Radioactive metal waste gamma nuclide rapid measuring device

Abstract

The invention discloses a radioactive metal waste gamma nuclide rapid measurement device, and belongs to the technical field of radioactive measurement. According to the radioactive metal waste gamma nuclide rapid measurement device, a lead layer and a well type anticoincidence detector are adopted to wrap a main detector in the center, directional measurement is achieved in a complex radioactive waste measurement scene, a 3D depth camera is adopted, a radioactive activity numerical value of a measurement point and a distance value measured by the depth camera are subjected to three-dimensional fusion, and the radioactive metal waste gamma nuclide rapid measurement device is obtained. According to the invention, high-precision correction of measurement activity is realized, an anti-coincidence detector device with directional measurement is developed, the problem that an existing measurement device is affected by a surrounding complex radiation field is solved, and a depth measurement activity correction function of optical fusion is realized based on a 3D binocular depth camera. The influence of the distance effect and the irregular geometric contour of the to-be-measured object on the measurement precision of the existing device is solved.

Description

Technical Field

[0001] The invention relates to the technical field of radioactivity measurement, in particular to a device for rapid measurement of gamma nuclides of radioactive metal waste. Background Art

[0002] Radioactivity measurement is a technology that involves detecting and analyzing the intensity and energy of radiation emitted by radioactive nuclides. The gamma nuclide measurement technology is based on the photoelectric effect, Compton effect and electron pair effect produced by the interaction between gamma rays and detectors. These effects appear as total energy peaks, Compton continuous spectra and escape peaks in the gamma energy spectrum. The position of the total energy peak is proportional to the energy of the incident gamma rays, and the net peak area is proportional to the nuclide content, thereby realizing the identification and quantitative analysis of nuclides.

[0003] For complex radioactive waste measurement scenarios, existing measurement devices are unable to perform directional measurements and are easily interfered by surrounding radiation sources. When measuring the activity of radioactive waste, the distance effect has a significant impact on the measurement results. Existing measurement devices do not have the ability to locate and correct measurements. Summary of the invention

[0004] In view of the problem that the above-mentioned prior art cannot perform directional measurement and is easily disturbed by surrounding radiation sources, the present invention is proposed.

[0005] Therefore, the technical problem to be solved by the present invention is the problem that the directional measurement is unable to be easily disturbed by the surrounding radiation sources.

[0006] To achieve the above object, the present invention provides the following technical solution: a device for rapid measurement of γ nuclides in radioactive metal waste, comprising:

[0007] An acquisition module, the acquisition module comprising an embedded industrial computer, an energy spectrometer, an outer protective layer and an optical depth camera, wherein one end of the embedded industrial computer is provided with an energy spectrometer, one end of the energy spectrometer is provided with an outer protective layer, and the optical depth camera is provided on the outer protective layer;

[0008] A protective shell is provided with a collection module inside the protective shell, and a guide groove is opened inside the protective shell.

[0009] As a further solution of the present invention: the embedded industrial computer, the spectrometer, the outer protective layer and the optical depth camera are electrically connected to each other through wires.

[0010] As a further solution of the present invention: the outer protective layer includes an anti-coincidence detector, a main detector and a silicon photomultiplier tube, the anti-coincidence detector is arranged in the outer protective layer, the main detector is arranged in the anti-coincidence detector, and a silicon photomultiplier tube is arranged at one end of the anti-coincidence detector.

[0011] As a further solution of the present invention: the anti-coincidence detector is arranged in a "concave" shaped structure.

[0012] As a further solution of the present invention: an anti-coincidence detection arrangement array is arranged in the anti-coincidence detector, and a main detection arrangement array is arranged in the main detector.

[0013] As a further solution of the present invention: the anti-coincidence detection arrangement array and the main detection arrangement array are electrically connected, and an electronic system is connected in series on one side of the anti-coincidence detection arrangement array and the main detection arrangement array.

[0014] As a further solution of the present invention: a high voltage power supply is also connected in series on one side of the anti-coincidence detection arrangement array and the main detection arrangement array.

[0015] As a further solution of the present invention: a connection wire holder is provided on the protective shell, and the connection wire holder is electrically connected to the acquisition module.

[0016] As a further solution of the present invention: a connecting protective shell is arranged on the protective outer shell, and at least one group of symmetrical protective lenses is arranged on the connecting protective shell.

[0017] As a further solution of the present invention: the position of the protective lens corresponds to the position of the optical depth camera.

[0018] Compared with the prior art, the beneficial effects of the present invention are as follows: the device for rapid measurement of gamma nuclides of radioactive metal waste uses a lead layer and a well-type anti-coincidence detector to wrap the main detector in the center, realizes directional measurement in complex radioactive waste measurement scenarios, and uses a 3D depth camera to perform three-dimensional fusion of the radioactivity value of the measurement point and the distance value measured by the depth camera to achieve high-precision correction of the measured activity. An anti-coincidence detector device with directional measurement is developed, which solves the problem that the existing measuring device will be affected by the surrounding complex radiation field. The depth measurement activity correction function of optical fusion is realized based on the 3D binocular depth camera, which solves the influence of distance effect and irregular geometric contour of the object to be measured on the measurement accuracy of the existing device. BRIEF DESCRIPTION OF THE DRAWINGS

[0019] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the following briefly introduces the drawings required for describing the embodiments. Obviously, the drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without creative work. Among them:

[0020] Figure 1 This is a schematic diagram of the overall structure of a device for rapid measurement of γ nuclides in radioactive metal waste according to an embodiment of the present invention.

[0021] Figure 2 This is a schematic diagram of the connection structure of a collection module of a rapid measurement device for gamma nuclides of radioactive metal waste according to an embodiment of the present invention.

[0022] Figure 3 This is a schematic diagram of the array arrangement structure of a collection module of a radioactive metal waste gamma nuclide rapid measurement device according to an embodiment of the present invention.

[0023] Figure 4 A schematic diagram of identification parameters of a rapid measurement device for gamma nuclides in radioactive metal waste according to an embodiment of the present invention,

[0024] Figure 5 A schematic diagram of coordinate relations of a rapid measurement device for gamma nuclides in radioactive metal waste according to an embodiment of the present invention,

[0025] Figure 6 A schematic diagram of a rapid measurement device for gamma nuclides in radioactive metal waste and pipeline modeling according to an embodiment of the present invention,

[0026] Figure 7 A schematic diagram of the radiation emitted from the outer surface of a pipe of a device for rapid measurement of γ nuclides in radioactive metal waste according to an embodiment of the present invention.

[0027] Figure 8 A schematic diagram of the ray emission from the inner surface of a pipe of a device for rapid measurement of gamma nuclides in radioactive metal waste according to an embodiment of the present invention. DETAILED DESCRIPTION

[0028] In order to make the above-mentioned objects, features and advantages of the present invention more obvious and easy to understand, the specific embodiments of the present invention are described in detail below in conjunction with the accompanying drawings.

[0029] In the following description, many specific details are set forth to facilitate a full understanding of the present invention, but the present invention may also be implemented in other ways different from those described herein, and those skilled in the art may make similar generalizations without violating the connotation of the present invention. Therefore, the present invention is not limited to the specific embodiments disclosed below.

[0030] Secondly, the present invention is described in detail with reference to the schematic diagram. When describing the embodiments of the present invention in detail, for the sake of convenience, the cross-sectional diagrams showing the device structure will not be partially enlarged according to the general scale, and the schematic diagrams are only examples, which should not limit the scope of protection of the present invention. In addition, in actual production, the three-dimensional dimensions of length, width and depth should be included.

[0031] Furthermore, the term "one embodiment" or "embodiment" as used herein refers to a specific feature, structure, or characteristic that may be included in at least one implementation of the present invention. The term "in one embodiment" that appears in different places in this specification does not necessarily refer to the same embodiment, nor is it a separate or selective embodiment that is mutually exclusive with other embodiments.

[0032] Example 1

[0033] like Figures 1 to 3 As shown, the present invention provides a technical solution: a device for rapid measurement of γ nuclides of radioactive metal waste, comprising:

[0034] The acquisition module 100 includes an embedded industrial computer 101, an energy spectrometer 102, an outer protective layer 103 and an optical depth camera 104. The energy spectrometer 102 is disposed at one end of the embedded industrial computer 101, the outer protective layer 103 is disposed at one end of the energy spectrometer 102, and the optical depth camera 104 is disposed on the outer protective layer 103;

[0035] A protective shell 200, wherein the collection module 100 is disposed in the protective shell 200, and a guide groove 201 is provided in the protective shell 200;

[0036] In this embodiment, during the measurement process, the detector will be affected by environmental radiation from other directions. In order to reduce the interference of the environmental background on the measurement, a collection module 100 structure with a directional measurement function is designed. The overall structure of the detector consists of three parts: the outermost outer protective layer 103, the middle well-shaped anti-coincidence detector 103a and the central main detector 103b. The anti-coincidence detector 103a uses an organic scintillator, which has the characteristics of short luminescence decay time, high light output efficiency, strong plasticity, etc. It is very suitable for the anti-coincidence detector 103a that is made into a specific shape according to design requirements, has good mechanical strength and wear resistance, performs well in complex environments and long-term use, and has a very low cost;

[0037] The main detector 103b uses an inorganic scintillator, which has the characteristics of excellent energy resolution, short luminescence decay time, high photon yield, excellent photon detection efficiency, good chemical and thermal stability, no radiation background and not easy to deliquesce. Its comprehensive performance is very suitable for environmental radioactivity detection;

[0038] The outer protective layer 103 is made of a lead layer, and the well-type anti-coincidence detector 103a wraps the main detector 103b in the center. Only the direction of the well-type opening of the anti-coincidence detector 103a directly above the main detector 103b can directly detect the external gamma rays. Since the lead sheet and the anti-coincidence detector have a certain blocking ability, the environmental radiation from other directions will be blocked by the outer protective layer 103 and the anti-coincidence detector 103a and cannot directly interact with the main detector. At the same time, the main detector 103b and the anti-coincidence detector 103a are time-coincident, which can also identify whether the particle comes from the direction of the well-type opening or other directions. That is, if the time when the particle arrives at the main detector 103b is earlier than the time when it arrives at the anti-coincidence detector 103a, it is considered that the particle comes from the direction of the well-type opening, otherwise it comes from other directions. Therefore, the anti-coincidence structure design enables the detector to have a better directional measurement function;

[0039] For scintillation crystals, photons can be converted into electrons for signal readout through photomultiplier tubes PMT or silicon photomultiplier tubes SiPM. Since PMT is usually too large, it is not conducive to integration in portable devices. At the same time, the large size makes it impossible for the anti-coincidence detector to form an effect of surface bonding with the main detector, affecting the anti-coincidence measurement effect. Therefore, this design uses a small-volume solid-state photoelectric conversion device SiPM array as the signal readout device.

[0040] Example 2

[0041] Combined with Figures 1 to 8 , it is concluded that: the embedded industrial computer 101, the spectrometer 102, the outer protective layer 103 and the optical depth camera 104 are electrically connected to each other through wires, the outer protective layer 103 includes an anti-coincidence detector 103a, a main detector 103b and a silicon photomultiplier tube 103c, the outer protective layer 103 is provided with an anti-coincidence detector 103a, the anti-coincidence detector 103a is provided with a main detector 103b, and a silicon photomultiplier tube 103c is provided at one end of the anti-coincidence detector 103a;

[0042] Preferably, the anti-coincidence detector 103a is arranged in a "concave" shape, an anti-coincidence detection arrangement array 105 is arranged in the anti-coincidence detector 103a, and a main detection arrangement array 106 is arranged in the main detector 103b;

[0043] In this embodiment: since the distance between the detector and the radioactive waste to be measured and the irregular geometric contour of the radioactive waste will affect the accuracy of the detector activity measurement, in order to achieve accurate measurement of the activity, it is necessary to use a binocular camera to scan the three-dimensional shape and size of the object, construct the workpiece contour, and then perform three-dimensional correction of the activity according to the contour and distance. Based on the stereo vision and structured light projection technology of the binocular camera, the three-dimensional image and depth information of the real-world object can be accurately obtained. The measurement system equipped with the depth camera performs three-dimensional fusion of the radioactive activity value of the measurement point and the distance value measured by the depth camera to achieve high-precision correction of the measured activity;

[0044] Through the transformation relationship between various coordinate systems, the position coordinates of the instrument in three-dimensional space can be accurately located during the radiation data acquisition process. Usually, this position is the coordinate of the camera in the world coordinate system, which needs to be transformed to the coordinate position of the radiation detector in the world coordinate system to ensure the accuracy of radiation positioning. The positions of various modules of the instrument have been fixed during the design process and will not change during actual use. Therefore, the movement trajectory of the radiation detector in the world coordinate system during the measurement process can be obtained through the fixed transformation relationship, such as Figure 5 As shown, the schematic diagram shows the position coordinate relationship between the instrument's camera and the radiation detector. Through this position relationship, in the actual measurement process, the radiation information measured by the detector can be superimposed on the corrected position coordinates, and the relevant coordinates and radiation information data can be output, providing a data basis for the spatial fusion of radiation information.

[0045] Example 3

[0046] Combined with Figures 1 to 8 , it is concluded that: the anti-coincidence detection arrangement array 105 and the main detection arrangement array 106 are electrically connected, an electronic system 107 is connected in series to one side of the anti-coincidence detection arrangement array 105 and the main detection arrangement array 106, and a high-voltage power supply 108 is also connected in series to one side of the anti-coincidence detection arrangement array 105 and the main detection arrangement array 106;

[0047] Preferably, a connection wire holder 202 is provided on the protective shell 200, and the connection wire holder 202 is electrically connected to the acquisition module 100. A connection protective shell 203 is provided on the protective shell 200, and at least one set of symmetrical protective lenses 204 is provided on the connection protective shell 203, and the position of the protective lenses 204 corresponds to the position of the optical depth camera 104.

[0048] In this embodiment: the number of points is selected for measurement according to the size of the item. After the measurement is completed, the measurement result is displayed in the form of dose rate or specific activity to indicate the category to which the item belongs. The three-dimensional shape and size of the object are scanned by the optical depth camera 104 to construct the contour of the workpiece. The acquisition module 100 realizes directional measurement of radioactive activity by designing an anti-coincidence detector 103a and an outer protective layer 103 to wrap the main detector 103b. The scanning data and the activity value measured by the anti-coincidence detector 103a are transmitted to the embedded industrial computer 101 for optical three-dimensional fusion to realize the high-precision measurement function of radioactive activity.

[0049] The working principle of the present invention is as follows: during the measurement process, a handheld scanning device is first used to aim it at the item to be measured in the room, and a scan is performed. The device displays different degrees of contamination and radioactivity levels through colors. As an auxiliary measurement, the metal waste to be measured is placed at the work site, and then the probe of the rapid measuring device is aimed at the item to be measured to start measurement. After the current point measurement is completed, the next point is measured, and the number of points is selected according to the size of the item for measurement. After the measurement is completed, the measurement result is displayed in the form of dose rate or specific activity to indicate the category to which the item belongs. The three-dimensional shape and size of the object are scanned by the optical depth camera 104 to construct the contour of the workpiece. The acquisition module 100 realizes directional measurement of radioactive activity by designing an anti-coincidence detector 103a and an outer protective layer 103 to wrap the main detector 103b. The scanning data and the activity value measured by the anti-coincidence detector 103a are transmitted to the embedded industrial computer 101 for optical three-dimensional fusion to realize the high-precision measurement function of radioactive activity.

[0050] Importantly, it should be noted that the construction and arrangement of the present application shown in a number of different exemplary embodiments are only exemplary. Although only a few embodiments are described in detail in this disclosure, it should be readily understood by those who refer to this disclosure that many modifications are possible, for example, the size, scale, structure, shape and proportion of various elements, and parameter values ​​such as temperature, pressure, etc., mounting arrangements, use of materials, color, directional changes, etc., without substantially departing from the novel teachings and advantages of the subject matter described in the application. For example, the element shown as integrally formed can be composed of multiple parts or elements, the position of the element can be inverted or otherwise changed, and the nature or number or position of the discrete element can be changed or changed. Therefore, all such modifications are intended to be included in the scope of the present invention. The order or sequence of any process or method steps can be changed or reordered according to alternative embodiments. In the claims, any "device plus function" clause is intended to cover the structure of the execution function described herein, and is not only structurally equivalent but also equivalent structure. Without departing from the scope of the present invention, other substitutions, modifications, changes and omissions can be made in the design, operating conditions and arrangement of the exemplary embodiments. Therefore, the invention is not limited to a specific embodiment, but extends to numerous modifications still falling within the scope of the appended claims.

[0051] Furthermore, in order to provide a concise description of exemplary embodiments, all features of an actual embodiment may not be described, i.e., those features that are not relevant to the best mode presently contemplated for carrying out the invention or those features that are not relevant to implementing the invention.

[0052] It should be understood that in the development of any actual implementation, as in any engineering or design project, numerous implementation-specific decisions may be made. Such a development effort may be complex and time-consuming, but for those of ordinary skill having the benefit of this disclosure, the development effort will be a routine task of design, fabrication, and production without undue experimentation.

[0053] It should be noted that the above embodiments are only used to illustrate the technical solutions of the present invention rather than to limit it. Although the present invention has been described in detail with reference to the preferred embodiments, those skilled in the art should understand that the technical solutions of the present invention may be modified or replaced by equivalents without departing from the spirit and scope of the technical solutions of the present invention, which should all be included in the scope of the claims of the present invention.

Claims

1. A rapid measurement device for gamma nuclides in radioactive metal waste, characterized by: include, A collection module (100), the collection module (100) comprising an embedded industrial computer (101), an energy spectrometer (102), an outer protective layer (103) and an optical depth camera (104), wherein one end of the embedded industrial computer (101) is provided with the energy spectrometer (102), one end of the energy spectrometer (102) is provided with the outer protective layer (103), and the optical depth camera (104) is provided on the outer protective layer (103); and, A protective shell (200), wherein a collection module (100) is arranged inside the protective shell (200), and a guide groove (201) is provided inside the protective shell (200).

2. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 1, characterized in that: The embedded industrial computer (101), the spectrometer (102), the outer protective layer (103) and the optical depth camera (104) are electrically connected to each other via wires.

3. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 2, characterized in that: The outer protective layer (103) comprises an anti-coincidence detector (103a), a main detector (103b) and a silicon photomultiplier tube (103c); the anti-coincidence detector (103a) is arranged inside the outer protective layer (103); the main detector (103b) is arranged inside the anti-coincidence detector (103a); and the silicon photomultiplier tube (103c) is arranged at one end of the anti-coincidence detector (103a).

4. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 3, characterized in that: The anti-coincidence detector (103a) is arranged in a "concave"-shaped structure.

5. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 4, characterized in that: An anti-coincidence detection arrangement array (105) is arranged in the anti-coincidence detector (103a), and a main detection arrangement array (106) is arranged in the main detector (103b).

6. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 5, characterized in that: The anti-coincidence detection arrangement array (105) and the main detection arrangement array (106) are electrically connected, and an electronic system (107) is connected in series on one side of the anti-coincidence detection arrangement array (105) and the main detection arrangement array (106).

7. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 6, characterized in that: A high voltage power supply (108) is also connected in series on one side of the anti-coincidence detection arrangement array (105) and the main detection arrangement array (106).

8. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 1, characterized in that: The protective housing (200) is provided with a connection wire seat (202), and the connection wire seat (202) is electrically connected to the collection module (100).

9. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 8, characterized in that: The protective shell (200) is provided with a connecting protective shell (203), and the connecting protective shell (203) is provided with at least one group of symmetrical protective lenses (204).

10. The device for rapid measurement of gamma nuclides in radioactive metal waste according to claim 9, characterized in that: The position of the protective lens (204) corresponds to the position of the optical depth camera (104).

Images