand, when a part with a difference is extracted, the internal radiation calculation part 71 of the radioactivity estimation part 7 is used as a 2nd means. The internal radiation calculation unit 71 illustrated in FIG. 1 acquires the internal structure of the target structure from the structure DB 8, and selects a radiation source candidate position according to the linearity of the radiation within the structure.

  For example, FIG. 6 shows a case where an adjacent pipe 9a is arranged in addition to the pipe 9 shown in FIG. The pipe 9 and the pipe 9 a shown in FIG. 6 can acquire the pipe inner diameter and the like for the pipe 9 from the structure DB 8. Thereby, the internal radiation calculation unit 71 can select the third pseudo radiation source 10aa inside the pipe 9 and the fourth pseudo radiation source 10ab outside the pipe 9 as the radiation source candidate positions.

  Here, the third pseudo radiation source 10aa does not coincide with the image Pb of the gamma camera 2b. Also, regarding the second pseudo radiation source 10c, if it is assumed that gamma rays pass through the pipe 9, the photographing position of the gamma camera 2a is deviated from the center, resulting in a difference.

  On the other hand, for the fourth pseudo radiation source 10ab, it is difficult to determine the position by imaging at the three positions shown in FIG. 6, but by measuring the entire surface of the pipe 9 with the gamma camera 2 a plurality of times. Therefore, it is easy to determine whether or not there is a radiation source at these positions.

  As described above, the radioactivity estimation unit 7 can select the actual position of the radiation source 10 from these radiation source candidate positions.

  For example, as the radiation source candidate position, when the adjacent pipe 9a exists in FIG. 6, the second radiation source 10ac located on the surface of the pipe 9a is also estimated. In this case, since the installation position of the adjacent pipe 9a is also stored in the structure DB 8, the transmitted radiation calculation unit 72 shown in FIG. 1 calculates the amount of radiation that passes through the pipe 9 from the adjacent pipe 9a.

  As described above, in the radioactivity estimation unit 7, the internal radiation calculation unit 71 and the transmitted radiation calculation unit 72 estimate the influence of the radiation source candidate position in the structure and the radiation source in the adjacent structure. be able to. Thereby, the contribution of the radiation to the gamma camera image can be calculated.

  As a specific method, a gamma camera image photographed by the gamma camera 2 is calculated and evaluated based on the radiation source candidate position, and the peak position of the gamma ray intensity and the difference in intensity from the actual measurement result are digitized as parameters. The radioactivity position converging unit 73 shown in FIG. 1 determines the most probable radiation source position by comparing the ratios of differences (numerical data) at each radiation source candidate position based on such numerical data. Can do.

  Thereby, the radioactivity three-dimensional measurement apparatus 12 of the first embodiment can consider the radiation intensity measured by the gamma camera 2 in consideration of the distance to the radiation source and the shielding by the structure therebetween. It is possible to estimate the amount of intrinsic radioactivity within.

  7 and 8 are flowcharts showing a measurement process flow of the radioactivity three-dimensional measurement apparatus 12 according to the first embodiment. The processing contents of FIGS. 7 and 8 will be described below with reference to FIG.

  When measurement processing of the signal processing device 11 is started, first, an imaging position from a position around the target structure (pipe 9) is determined (step S1).

  After determining the photographing positions in the visible camera 1 and the gamma camera 2, a visible image is photographed by the visible camera 1 from a position around the pipe 9 (step S2). At the same time, a gamma camera image is taken from the position by the gamma camera 2 (step S3).

  In the shooting position storage unit 3 of the signal processing device 11, shooting information including the shooting direction and shooting location at this position is recorded in association with the visible image and the gamma camera image (step S4).

  The structure three-dimensionalization unit 4 superimposes the gamma camera image captured by the gamma camera 2 on the visible image captured by the visible camera 1 (step S5). For example, as shown in FIG. 3, images taken at positions a to c are superimposed to generate images Pa to Pc.

  The photographing position determining unit 31 determines whether or not photographing at a plurality of positions is finished (step S6). When shooting at a plurality of shooting positions has not been performed (No at step S6), the shooting position determination unit 31 returns the process at step S1. For example, as shown in FIG. 3, steps S2 to S5 are sequentially shown for each of these shooting positions in accordance with an instruction input to the shooting position determination unit 31 from the operator, such as position b and then position c. Processing is performed.

  In other cases (step S6 Yes), the process proceeds to the next step S7.

  The structure three-dimensionalization unit 4 configures the three-dimensional structure (surface shape) of the object from the 3D (three-dimensional) visible image information (step S7).

  The surface radiation distribution conversion unit 5 calculates the radiation intensity distribution on the structure surface based on the gamma camera image data mapped to the visible image (step S8).

  The surface radiation distribution difference site extraction unit 6 acquires a radiation intensity distribution estimated from different gamma camera images on the surface of the same structure (step S9).

  The surface radiation distribution difference site extraction unit 6 extracts a site having a difference (step S10).

  The surface radiation distribution difference site extraction unit 6 determines the degree of difference for the extracted site (step S11).

  When there is a difference portion, the internal radiation calculation unit 71 of the radioactivity estimation unit 7 determines the internal structure of the structure (pipe 9) using the structure DB 8 (step S12).

  The internal radiation calculation unit 71 selects a radiation source candidate position for the extracted part based on the internal structure of the structure, the peripheral device arrangement (adjacent structure), and the like (step S13).

  Next, the transmitted radiation calculation unit 72 calculates the transmission line intensity for each gamma camera position at all the estimated radiation source candidate positions (step S14).

  The transmitted radiation calculation unit 72 calculates the difference at the same position on the structure surface with respect to the radiation intensity distribution (surface radiation intensity distribution) at the surface position obtained from each gamma camera image (step S15).

  Next, the radioactivity position convergence unit 73 determines (narrows down) the radiation source candidate positions with the least difference (step S16). That is, the radiation source position is determined.

  The radioactivity position converging unit 73 determines whether or not the difference (digitized data) is equal to or greater than a predetermined value (step S17).

  When the difference is smaller than the predetermined value, the radioactivity estimation unit 7 estimates the radioactivity amount at the radiation source position from the gamma camera conversion value and the structure shielding rate (step S18).

  The radioactivity estimation unit 7 estimates the amount of intrinsic radioactivity based on the distance from the gamma camera 2 on the assumption that the structure is surface contamination or a volume radiation source (step S19).

  The radioactivity estimation unit 7 displays the estimated intrinsic radioactivity (step S20). After step S20, the radioactivity three-dimensional measurement apparatus 12 ends this process.

  On the other hand, if there is no difference in step S11, the radioactivity estimation unit 7 estimates the amount of intrinsic radioactivity based on the distance from the gamma camera 2 assuming surface contamination or a volume radiation source (step S111). ). The radioactivity estimation part 7 moves a process to step S20.

  If the difference is greater than or equal to a predetermined value in step S17, the process proceeds to step S171. The radioactivity estimation unit 7 checks whether or not the difference is greater than or equal to a predetermined value at all the radiation source candidate positions (step S171).

  The radioactivity estimation unit 7 determines whether or not the difference is greater than or equal to a predetermined value at all the radiation source candidate positions (step S172).

  When the difference is equal to or larger than the predetermined value (step S172 Yes), the radioactivity estimation unit 7 notifies the abnormality to the outside of the radioactivity three-dimensional measurement device (step S173). After the notification, the radioactivity three-dimensional measurement apparatus 12 ends this process.

  On the other hand, when the difference is smaller than the predetermined value (No at Step S172), the radioactivity estimation unit 7 notifies a request for measurement at another measurement position (Step S174). After the notification, the radioactivity three-dimensional measurement apparatus 12 ends this process.

  According to the radioactivity three-dimensional measurement apparatus of the first embodiment, an accurate radioactivity amount can be measured even for radioactivity inherent in structures such as pipes. It is also possible to measure the exact radioactivity distribution in the radiation handling work environment. Furthermore, since the number of cameras can be minimized to one gamma camera and one visible camera, the burden of measurement work such as movement and carrying can be reduced.

[Second Embodiment]
FIG. 9 is a block diagram showing a second embodiment of the radioactivity three-dimensional measurement apparatus according to the present invention. Detailed descriptions of components having the same reference numerals as those in the configuration diagram shown in FIG. 1 are omitted here.

  The configuration of the radioactivity three-dimensional measurement device 12d shown in FIG. 9 is different from the configuration of the radioactivity three-dimensional measurement device 12 shown in FIG. 1 in that the in-air radioactivity calculation unit 30 and the in-air radioactivity correction unit 74 are used. It is a point that has. Hereinafter, the configuration of the radioactivity three-dimensional measurement apparatus 12d will be described mainly with reference to the above differences with reference to FIG.

  As shown in FIG. 9, the radioactivity three-dimensional measuring device 12d includes a visible camera 1d, a gamma camera 2d, a signal processing device 11d, and a structure DB 8. Furthermore, the signal processing device 11d includes an imaging position determination unit 31, an imaging position storage unit 3, a structure three-dimensionalization unit 4, a surface radiation distribution conversion unit 5, a surface radiation distribution difference site extraction unit 6, and an air radioactivity calculation unit 30. And a radioactivity estimation unit 70.

  The air radioactivity calculation unit 30 converts the amount of radioactivity from the radiation source floating in the air converted by the surface radiation distribution conversion unit 5.

  The radioactivity estimation unit 70 is based on information input from the imaging position storage unit 3, the structure three-dimensionalization unit 4, the structure DB 8, the in-air radiation calculation unit 30, etc., for the extracted part. Estimate the radiation generation position. The radioactivity estimation unit 70 further includes an internal radiation calculation unit 71, a transmitted radiation calculation unit 72, a radioactivity position convergence unit 73, and an in-air radioactivity correction unit 74.

  The air radioactivity correction unit 74 uses the amount of radioactivity from the radiation source in the air calculated by the air radioactivity calculation unit 30 to use the internal radiation calculation unit 71, the transmitted radiation calculation unit 72, and the radioactivity position convergence unit. About the radioactivity distribution estimated by 73, the radioactivity distribution is corrected in distinction from the radioactivity amount from the radiation source in the structure.

  FIG. 10 is a diagram illustrating a measurement method for measuring the amount of radioactivity in the air using the radioactivity three-dimensional measurement apparatus according to the second embodiment.

  In an actual radiation handling work environment, for example, when the radiation source 10 is present inside a structure (pipe 9) as shown in FIG. 10, or the radioactivity adhering to the aerosol floating in the air as shown in FIG. The case where (radioactive aerosol 33) exists, the case where the radiation source from air, such as radioactive noble gases, such as Kr, exists is assumed.

  The radioactivity three-dimensional measuring apparatus 12d explains the ratio of the radiation from the radiation source 10 in the structure and the radiation from the radiation source in the air (the radioactive aerosol 33) from the measured radioactivity distribution below. It is possible to measure accurately by the processing.

  As shown in FIG. 10, a radioactive aerosol 33 (including a radioactive noble gas component) is suspended in the air in the measurement target area. The pipe 9 is disposed at the wall 32, and the radioactivity three-dimensional measuring device 12d is disposed at a distance L1 from the wall 32 at the time of measurement. Further, at the time of measurement at another position, the radioactivity three-dimensional measurement device 12e is disposed at a position at a distance L2 shorter than the distance L1.

  Under such measurement conditions, the contribution from the radiation source 10 in the pipe 9 measured by the radioactivity three-dimensional measuring devices 12d and 12e is one-half the distance, and the radiation intensity is weakened.

  On the other hand, regarding the contribution from the radioactive aerosol 33 measured by the radioactivity three-dimensional measuring devices 12d and 12e, the distance L1 and the distance L2 in the space between the wall 32 and the gamma cameras 2d and 2e It is determined by the floating amount of the radioactive aerosol 33 contained in.

  The nuclide of the radioactive aerosol 33 is mainly I-131 (364 keV) and Cs-137 (661 keV), and for example, the distance attenuated to 1 / e is about 14 m even with a gamma ray of about 100 keV. The indoor space in a nuclear power plant generally has a linear distance of 10 m or less, and in this space, the radiation dose contribution by the radioactive aerosol 33 hardly attenuates at distances L1 and L2 of 10 m or less. Therefore, in the example of FIG. 10, it is thought that it depends on the amount of radioactive aerosol existing between the distances L1 and L2. Strictly speaking, the attenuation may be corrected according to the gamma ray energy and integrated in space.

  Specifically, the prediction formula of the contribution by the radioactive aerosol 33 is expressed by an approximate expression of attenuation of gamma rays in the air as shown in the following (Formula 1).

I = I ₀ · exp (−μx) (Formula 1)
Here, the coefficients used in (Equation 1) are as follows.

I: Gamma ray intensity after transmission through x distance (Bq / cm)
I ₀ : Gamma ray intensity at the time of occurrence (Bq / cm)
μ: Damping coefficient (3.35 × 10 ^-5 / cm)
x: Transmission distance (cm)
For example, in a place where the gamma ray intensity I ₀ is uniformly distributed, the intensity when the distances _{0 to} L (cm) are integrated is I ₀ = L × I ₀ (Bq) when there is no attenuation, It is approximately proportional to the distance L. On the other hand, when there is attenuation, (Expression 1) is integrated from 0 to L (cm) (Expression 2).

  When (Equation 2) is applied, the attenuation of gamma rays (for example, 0.07 MeV to 2 MeV) in the air is small, and therefore is substantially proportional to the length L. As an example, FIG. 11 is a graph showing the relationship between the distance of the radiation intensity due to the radioactive aerosol based on (Equation 2). As shown in FIG. 11, it can be seen that the intensity of gamma rays is attenuated in proportion to the distance.

  On the other hand, the contribution of the radiation source 10 in the pipe 9 to the gamma cameras 2d and 2e is inversely proportional to the squares of the distances L1 and L2.

  Therefore, assuming that the aerosol concentration in the air and the radioactivity concentration in the pipe 9 are to be obtained, if the distances L1 and L2 are changed and measured, it is possible to obtain each from the attenuation ratio. In this case, the energy of gamma rays is known, and when the gamma ray energy is unknown, it is possible to increase the number of times of measurement and estimate the concentration of each by comparison with the calculation result. It should be noted that the distances L1 and L2 can be obtained by a stereo view by a plurality of times of shooting with the visible camera 1d or 1e. Alternatively, a known method such as a laser distance meter may be applied.

  That is, the in-air radioactivity calculation unit 30 calculates the above based on the radioactivity distribution data measured at two or more positions with different measurement distances with respect to the measurement object installed in the vicinity of the wall 32. It is possible to calculate the contribution due to the radioactive aerosol 33 in the air from the equation.

  Although the conventional measuring apparatus supports only the case where all the radioactivity is accumulated on the surface of the pipe 9 obtained by the stereo vision of the visible camera, the radioactivity three-dimensional measuring apparatus according to the second embodiment. Thus, it becomes possible to identify even the contribution (ratio of radiation) of the radioactive aerosol 33 floating in the middle space.

  Since the radioactive aerosol component in the air can be simultaneously measured in this way, it is not necessary to separately sample the aerosol in the air and measure the component, so that the radiation measurement can be performed efficiently. Further, from the measured radioactivity distribution, it is possible to accurately measure the ratio between the radiation from the radiation source in the contaminated structure and the radiation from the radiation source in the air.

  As described above, according to the radioactivity three-dimensional measurement apparatus of the second embodiment, the radioactivity scattered in the air and the radioactivity inherent in the pipe, which cannot be measured only by photographing with a visible camera and a gamma camera. Therefore, it is possible to measure an accurate radioactivity distribution.

  In addition, by using the radioactivity three-dimensional measuring apparatus of the second embodiment, it is possible to easily grasp the exposure management during radiation handling work and the influence on the radioactivity evaluation of the piping section.

[Third Embodiment]
FIG. 12 is a block diagram showing an embodiment of a radiation handling work management system according to the present invention.

  The radiation handling work management system 60 of the embodiment includes a radioactivity three-dimensional measurement device 12f, a structure DB 8, and an exposure dose evaluation device 61, as shown in FIG. Note that the radioactivity three-dimensional measurement device 12f has, for example, a structure DB8 provided outside from the radioactivity three-dimensional measurement device 12d described above.

  In FIG. 12, the structure 90 is installed in the radiation handling work environment, and the radioactivity (radioactive aerosol) 33a in the air exists. In the radiation handling work environment as shown in FIG. 10, it is necessary to evaluate the radiation dose, for example, the radiation source inside the structure 90 or the radioactive aerosol 33a in the air as the exposure dose.

  In the radiation handling work management system 60 in the configuration of FIG. 12, the exposure dose evaluation device 61 uses the radiation distribution measured by the radiation three-dimensional measurement device 12f, the structure information of the structure DB 8, and the like. Predict the distribution.

  When receiving the work conditions such as the work place (area) designated from the outside and the work time, the exposure dose evaluation apparatus 61 predicts the exposure dose according to the work conditions. For this purpose, as shown in FIG. 12, the exposure dose evaluation apparatus 61 includes a measurement data receiving unit 62, a DB update unit 63, a radioactivity distribution DB 64, a work condition input unit 65, an exposure dose analysis unit 66, and an evaluation result output unit. 67.

  The measurement data receiving unit 62 receives measurement data on the measurement target structure 90, the radiation source, and the radioactivity distribution from the radioactivity three-dimensional measurement device 12f. The measurement data receiving unit 62 sends these measurement data to the DB update unit 63.

  When the DB update unit 63 receives the measurement data on the measurement target structure 90, the radiation source, and the radioactivity distribution from the measurement data reception unit 62, the DB update unit 63 associates the measurement data with each measurement data and registers them in the radioactivity distribution DB 64. Or update.

  In the radioactivity distribution DB 64, measurement data on a plurality of structures including the structure 90, radiation sources, and radioactivity distributions are stored as radioactivity distribution data in association with work areas and the like. . These can be sequentially updated and registered.

  The work condition input unit 65 receives work condition information including a work place (area) and work time from an operator or the like. In addition, the work condition input unit 65 searches structure information around the work place, and narrows down a premise (analysis) condition for analyzing the exposure dose.

  The exposure dose analysis unit 66 refers to the analysis conditions sent from the work condition input unit 65 and acquires the radioactivity distribution data from the radioactivity distribution DB 64. The exposure dose analysis unit 66 calculates the exposure dose based on the acquired radioactivity distribution data, the work place, the work time, and the like. The exposure dose analysis unit 66 sends an exposure dose evaluation result including the calculated exposure dose to the evaluation result output unit 67.

  The evaluation result output unit 67 outputs the exposure dose evaluation result received from the exposure dose analysis unit 66 to a display device or the like.

  As described above, the exposure dose evaluation apparatus 61 predicts the exposure dose of the worker who handles radiation using the radioactivity distribution measured by the radioactivity three-dimensional measurement apparatus 12f and the structure information of the structure DB 8. Can do.

  In addition to the above, the exposure dose evaluation apparatus 61 compares the real-time value of the position where the measurement by the direct gamma camera 2 is performed with the value predicted from the radioactivity distribution DB 64, and the radiation. You may check the validity of the quantity. Further, commercially available portable dosimeter data may be taken in so that the dose value can be calibrated.

  FIG. 13 is a flowchart showing an overall processing flow of the radiation handling work management system of the embodiment.

  In the radiation handling work management system 60, when the exposure dose evaluation apparatus 61 is activated, the radiation handling work management process is started. The exposure dose evaluation apparatus 61 receives work condition information including a work place and a work time (step S31).

  Next, it is determined whether or not the measurement data receiving unit 62 of the exposure dose evaluation apparatus 61 has received measurement data from the radiation three-dimensional measurement apparatus 12f (step S32).

  When the measurement data is received (Yes in step S32), the measurement data receiving unit 62 sends the received measurement data to the DB update unit 63. The DB update unit 63 registers the updated measurement data (radioactivity distribution data) in the radioactivity distribution DB 64 or updates the radioactivity distribution DB 64 (step S33).

  The DB update unit 63 compares the radioactivity distribution data before and after the update and checks whether there is a difference (step S34). When there is a difference (Yes in step S34), the DB update unit 63 performs a caution display (or warning output) on the data whose radioactivity distribution has changed (step S35). Thereafter, the process proceeds to step S36. On the other hand, also when there is no difference (No in step S34), the process proceeds to step S36.

  The exposure dose analysis unit 66 calculates the exposure dose based on the work condition information and the radiation distribution data stored in the radiation distribution DB 64 (step S36).

  When the evaluation result output unit 67 receives the evaluation result of the exposure dose from the exposure dose analysis unit 66, the evaluation result output unit 67 outputs the evaluation result to a display device or the like (step S37). After output, this process ends.

  Here, as main equipment configurations of the radiation dose evaluation apparatus 61 shown in FIG. 12, for example, a CPU (Central Processing Unit), a ROM (Read Only Memory), a RAM (Random Access Memory), an HDD (Hard Disk Drive), a keyboard, A configuration including a mouse, a monitor, and the like may be used. In this case, for example, the exposure dose evaluation apparatus 61 is provided with a program for executing the exposure dose evaluation processing as described above, and the exposure dose evaluation apparatus 61 shown in FIG. The processing in each processing unit is executed.

  Further, in the case of the configuration of the above example, a configuration in which an operator inputs work condition information or the like from a keyboard, a mouse, or the like may be used. The exposure dose evaluation apparatus 61 may be configured to input work condition information and the like from the outside via a LAN or the like.

  When removing equipment due to decommissioning of a nuclear reactor, etc., the radioactivity inherent in equipment such as piping is removed or the radioactivity is temporarily installed and increased due to temporary placement. There is a case. It is also assumed that the concentration of radioactive aerosol in the air increases due to cutting or the like. The monitoring of ambient doses associated with these removals requires detailed monitoring, including real-time monitoring, in advance, and an appropriate work plan that can reduce exposure.

  In the configuration of FIG. 12, the position of radioactivity can be specified in real time using the radioactivity three-dimensional measurement apparatus of the first to third embodiments. In addition, by using the structure DB 8 that cooperates with a CAD system or the like, it is possible to map the radioactivity distribution in the work area where each device or structure is arranged. If the equipment removal plan at the time of decommissioning is determined, it will be possible to predict changes in the existing radioactivity distribution in accordance with the removal plan.

  According to the radiation handling work management system and the radiation handling work management method of the present embodiment, since the radioactivity three-dimensional measuring apparatus capable of providing an accurate radioactivity distribution is used, the movement of radioactivity accompanying the removal of the equipment is accurately grasped. It becomes possible to do. Based on the result, the dose in the work area can be accurately predicted. As a result, radiation handling work management capable of reducing the exposure amount can be realized by more accurate exposure dose management.

[Other Embodiments]
As mentioned above, although some embodiment of this invention was described, these embodiment is shown as an example and is not intending limiting the range of invention. For example, the features of the embodiments may be combined. Furthermore, these embodiments can be implemented in various other forms, and various omissions, replacements, and changes can be made without departing from the scope of the invention. These embodiments and modifications thereof are included in the invention described in the claims and equivalents thereof as well as included in the scope and gist of the invention.

  DESCRIPTION OF SYMBOLS 1, 1a, 1b, 1c, 1d, 1e ... Visible camera, 2, 2a, 2b, 2c, 2d, 2e ... Gamma camera, 3 ... Imaging position memory | storage part, 4 ... Structure three-dimensionalization part, 5 ... Surface radiation distribution Conversion unit, 6 ... surface radiation distribution difference site extraction unit, 7, 70 ... radioactivity estimation unit, 8 ... structure DB (database), 9, 9a ... piping, 10 ... radiation source, 10a ... first pseudo radiation source, 10c 2nd simulated radiation source, 10aa ... 3rd simulated radiation source, 10ab ... 4th simulated radiation source, 10ac ... 2nd radiation source, 11, 11a, 11b, 11c, 11d, 11e ... Signal processing device, 12, 12a, 12b, 12c, 12d, 12e, 12f ... Radioactivity three-dimensional measuring device, 30 ... Radioactivity calculation unit in air, 31 ... Imaging position determination unit, 32 ... Wall, 33, 33a ... Radioactive aerosol, 60 ... Radiation handling work management Cis 61 ... Exposure dose evaluation device, 62 ... Measurement data receiving unit, 63 ... DB update unit, 64 ... Radioactivity distribution DB, 65 ... Working condition input unit, 66 ... Exposure dose analysis unit, 67 ... Evaluation result output unit, 71 ... Internal radiation calculation unit, 72 ... Transmission radiation calculation unit, 73 ... Radioactivity position convergence unit, 74 ... In-air radioactivity correction unit, 90 ... Structure

Claims (6)

For each of a plurality of structures to be measured, a structure database storing three-dimensional data including the installation position and shape, and structure information including materials,
A visible camera that captures a two-dimensional visible image of the structure to be measured;
A radiation camera that is arranged so as to be included in a range of an angle of view of the visible camera, and that measures a radiation intensity distribution incident from the same direction as the imaging direction of the visible camera and captures a radiation image;
An imaging position storage unit that assigns an identifier to each of the captured visible image and the radiographic image and stores imaging information including an imaging position and an imaging direction for each identifier;
A structure three-dimensionalization unit for calculating the shape and position of the structure from the plurality of visible images taken by the visible camera;
A surface radiation distribution conversion unit that converts the radiographic image simultaneously captured in the plurality of visible images into a radiation intensity at a surface position in the shape of the structure calculated by the structure three-dimensionalization unit; ,
By comparing the radiation intensity of the surface in the shape of the structure converted by the surface radiation distribution conversion unit with the radiation distribution measured by the radiation camera, at the position of the same surface compared for the structure A surface radiation distribution difference site extraction unit for extracting sites with different radiation intensities;
A radiation generation position is estimated from the imaging information stored in the imaging position storage unit and structure information stored in the structure database for the site extracted by the surface radiation distribution difference site extraction unit. A radioactivity estimation unit for converting into radioactivity,
A radioactivity three-dimensional measuring apparatus comprising: The radioactivity estimation unit is
From the imaging information about the extracted part from the imaging position storage unit, the shape and position of the structure calculated by the structure three-dimensionalization unit, and the structure information of the structure database, the structure An internal radiation calculation unit for calculating a dose in the structure when radioactivity is contained inside,
Radioactivity position that estimates the radiation generation position and repeats the calculation until the dose calculated from the internal radiation calculation unit and the dose obtained from the radiographic imaging result converge with a difference within a predetermined range. A convergence section;
The radioactivity three-dimensional measurement apparatus according to claim 1, wherein The radioactivity estimation unit is
About the extracted part, the imaging position information from the imaging position storage unit and the position and shape of the structure calculated by the structure three-dimensionalization unit are transmitted through the structure and transmitted through the structure. A transmitted radiation calculator for calculating the dose on the surface on the transmitted side;
Radioactivity position convergence which repeats the calculation by estimating the radiation generation position until the dose calculated from the transmitted radiation calculation unit and the dose obtained from the radiographic image capture result converge with a difference within a predetermined range. And
The radioactivity three-dimensional measurement apparatus according to claim 1, further comprising: The radioactivity estimation unit is
When converting to the amount of radioactivity at the radiation generation position, the radioactivity component from the air around the structure is calculated based on the imaging results at different distances to the structure, and the calculated air from the air The radioactivity three-dimensional measurement apparatus according to any one of claims 1 to 3, further comprising an air radioactivity calculation correction unit that corrects radioactivity components and converts the radioactivity components into the radioactivity amount. A radiation handling work management system that has a structure database, a radioactivity three-dimensional measurement device, and a radiation handling work management device, and that predicts an exposure dose in a work area including a plurality of structures,
The structure database stores, for each of the plurality of structures to be measured, three-dimensional data including an installation position and a shape, and structure information including a material,
The radioactivity three-dimensional measuring device is:
A visible camera that captures a two-dimensional visible image of the structure to be measured;
A radiation camera that is arranged so as to be included in a range of an angle of view of the visible camera, and that measures a radiation intensity distribution incident from the same direction as the imaging direction of the visible camera and captures a radiation image;
An imaging position storage unit that assigns an identifier to each of the captured visible image and the radiographic image and stores imaging information including an imaging position and an imaging direction for each identifier;
A structure three-dimensionalization unit for calculating the shape and position of the structure from the plurality of visible images taken by the visible camera;
A surface radiation distribution conversion unit that converts the radiographic image simultaneously captured in the plurality of visible images into a radiation intensity at a surface position in the shape of the structure calculated by the structure three-dimensionalization unit; ,
Radiation at the same surface position compared for the structure by comparing the radiation intensity of the surface in the shape of the structure converted by the surface radiation distribution conversion unit with the radiation distribution measured by the radiation camera. A surface radiation distribution difference site extraction unit for extracting sites of different intensities;
A radiation generation position is estimated from the imaging information stored in the imaging position storage unit and structure information stored in the structure database for the site extracted by the surface radiation distribution difference site extraction unit. A radioactivity estimation unit for converting into radioactivity,
The radiation handling work management device is:
A work condition input unit for entering work information including work position and work time in an area for work management;
A radioactivity distribution database storing radioactivity distribution data of the plurality of structures measured by the radioactivity three-dimensional measurement device;
The radioactivity distribution data is extracted from a plurality of the structures based on the work information input from the work condition input unit, and the exposure dose in the work area is determined based on the extracted radioactivity distribution data. An exposure dose analysis unit to calculate,
A radiation handling work management system comprising: For each of a plurality of structures to be measured, a structure database that stores three-dimensional data including installation positions and shapes, structure information including materials, a three-dimensional radioactivity measuring apparatus, and a radiation handling work management apparatus A radiation handling work management method in a radiation handling work management system for predicting an exposure dose in a work area including a plurality of structures,
A visible image capturing processing step in which the visible camera of the radioactivity three-dimensional measuring device captures a two-dimensional visible image of the structure to be measured;
The radiation camera of the radioactivity three-dimensional measurement device arranged to be included in the range of the angle of view of the visible camera measures a radiation intensity distribution incident from the same direction as the imaging direction of the visible camera to obtain a radiation image. A radiographic imaging process step for imaging;
The radioactivity three-dimensional measuring apparatus assigns an identifier to each of the captured visible image and radiographic image, and stores imaging information including an imaging position and an imaging direction in the imaging position storage unit for each identifier. A position memory processing step;
A three-dimensional structure processing step in which the radioactivity three-dimensional measuring device calculates the shape and position of the structure from the plurality of visible images taken by the visible camera;
The radioactivity three-dimensional measurement apparatus is configured to calculate the radiographic image simultaneously captured by the radiographic image capturing process step among the plurality of visible images and the structure calculated by the structural three-dimensionalization processing step. A surface radiation distribution conversion processing step for converting the radiation intensity at the surface position in the shape;
The radioactivity three-dimensional measuring device compares the radiation intensity of the surface in the shape of the structure converted by the surface radiation distribution conversion processing step with the radiation distribution measured by the radiation camera, and the structure Surface radiation distribution difference site extraction processing step for extracting a site having different radiation intensity at the same surface position of the object compared,
The imaging information stored in the imaging position storage unit and the structure information stored in the structure database for the site extracted by the surface radiation distribution difference site extraction processing step by the radioactivity three-dimensional measurement apparatus And a radioactivity estimation processing step for estimating a radiation generation position and converting it into a radioactivity amount,
The radiation handling work management device is a work condition input processing step for receiving work information including work position and work time in an area for work management;
Radioactivity distribution data storage processing step in which the radiation handling work management device stores the radioactivity distribution data of the plurality of structures measured by the radioactivity three-dimensional measurement device in a radioactivity distribution database;
The radiation handling work management device extracts the radioactivity distribution data from the radioactivity distribution database based on the work information input from the plurality of structures by the work condition input processing step, and the extracted An exposure dose analysis processing step for calculating an exposure dose in the work area based on radioactivity distribution data;
Radiation handling work management method characterized by including.

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