Method and measuring system for measurements on surfaces of a nuclear facility

Abstract

Method (S100) for measurements on surfaces (11, 12) in a nuclear facility (10), comprising Creating (S110) a digital model (21) of a first surface (11) of the nuclear facility (10); Overlaying (S120) the digital model (21) of the first surface (11) with a first digital raster grid (31) comprising a plurality of raster elements (35, 36); Assigning (S130) a first raster element (35) of the plurality of raster elements (35, 36) of measurement information for measuring a part of the first surface (11) corresponding to the first raster element (35) with a detector for measuring radioactive radiation (40); and Displaying (S140) the first raster element (35) in the first raster grid (31) together with the associated measurement information on a digital display device (51), the method further comprising Recording (S210) the first surface (11) with an optical sensor unit (52); and superimposing display (S220) of the recorded first area (11) together with the first grid (31) and the first grid element (35) with the associated measurement information on the digital display device (51).

Description

TECHNICAL FIELD

[0001] The present disclosure relates to methods for measuring surfaces of a nuclear facility and to a measuring system for measuring surfaces of a nuclear facility. In particular, the present disclosure relates to such methods and measuring systems with which surfaces in buildings of nuclear facilities can be measured for clearance. BACKGROUND

[0002] During the dismantling or decommissioning of nuclear facilities, such as nuclear power plants, radioactive residues are generated. These residues must be safely recycled, properly disposed of, or disposed of as radioactive waste. Based on previous experience, approximately 3% of the residues must be disposed of as radioactive waste, and approximately 97% of the residues are non-radioactive or only radioactive to a negligible extent. These residues can be used conventionally as non-waste outside of nuclear technology or can be subjected to proper and safe recycling or disposal in a manner compatible with the public good, i.e., "released."

[0003] In particular, residual materials whose radioactive activity is demonstrably below a certain level can be released by official decision. After that, the residual material is no longer considered radioactive within the meaning of nuclear law. Release results in the release of radioactive materials and objects, buildings, parts of rooms, floor areas, facilities, or parts of facilities from nuclear and radiation protection supervision.

[0004] For the release of the residual materials, they undergo a legally stipulated, detailed, comprehensively documented, and multiply quality-assured release process. This ensures the radiological safety of the released residual materials. In Germany, release is governed by the Radiation Protection Ordinance. The regulations are based, among other things, on European directives (Directive 2013 / 59 / Euratom) and recommendations of the German Radiological Protection Commission (SSK) (SSK recommendations of February 12, 1998, Federal Gazette of October 15, 1998; SSK recommendations of December 6, 2006, Federal Gazette of June 22, 2007). The Radiation Protection Ordinance lists the release levels that must be met for all major radionuclides for release. Compliance with these levels is verified using the results of the decision measurement for release. In addition, the Radiation Protection Ordinance formulates numerous requirements that must be met for release.

[0005] Radiological safety is a prerequisite for clearance. The key criterion for this is the "10 microsievert criterion" (see IAEA Safety Series No. 89, ISBN 92-0-123888-6). Accordingly, a radioactive substance may only be cleared if, in the worst-case scenario, it could only cause an additional radiation exposure to members of the public, expressed as a so-called effective dose, in the range of 10 microsieverts per calendar year.

[0006] Dismantable components of a nuclear facility can be subjected to clearance measurements in a clearance measurement system. In particular, dismantable components of nuclear facilities can be moved from the controlled area to the fenced monitoring area of ​​the nuclear facility and subjected to clearance measurements there using a clearance measurement system.

[0007] This is not possible for buildings located within the controlled area of ​​nuclear facilities, and the clearance measurements of building surfaces must be performed on-site. For this purpose, the walls of the rooms to be cleared are divided into numerous sectors by hand using paint markings and labeled accordingly. This is particularly time-consuming in large or angled rooms. The marked sectors are then measured individually, and the measurement results are recorded manually. This requires precise measurement planning in advance, which specifies in detail how the detectors for measuring radioactive radiation must be positioned and aligned. However, this is time-consuming and carries the risk of incorrect or forgotten measurements.

[0008] The following additional challenges arise when conducting clearance measurements on building surfaces: The walls of the buildings are often made of thick concrete or have a thick concrete structure, which requires a high measurement penetration depth for the measurements. The rooms in the buildings can be up to 30m x 30m x 10m and it is often difficult to position the measuring devices correctly at every point in the room. The rooms in the buildings often contain a variety of measurement obstacles, such as concrete posts or metal frames, which make accurate measurements difficult. The rooms are also often dusty, which can make measurements more difficult. The rooms in the buildings usually have no (permanently installed) infrastructure, in particular no electricity and no communication network, such as a wireless radio network (WLAN) or a cellular network.Furthermore, measuring devices installed in the rooms often have to be dismantled and reassembled, which makes correct repositioning of the measuring devices complex.

[0009] Despite these challenging measurement conditions, it is important to ensure that all areas are correctly cleared, no area is missed, and all measurements are properly documented. Furthermore, to avoid unwanted radiation exposure, the time spent by measuring personnel in the rooms being measured should be kept as short as possible.

[0010] JP 2017-211347 A relates to a measuring device for measuring radioactivity surface contamination density. The measuring device comprises a drive section with a radioactivity detector, a shape measurement scanner, a transfer mechanism, and a control section. The transfer mechanism moves the radioactivity detector along a predetermined route to a measurement object. The control section includes a measurement route calculation processing device that generates a 3D model of the measurement object based on a measurement signal from the shape measurement scanner, calculates a radioactivity measurement position of the radioactivity detector according to a surface shape, and determines the route based on a calculation result. BRIEF SUMMARY

[0011] The present disclosure is based on the object of providing a method for measurements on surfaces of a nuclear facility and a measuring system for measurements on surfaces of a nuclear facility, which help the measuring personnel to carry out regulatory clearance measurements with the shortest possible time spent in the nuclear facility.

[0012] To solve this problem, according to a first aspect of the present disclosure, a method for measurements on surfaces of a nuclear facility according to claim 1 is proposed, which comprises the following method steps: generating a digital model of a first surface of the nuclear facility, overlaying the digital model of the first surface with a first digital raster grid comprising a plurality of raster elements, assigning a first raster element of the plurality of raster elements of measurement information for measuring a part of the first surface which corresponds to the first raster element, with a detector for measuring radioactive radiation, and displaying the first raster element in the first raster grid together with the assigned measurement information on a digital display device.

[0013] The digital model of the first surface of the nuclear facility can be generated using a generation device that comprises at least one 3D image acquisition unit or a 3D scanning system, and can additionally comprise a data processing device. The data processing device can also be provided in a portable unit. With the aid of the 3D image acquisition unit and the data processing device, a non-contact photogrammetric coordinate measurement of the first surface can be performed, in which the dimensions of the first surface are deduced from images that depict the first surface from different perspectives by transforming the image data into an object coordinate system in the data processing device. The basis for the coordinate calculations can be the determination of the orientation of the 3D image acquisition unit for the respective images.The coordinates of the first surface can be determined using referenced markers from which the 3D coordinate measurement can be performed. For this purpose, the image coordinate system, which refers to the recorded three-dimensional image, can be transformed into an object coordinate system. The transformation can take place based on recorded markers whose positions in the object coordinate system are known. Thus, the 3D image acquisition unit can be a plurality of cameras with a stereo basis. Instead of the 3D image acquisition unit, a 3D scanning system, for example, a 3D laser scanner, can also be provided, with the data processing device generating the digital model of the first surface from the measurement data of the 3D scanning system. The advantage of the 3D scanning system, in particular the 3D laser scanner, is that it enables more precise measurements.

[0014] After generating the digital model of the first surface of the nuclear facility, it is overlaid with a first digital grid comprising a plurality of grid elements. The generation of the digital model and the overlay can be performed by the data processing device.

[0015] Subsequently, measurement information is assigned to a first raster element of the plurality of raster elements. The assignment can also be performed by the data processing device. The measurement information comprises information data for measuring a portion of the first surface corresponding to the first raster element using a detector for measuring radioactive radiation. For example, the measurement information can include a position of the detector relative to the first surface, a distance of the detector from the first surface, an orientation of the detector relative to the first surface, and / or a measurement duration. The detector for measuring radioactive radiation can be a germanium detector, in particular a germanium detector with a collimator. The detector for measuring radioactive radiation can also be a detector for gamma (photon) radiation and for beta particles, for example.

[0016] The first raster element in the first raster grid is displayed on a digital display device along with the associated measurement information. The display device and the data processing device can be integrated into a portable unit. For example, the display device can be a touch-sensitive screen of a portable tablet computer, and the data processing device can be a central processing unit of the tablet computer.

[0017] This allows measurement personnel to be informed in a simple and error-free manner where measurements are required and how the detector must be positioned and aligned for a correct measurement with respect to the first surface. This method also reduces the time that measurement personnel must be present in the nuclear facility building, helping to protect them from radioactive radiation.

[0018] To further simplify the correct positioning and alignment of the detector with respect to the first measurement surface for the measuring personnel, the method further comprises the method steps of recording the first surface with an optical sensor unit and superimposing the recorded first surface together with the first grid and the first grid element with the associated measurement information on the digital display device. The optical sensor unit can be designed, for example, as a 3D laser scanner. 3D laser scanners are advantageously very precise. The optical sensor unit can also comprise a camera, for example.

[0019] The optical sensor unit can, for example, be the camera of the portable unit (e.g., the tablet computer) that records the first surface, with the display device of the portable unit (e.g., the tablet computer) displaying the recorded first surface together with the first grid and the first grid element with the associated measurement information in real time. It is also conceivable for the display to be carried out using a 3D display device, for example, a stereoscopic display that generates two slightly different images for the left and right eyes. For this purpose, the 3D display device can be in communication with the data processing device (e.g., via WLAN).

[0020] The present method is not limited to individual building areas. In particular, entire rooms or entire buildings can be measured or cleared three-dimensionally using the present method. The method can thus comprise the following further steps: generating a digital model of a room of the nuclear facility, which comprises the first area and a second area, and overlaying the digital model of the second area with a second digital grid, which comprises a plurality of grid elements. In particular, it is conceivable that the sizes of the individual grid elements differ. For example, a standard size of a grid tenant of 1m 2 variable in the other grid to 50cm 2This makes it possible to individually adapt the sizes of the grid elements to the specific characteristics of the areas to be measured. For example, a surface to be measured may contain small parts that need to be measured separately. This may require adjusting the grid elements of the grid so that the small part can be left out and measured individually.

[0021] In one embodiment of the method, the raster elements of the second digital raster grid can differ from the raster elements of the first digital raster grid. This is particularly advantageous if the first and second surfaces have different configurations. In such a case, both the raster elements of the first digital raster grid and the raster elements of the second digital raster grid can be optimally adapted to the associated surface.

[0022] The method can further comprise the steps of measuring, with the detector based on the measurement information, the first area for radioactive radiation and assigning a measured value of the measurement to at least one grid element which corresponds to a measured part of the first area. The assignment can in particular take place automatically. For example, it is conceivable for the detector to comprise a communication device (for example a WLAN module) which communicates with a communication device (for example also a WLAN module) in the portable unit. After the measurement has been carried out by the detector, the measured value is sent wirelessly via a WLAN connection to the portable unit, which automatically assigns the measured value to the corresponding grid element and stores the measured value or the assignment in the portable unit. After the measurement has been completed, the portable unit can store all of the stored measurement data together with the grid element orSend raster element data to a central unit for further processing. For this purpose, the portable unit can be configured to only begin sending data to the central unit after leaving the controlled area of ​​the nuclear facility.

[0023] The measured value measured by the detector can be a value of radioactive radiation and / or a number of measurements.

[0024] Furthermore, the measurement with the detector can include an orientation measurement and / or a subsequent decision measurement. All measurement prerequisites and measurement results, along with the respective grid element assignments, can be stored in the portable unit and displayed on the display device. This simple and secure presentation and storage of measurement information and data makes it possible to reduce the time spent by measurement personnel in the nuclear facility. A further reduction in the time spent by measurement personnel in the nuclear facility can be achieved by reducing the possibility of errors and the need for repeated measurements.

[0025] To process the clearance measurement, the method can further comprise the steps of comparing the measured value of radioactive radiation with a clearance value and assigning the comparison result to the grid element that corresponds to the measured part of the first area or the second area. The clearance value can refer to the "10 microsievert criterion" and / or to the Radiation Protection Ordinance (StrISchV). This provides a simple way for measuring personnel to be informed whether a measurement has met the requirements for clearance or whether further decontamination of the area and another measurement of the area is necessary. This gives measuring personnel immediate certainty as to whether, and if so, what, action needs to be taken with regard to the area, thereby further reducing the length of time the measuring personnel spend in the nuclear facility building.

[0026] For even more precise measurements or optimization of the detector's installation positions or orientations, the method may further comprise the steps of assigning historical operational data of the nuclear facility to the first grid element. The historical operational data may be past circumstances that could affect the measurement result. For example, historical operational data may include location information regarding a water ingress into a specific area of ​​an area to be measured or a room adjacent to the area to be measured, or a breach through a concrete wall of the area that was then resealed with filler material, allowing radioactive radiation from an adjacent room to impact the area to be measured.

[0027] The method may further comprise displaying the first grid element together with the associated operational history data on the digital display device. This display advantageously allows a natural person to verify the assignment performed.

[0028] According to one embodiment of the present disclosures, the first grid is a Cartesian grid, a spherical grid, or a cylindrical grid. Each grid element of the first grid can have a rectangular shape. Furthermore, the sizes of the grid elements of the first grid can be variable. Consequently, individual adaptation of the grid or grid elements to the conditions of the area or space to be measured is possible.

[0029] To solve the above-mentioned problem, according to a second aspect of the present disclosure, a measuring system for measurements on surfaces of a nuclear installation is proposed according to claim 12, which comprises the following: a generating device configured to generate a digital model of a first surface of the nuclear installation, a superimposing device configured to superimpose the digital model of the first surface with a first digital grid comprising a plurality of grid elements, an assigning device configured to assign measurement information to a first grid element of the plurality of grid elements for measuring a part of the first surface corresponding to the first grid element with a detector for measuring radioactive radiation, and a digital display device configured todisplay the first raster element in the first raster grid together with the associated measurement information on a digital display device.

[0030] For example, the measurement system can comprise a portable unit (e.g., a tablet computer) and a generating device connected to it for communication purposes. The generating device can, in particular, be the 3D image acquisition unit described above. The superimposition device and the assignment device can be a data processing device, for example, a central processing unit, integrated into the portable unit. The display device can be a screen of the portable unit.

[0031] Furthermore, the measuring system, in particular the portable unit of the measuring system, comprises an optical sensor unit configured to record the first surface, wherein the digital display device is configured to display the recorded first surface together with the first grid and the first grid element, with the associated measurement information superimposed. The optical sensor unit can be designed, for example, as a 3D laser scanner. 3D laser scanners are advantageously very precise. The optical sensor unit can also comprise a camera, for example. In particular, the camera can be the camera of a tablet computer. Consequently, the first surface together with the first grid, the first grid element, and the associated measurement information can be displayed to the measuring personnel in real time.If the display device is a 3D display device, the data can be visualized even more clearly in real time for the measuring personnel.

[0032] The measuring system may further comprise a detector for measuring radioactive radiation, which is configured to send a distance of the detector from the first surface, an orientation of the detector relative to the first surface, a measurement duration, a value of measured radioactive radiation, and / or a number of measurements to the allocation device. For this purpose, the detector and the portable unit may have respective communication devices (e.g., WLAN radio modules), via which a communication connection, in particular a bidirectional communication connection, is enabled between the detector and the portable unit.

[0033] According to one embodiment, the measuring system comprises a central unit configured to generate the measurement information and a storage unit configured to receive the measurement information from the central unit and to send it to the allocation device, wherein the central unit is arranged outside a control area of ​​the nuclear installation and the storage unit and the allocation device are configured to be moved from outside the control area of ​​the nuclear installation into the control area of ​​the nuclear installation and within the control area of ​​the nuclear installation.

[0034] The central unit can, in particular, be a central computer (e.g., a cloud computer) that receives all measurement data, calculates the optimal detector installation locations or orientations using simulations, and sends this data to the portable unit, which then visualizes it for measurement personnel to display the optimal detector setup data. Since the measurements are taken inside a building of the nuclear facility, whose walls are usually thick concrete, thus preventing communication from outside the building to inside the building, it can also be provided that data exchange between the portable unit and the central unit only takes place when the portable unit is outside the room.For this purpose, it can be provided that the portable unit determines whether stable data communication between the portable unit and the central unit is possible before attempting to send data.

[0035] Furthermore, the central unit can comprise a computing unit configured to calculate the measurement information based on the digital model of the first surface, measured local dose rates of the first surface, and measured local dose rates of other surfaces in the same room as the first surface and / or a room adjacent to the first surface. For this purpose, the computing unit can execute a plurality of simulations, which are used to calculate the optimal installation positions or orientations of the detector with respect to the surface.

[0036] Furthermore, the measuring system can comprise a comparison device configured to compare a measured value of the radioactive radiation with a release value, wherein the assignment device is configured to assign the comparison result to a grid element corresponding to a portion of the first area measured with the detector. The release value can refer, in particular, to the "10 microsievert criterion" or to the German Radiation Protection Ordinance (StrISchV). The comparison device can be provided, for example, in the portable unit or the central unit, so that the comparison can be performed on-site or outside the building.

[0037] The aspects and variants described above can be combined without this being explicitly described. Each of the described embodiment variants is thus optional to each embodiment variant or even to combinations thereof. Consequently, the present disclosure is not limited to the individual embodiments and variants in the described order or to a specific combination of the aspects and embodiment variants. BRIEF DESCRIPTION OF THE DRAWINGS

[0038] Further advantages, details and features of the methods, devices and systems described here will become apparent from the following description of embodiments and the figures. Fig. 1 shows a schematic representation of an embodiment of a measuring system for measurements on surfaces of a nuclear facility; Fig. 2 shows a flowchart of an embodiment of a first method for measurements on surfaces of a nuclear facility; Fig. 3 shows a flowchart of an embodiment of a second method for measurements on surfaces of a nuclear facility; and Fig. 4 shows a flowchart of an embodiment of a third method for measurements on surfaces of a nuclear facility. DETAILED DESCRIPTION

[0039] The Fig. 1 shows a schematic representation of an embodiment of a measuring system for measurements on surfaces of a nuclear facility. Fig. Figure 1 shows a building 10 of a nuclear facility located in the controlled area of ​​the nuclear facility. The building 10 comprises a plurality of rooms, of which room 15 is shown schematically. Two walls of room 15, i.e., a first surface 11 and a second surface 12, are labeled as an example. A plurality of further rooms with a plurality of further surfaces are adjacent to room 15 (in Fig. 1 not shown). In room 15 and the other rooms there are a number of built-in elements, such as concrete posts or metal frames (in Fig. 1 not shown). Furthermore, surfaces 11 and 12 of room 15 are thick concrete walls, which can only be processed with great mechanical effort.

[0040] The measuring system comprises a detector 40, a portable unit 50 and a generating device 60. As can be seen from the Fig. 1, the detector 40, the portable unit 50 and the generating device 60 are arranged in the building 10. In particular, the detector 40, the portable unit 50 and the generating device 60 are arranged in the room 15 (in Fig. 1 not shown for clarity).

[0041] The detector 40 is a germanium detector with a collimator, the portable unit 50 is a tablet computer, and the generating device 60 is a 3D laser scanner. The detector 40 and the generating device 60 may include respective communication devices for transmitting and receiving data, in particular for data communication with the tablet computer 50.

[0042] The tablet computer 50 comprises a digital display device 51, a camera 52, an overlay device 53, an association device 54, a communication device 55, a data processing device 56, and a storage device 57. The communication device 55 or the communication devices of the detector 40 and the generation device 60 can be, for example, WLAN radio modules.

[0043] More in the Fig. 1, elements for determining the 3D coordinates of surfaces 11 and 12, such as devices for executing a triangulation method for the generating device 60, can be provided. For example, a triangulation calculation can be performed using the input angles of transmitted and received signals. For this purpose, a multi-antenna system can be provided in the space 15, which has a relatively wide aperture angle and calculates the required angle information from the propagation time difference of received signals. For this purpose, a sensor can be provided on the detector 40, which is configured to determine the position or orientation of the detector 40. Furthermore, so-called "anchor receivers" can be provided in the space 15, which receive transmitted signals from the sensor, with automatic calibration taking place between the sensor and the anchor receivers. This makes it possible to detect the exact position of the detector 40, its inclination, and its detection angle.

[0044] In the Fig. 1 further shows a central unit 70 located outside the building 10. When the portable unit 50 is located outside the building 10, the central unit 70 can communicate with the portable unit 50. For this purpose, the central unit 70 includes a communication device 73, for example, a WLAN radio module. The central unit 70 further includes a computing unit 71, a comparison device 72, and an input device 74.

[0045] The computing unit 71 of the central unit 70 is configured to calculate measurement information for the detector 40 based on a digital model 21 of the first area 11, measured local dose rates and the activity of the first area 11, and measured local dose rates of other areas 12 in the same room 15 as the first area 11 and / or a room adjacent to the first area 11. The comparison device 72 is configured to compare a radioactive radiation value measured by the detector 40 with a release value. Using the input device 74, an operator can enter data into the central unit 70.

[0046] Furthermore, the Fig. 1 schematically shows a digital model of the room 15. In particular, the digital model is displayed on the display device 51 of the portable unit 50. Thus, the digital model comprises a first digital model 21 of the first surface 11 of the room 15 and a second digital model 22 of the second surface 12 of the room 15. A first digital raster grid 31 is superimposed on the first digital model 21, and a second digital raster grid 32 is superimposed on the second digital model 22. The first digital raster grid 31 comprises a first plurality of raster elements, of which raster elements 35 and 36 are shown as examples. The second digital raster grid 32 comprises a second plurality of raster elements, of which raster elements 38 and 39 are shown as examples. Furthermore, in the Fig. 1 shows a further grid 33, which corresponds to a floor of the room 15.

[0047] Referring to the Fig. 2, an embodiment of a first method S100 for measurements on surfaces of a nuclear facility is described below. In particular, the method S100 can be derived from the method described in Fig. 1 shown measuring system.

[0048] In a first step S110, a digital model 21 of the first surface 11 of the room 15 of the nuclear facility 10 is generated. This generation can be carried out with the aid of the 3D laser scanner 60 and a data processing device 56 provided in the portable unit 50.

[0049] In a second step S120, the digital model 21 of the first surface 11 is overlaid with a first digital grid 31, which comprises a plurality of grid elements 35, 36. The overlay can be performed by the overlay device 53 in the portable unit 50.

[0050] Subsequently, in a third step S130, a first raster element 35 of the plurality of raster elements 35, 36 is assigned measurement information for measuring a portion of the first surface 11 corresponding to the first raster element 35 with the detector 40. The measurement information can include a position of the detector 40 relative to the first surface 11, a distance of the detector 40 from the first surface 11, an orientation of the detector 40 relative to the first surface 11, and / or a measurement duration. The assignment can be performed by the assignment device 54 in the portable unit 50.

[0051] Finally, in a fourth step S140, the first raster element 35 in the first raster grid 31 is displayed together with the associated measurement information on the digital display device 51 of the portable unit 50.

[0052] Corresponding generation, overlay, assignment and display steps can also be carried out with respect to the second area 12 of the room 15 or a plurality of further areas of the room 15 and / or further rooms of the building 10.

[0053] In particular, the first grid 31 can be a Cartesian grid, a spherical grid, or a cylindrical grid. Furthermore, each grid element 35, 36 of the first grid 31 can have a square or rectangular shape. Furthermore, the sizes of the grid elements 35, 36 of the first grid 31 can be variable.

[0054] Using method S100, the portable unit 50 can indicate to the measuring personnel where and with what orientation the detector 40 must be positioned to measure a respective grid element. In particular, this method eliminates the need to draw colored markings with additional information on surfaces 11 and 12 of room 15, thus reducing the time the measuring personnel spend in room 15 or building 10.

[0055] Referring to the Fig. 3, an embodiment of a second method S200 for measurements on surfaces of a nuclear facility is described below. In particular, the method S200 can be derived from the method described in Fig. 1. Furthermore, method S200 can follow method S100.

[0056] In a first step S210, the first surface 11 is recorded with the camera 52 of the portable unit 50.

[0057] In a second step S220, the recorded first area 11 is displayed superimposed together with the first grid 31 and the first grid element 35 with the associated measurement information on the digital display device 51 of the portable unit 50.

[0058] With the S200 method, the necessary measurement information for the detector 40 can be displayed to the trade fair personnel in real time, so that the time for positioning and aligning the detector 40 can be reduced, which helps to reduce the time the measuring personnel spend in the building 10.

[0059] Referring to the Fig. 4, an embodiment of a third method S300 for measurements on surfaces of a nuclear facility is described below. In particular, the method S300 can be derived from the method described in Fig. 1. Furthermore, method S300 can follow method S100 and / or method S200.

[0060] In a first step S310, the first surface 11 is measured for radioactive radiation using the detector 40 based on measurement information. The measurement information includes information data for measuring a portion of the first surface 11 corresponding to the first raster element 35 with the detector 40. Thus, the measurement information can include a position of the detector 40 relative to the first surface 11, a distance of the detector 40 from the first surface 11, an orientation of the detector 40 relative to the first surface 11, and / or a measurement duration of the detector 40. Furthermore, the measurement can include an orientation measurement and a subsequent decision measurement.

[0061] In a second step S320, a measured value of the measurement is assigned to the grid element 35 corresponding to a measured part of the first surface 11. In particular, this assignment can be performed automatically by the detector 40 sending measured values ​​to the portable unit 50, which automatically assigns them to the corresponding grid elements. The data is then stored in the portable unit 50 in the storage device 57 and can subsequently be sent to the central unit 70 for proper documentation. The measured value comprises a radioactive radiation value and / or a number of measurements. The number of measurements is documented and can be used to ensure that no measurement has been forgotten. In particular, it can be provided that the portable unit 50 emits an alarm signal if the number of measurements has the value zero after the occurrence of a certain event.The specific event may, for example, be the expiration of a certain period of time.

[0062] With the S300 method, the measured values ​​can be easily assigned to corresponding grid elements, which simplifies documentation, avoids repeated measurements and inaccuracies, and ensures that no measurement is forgotten, ultimately reducing repeated measurements and / or an extended stay of the measuring personnel in building 10.

[0063] The methods S100, S200, and S300 described above may further comprise the steps of comparing the measured value of the radioactive radiation with a clearance value and assigning the comparison result to the grid element 35 corresponding to the measured part of the first surface 11. Thus, it is possible to document in a simple and reliable manner or to signal to the measuring personnel whether a measurement meets the specified clearance requirements or whether at least one further measurement is necessary, which requires further decontamination of the first surface 11 beforehand.

[0064] The methods S100, S200, and S300 described above may further comprise the steps of assigning historical operational data of the nuclear facility 10 to the first grid element 35 and displaying the first grid element 35 together with the assigned historical operational data on the digital display device 51. This provides the measurement personnel with an overall overview of the measurement situation with the detector 40, which contributes to more accurate measurements with the detector 40 and can thus reduce the number of measurements or the time the measurement personnel spend in the building 10.

[0065] In the examples presented, various features and functions of the present disclosure have been described separately and in specific combinations. However, it is understood that many of these features and functions can be freely combined with one another, unless explicitly excluded.

Claims

[1] Method (S100) for measurements on surfaces (11, 12) in a nuclear facility (10), comprising Creating (S110) a digital model (21) of a first surface (11) of the nuclear facility (10); Overlaying (S120) the digital model (21) of the first surface (11) with a first digital raster grid (31) comprising a plurality of raster elements (35, 36); Assigning (S130) a first raster element (35) of the plurality of raster elements (35, 36) of measurement information for measuring a part of the first surface (11) corresponding to the first raster element (35) with a detector for measuring radioactive radiation (40); and Displaying (S140) the first raster element (35) in the first raster grid (31) together with the associated measurement information on a digital display device (51), the method further comprising Recording (S210) the first surface (11) with an optical sensor unit (52); and superimposing display (S220) of the recorded first area (11) together with the first grid (31) and the first grid element (35) with the associated measurement information on the digital display device (51). [2] Method according to the preceding claim, wherein the detector for measuring radioactive radiation (40) comprises a germanium detector and / or a collimator and / or a detector for gamma (photon) radiation and / or a detector for beta particles. [3] Method according to one of the preceding claims, wherein the measurement information comprises a position of the detector (40) with respect to the first surface (11), a distance of the detector (40) from the first surface (11), an orientation of the detector (40) with respect to the first surface (11) and / or a measurement duration. [4] Method according to one of the preceding claims, further comprising Creating a digital model (21, 22) of a space (15) of the nuclear facility (10) comprising the first surface (11) and a second surface (12); and Overlaying the digital model (22) of the second surface (12) with a second digital raster grid (33) comprising a plurality of raster elements (38, 39). [5] Method according to claim 4, wherein the raster elements (38, 39) of the second digital raster grid (32) differ from the raster elements (35, 36) of the first digital raster grid (31). [6] Method according to one of the preceding claims, further comprising Measuring (S310), with the detector (40) based on the measurement information, the first surface (11) for radioactive radiation; and Assigning (S320) a measured value of the measurement to at least one raster element (35) which corresponds to a measured part of the first surface (11). [7] The method of claim 6, wherein the measuring comprises an orientation measurement and / or a subsequent decision measurement. [8] Method according to claim 6 or 7, wherein the measured value comprises a value of radioactive radiation and / or a number of measurements. [9] The method of claim 8, further comprising Comparing the measured value of radioactive radiation with a clearance value; and Assigning the comparison result to the grid element (35) which corresponds to the measured part of the first surface (11) or the second surface (12). [10] Method according to one of the preceding claims, further comprising assigning to the first grid element (35) operational history data of the nuclear facility (10). [11] Method according to one of the preceding claims, wherein the first grid (31) comprises a Cartesian grid, a spherical grid or a cylindrical grid, each grid element (35, 36) of the first grid (31) has a rectangular shape and / or the sizes of the grid elements (35, 36) of the first grid (31) are variable. [12] Measuring system for measurements on surfaces (11, 12) in a nuclear facility (10), comprising a generating device (60) configured to generate a digital model (21) of a first surface (11) of the nuclear facility (10); an overlay device (53) configured to overlay the digital model (21) of the first surface (11) with a first digital raster grid (31) comprising a plurality of raster elements (35, 36); an assignment device (54) configured to assign measurement information to a first raster element (35) of the plurality of raster elements (35, 36) for measuring a part of the first surface (11) corresponding to the first raster element (35) with a detector for measuring radioactive radiation (40); and a digital display device (51) configured to display the first grid element (35) in the first grid (31) together with the associated measurement information on a digital display device (51), the measuring system further comprising: an optical sensor unit (52) which is arranged to receive the first surface (11), wherein the digital display device (51) is configured to display the recorded first area (11) together with the first grid (31) and the first grid element (35) with the associated measurement information superimposed. [13] The measuring system according to claim 12, further comprising the detector (40) for measuring radioactive radiation, which is configured to send a distance of the detector (40) from the first surface (11), an orientation of the detector (40) with respect to the first surface (11), a measurement duration, a value of a measured radioactive radiation and / or a number of measurements to the allocation device (54). [14] The measuring system of claim 13, further comprising a central unit (70) configured to generate the measurement information; and a storage unit (55) which is arranged to receive the measurement information from the central unit (70) and to send it to the allocation device (54), wherein the central unit (70) is arranged outside a controlled area of ​​the nuclear installation (10), and the storage unit (55) and the allocation device (54) are designed to be moved from outside the control area of ​​the nuclear installation (10) into the control area of ​​the nuclear installation (10) and within the control area of ​​the nuclear installation (10).

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