Nuclear densitometer

Abstract

The utility model relates to a nucleon densimeter which comprises an anti-radiation device, and a radiation source is arranged on the working side of the anti-radiation device; the anti-radiation device is provided with a first frame body, and the first frame body is used for fixing the anti-radiation device on the surface of a to-be-detected pipeline or container; the detection device is used for collecting gamma rays released by the radiation source and transmitting the gamma rays to the data processing device; the detection device is provided with a second frame body, the second frame body is used for fixing the detection device on the surface of the to-be-detected pipeline or container, and the detection device and the anti-radiation device are located on the two sides of the pipeline or container respectively. According to the nucleon densimeter, the embedded radiation source is used, the direction of gamma rays released by the radiation source is controlled, and the thickness and the width of the anti-radiation device are increased, so that the anti-radiation effect is improved, and the problem of radiation leakage in the production process, the transportation process, the use process and the radiation source replacement process is comprehensively solved.

Description

Technical Field

[0001] The utility model relates to the technical field of fluid density detection, in particular to a nuclear density meter. Background Art

[0002] Many working conditions in the production process are in harsh working environments such as high temperature, high pressure, high dust, and high toxicity. Conventional instruments and meters are difficult to meet the requirements of such working conditions. Therefore, non-contact detection and control instruments using radioactive isotopes have come into being. The existing radioactive nuclear radiation instruments are divided into density meters, level meters, level switches, etc., which can solve the detection problems of material level, liquid level, and density under harsh working conditions. However, while the existing nuclear radiation detection instruments and meters bring convenience to our production, they also bring many unsafe factors, such as improper use and loose installation, which lead to safety hazards such as radiation spillage and even major accidents. Utility Model Content

[0003] The embodiment of the utility model provides a nuclear density meter to solve the problem of radiation spillover caused by incomplete radiation protection or loose installation in the prior art.

[0004] In order to achieve the above purpose, the embodiment of the utility model provides the following technical solutions:

[0005] A nuclear density meter comprises a radiation protection device, wherein a radiation source is arranged on the working side of the radiation protection device; the radiation protection device is provided with a first frame, wherein the first frame is used to fix the radiation protection device on the surface of a pipeline or container to be detected; a detection device, wherein the detection device is used to collect gamma rays released by the radiation source and transmit them to a data processing device; the detection device is provided with a second frame, wherein the second frame is used to fix the detection device on the surface of the pipeline or container to be detected, and the detection device and the radiation protection device are respectively located on both sides of the pipeline or container.

[0006] Furthermore, a groove for embedding the radiation source and a radiation source protection baffle for closing the groove are provided at the center of one side of the radiation protection device.

[0007] Furthermore, a radiation source carrier is provided between the radiation protection device and the radiation source, and the radiation source carrier is detachably installed in the radiation protection device.

[0008] Furthermore, a first magnet is provided on the radiation protection device at one side of the radiation source, the radiation protection device is connected to a radiation protection cover, and a second magnet matching the first magnet is provided on the connection side of the radiation protection cover.

[0009] Furthermore, the radiation source is a Na-22 radiation source, and the activity of the radiation source is ≤1×106Bq.

[0010] Furthermore, the detection device is a photomultiplier tube sensor.

[0011] Furthermore, the first frame includes a fixing frame sleeved on the outside of the radiation protection device, and the fixing frame is provided with evenly distributed fastening bolts corresponding to the four sides of the radiation protection device.

[0012] Furthermore, the first frame and the second frame are fixedly connected via a connecting member.

[0013] Furthermore, the second frame is provided with a protective shell of the package detection device and a signal collection window of the detection head of the exposure detection device.

[0014] The utility model embodiment has the following advantages:

[0015] The utility model discloses a nuclear density meter which uses a built-in radiation source design to control the direction in which the radiation source releases gamma rays and increases the thickness and width of the radiation protection device, thereby increasing the radiation protection effect; and also adds a radiation protection cover to avoid leakage of the disassembled radiation source, thereby comprehensively solving the radiation leakage problem during the production process, transportation process, use process, and replacement process of the radiation source.

[0016] The utility model discloses a nuclear density meter, in which a first frame and a second frame are fixed by connecting pieces, the connecting pieces have the same specifications and can adjust the connection distance, and are used to adjust the distance between the first frame and the second frame, so that the tightness between the first frame and the second frame and the corresponding position between the radiation source and the detection head can be adjusted by adjusting the connecting piece between the first frame and the second frame. BRIEF DESCRIPTION OF THE DRAWINGS

[0017] In order to more clearly illustrate the implementation of the utility model or the technical solution in the prior art, the following is a brief introduction to the drawings required for the implementation or the prior art description. Obviously, the drawings in the following description are only exemplary, and for ordinary technicians in this field, other implementation drawings can be derived from the provided drawings without creative work.

[0018] The structures, proportions, sizes, etc. illustrated in this specification are only used to match the contents disclosed in the specification so as to facilitate understanding and reading by persons familiar with the technology. They are not used to limit the conditions under which the present invention can be implemented, and therefore have no substantial technical significance. Any structural modification, change in proportion or adjustment of size shall still fall within the scope of the technical contents disclosed in the present invention without affecting the effects and purposes that can be achieved by the present invention.

[0019] Figure 1A product structure diagram of a nuclear density meter provided by an embodiment of the utility model;

[0020] Figure 2 A partial enlarged view of a radiation source device in a nuclear density meter provided in an embodiment of the utility model;

[0021] Figure 3 An internal structural diagram of a radiation source device in another nuclear density meter provided by an embodiment of the utility model;

[0022] Figure 4 An assembly diagram of a radiation source device and a radiation protection cover in another nuclear density meter provided in an embodiment of the utility model.

[0023] In the figure:

[0024] 1. Radiation protection device; 2. Radiation source; 3. Groove; 4. Radiation source protection baffle; 5. Radiation source carrier; 6. Radiation protection cover; 7. First magnet; 8. Second magnet; 9. Detection device; 10. First frame; 11. Fixing frame; 12. Fastening bolts; 13. Second frame; 14. Protective shell; 15. Signal acquisition window; 16. Connector; 17. Horizontal frame; 18. Vertical frame. DETAILED DESCRIPTION

[0025] The following is a specific embodiment of the present invention. People familiar with the technology can easily understand the other advantages and functions of the present invention from the contents disclosed in this specification. Obviously, the described embodiment is a part of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0026] like Figure 1 As shown, a nuclear density meter includes a radiation protection device 1, and a radiation source 2 is provided on the working side of the radiation protection device 1. In the present technology, the radiation source is preferably a Na-22 radiation source, the activity of the radiation source is ≤1×106Bq, and a safer low-dose Na-22 radiation source 2 is used, the radiation safety risk is low, and the environmental protection department meets the dosage requirements of the radiation source 2 exempted from management, and obtains the exemption record.

[0027] like Figure 2As shown, a groove 3 for embedding the radiation source 2 and a radiation source protection baffle 4 for closing the groove 3 are provided at the center of one side of the radiation protection device 1. The radiation source 2 is fixed in the groove 3, so that the surroundings of the radiation source 2 are shielded, and only the working direction is not shielded, and the gamma rays can only be directed to the material in the tube body to avoid radiation leakage. The protection baffle is used to isolate the radiation source 2 from the external environment and does not shield radiation. The radiation protection device 1 increases the thickness and width. The thickness of the radiation protection device 1 is not less than 3 times the thickness of the radiation source 2, and the diameter is not less than 3 times the diameter of the radiation source 2. The radiation source 2 is set at the center of the radiation protection device 1, so that any horizontal direction on the radiation protection device 1 is at least 1 times the width of the radiation protection source, thereby strengthening radiation shielding, and achieving a leakage dose of less than 1μSv / h at 0.1 meters around the radiation protection device 1.

[0028] like Figure 3 As shown, a radiation source carrier 5 is provided between the radiation protection device 1 and the radiation source 2, and the radiation source carrier 5 is detachably installed in the radiation protection device 1, so that the radiation source 2 can be detached, and different radiation sources 2 can be replaced according to different functions, or the decayed radiation source 2 can be replaced, which can improve the application scope of the radiation protection device. Specifically, the radiation source 2 is embedded in the center of the radiation source carrier 5, and the radiation source carrier 5 is embedded in the radiation protection device 1. The radiation source carrier 5 and the radiation protection device 1 can be made of the same material or different materials. The radiation source carrier 5 and the radiation protection device 1 are threadedly connected or grooved, etc. As long as the detachable connection between the radiation source carrier 5 and the radiation protection device 1 can be achieved, it falls within the protection scope of the present technology.

[0029] like Figure 4 As shown, the radiation protection device 1 is provided with a first magnet 7 on one side of the radiation source 2. If there is a radiation source protection baffle 4, the magnetic force of the first magnet 7 can penetrate the radiation source protection baffle 4. In order to increase the magnetic force effect, a window can be provided at the corresponding position of the radiation source protection baffle 4 or the thickness of the position can be reduced. The radiation protection device 1 is connected to the radiation protection cover 6. The connection side of the radiation protection cover 6 is provided with a second magnet 8 matching the first magnet 7, which is used to buckle the radiation protection cover 6 first when the radiation protection device 1 is disassembled to avoid the problem of radiation leakage.

[0030] Detection device 9, the detection device 9 is used to collect the gamma rays released by the radiation source 2 and transmit them to the data processing device. In this technology, the detection device 9 is preferably a photomultiplier tube sensor, and a high-voltage converter can also be configured. The detection device 9 adopts photoelectric detection technology, is very sensitive to extremely low-dose gamma rays, can provide higher accuracy and sensitivity, and adopts an integrated design, compact structure, stable and reliable performance, and easy installation and use; the detection device 9 is equipped with a high-precision sampling circuit to achieve high-precision sampling, the counting frequency resolution is 0.1Hz, the density resolution can reach 0.1kg / M3, and the density, standard density or special calculated value (solid percentage, specific gravity, etc.) adopts direct milliampere (4-20mA) output, and also supports Modbus-RTU RS-232485 communication output.

[0031] The radiation protection device 1 is provided with a first frame 10, and the first frame 10 is used to fix the radiation protection device 1 on the surface of the pipeline or container to be inspected. The first frame 10 includes a fixing frame 11 sleeved on the outside of the radiation protection device 1, such as Figure 1 As shown, the radiation protection device 1 is a round pancake-shaped structure, and the first frame 10 is provided with a fixing frame 11 sleeved on the outside of the radiation protection device 1, and the fixing frame 11 is provided with evenly distributed fastening bolts 12 corresponding to the surroundings of the radiation protection device 1, and the fastening bolts 12 are used to lock the fixing frame 11 and the radiation protection device 1. The through holes on the fixing frame 11 connected with the fastening bolts 12 can be set as strip holes, which is convenient for adjusting the distance between the radiation protection device 1 and the pipeline surface or the container surface in a small range.

[0032] The detection device 9 is provided with a second frame 13, and the second frame 13 is used to fix the detection device 9 on the surface of the pipeline or container to be detected. The detection device 9 and the radiation protection device 1 are respectively located on both sides of the pipeline or container. The second frame 13 is provided with a protective shell 14 that wraps the detection device 9 and a signal collection window 15 that exposes the detection head of the detection device 9.

[0033] The first frame 10 and the second frame 13 are fixedly connected by a connector 16 and are installed using a pipe external clamp, which will not damage the surface of the pipe or container. It is insensitive to the installation position, corrosion, pipe material, flow rate and pressure, and can be used in situations where non-contact measurement is required under harsh working conditions such as high temperature, high pressure, and poor fluidity, and allows a maximum solid content while maintaining fluidity.

[0034] In the present technology, it is preferred to use a screw rod. According to the diameter of the pipe or container, the screw rod can be a straight rod or a curved rod. If the diameter is too large, a curved rod is used to reduce the lateral width of the first frame 10 and the second frame 13. In the present technology, a straight rod is used as an example. The first frame 10 and the second frame 13 are both provided with a cross frame 17. The cross frame 17 is wider than the diameter of the pipe. Both ends of the cross frame 17 of the first frame 10 and the second frame 13 are fixedly connected by screw rods. Since the length of the detection device 9 is longer than the radiation protection device 1, in order to balance the force of the first frame 10 and the second frame 13, a longitudinal frame 18 is provided on one side or both sides of the radiation protection device 1 to increase the frame distance of the radiation protection device 1 so that the length of the first frame 10 and the second frame 13 are the same.

[0035] Although the utility model has been described in detail above with general descriptions and specific embodiments, it is obvious to those skilled in the art that some modifications or improvements can be made to the utility model. Therefore, these modifications or improvements made without departing from the spirit of the utility model are within the scope of protection claimed by the utility model.

Claims

1. A nuclear density meter, characterized in that: include: A radiation protection device, wherein a radiation source is provided on a working side of the radiation protection device; The radiation protection device is provided with a first frame, and the first frame is used to fix the radiation protection device on the surface of the pipeline or container to be inspected; A detection device, the detection device is used to collect gamma rays released by the radiation source and transmit them to the data processing device; The detection device is provided with a second frame, and the second frame is used to fix the detection device on the surface of the pipeline or container to be detected. The detection device and the radiation protection device are respectively located on both sides of the pipeline or container.

2. A nuclear density meter according to claim 1, characterized in that: A groove for embedding a radiation source and a radiation source protection baffle for closing the groove are provided at the center of one side of the radiation protection device.

3. A nuclear density meter according to claim 2, characterized in that: A radiation source carrier is provided between the radiation protection device and the radiation source, and the radiation source carrier is detachably installed in the radiation protection device.

4. A nuclear density meter according to claim 2, characterized in that: A first magnet is provided on the radiation protection device at one side of the radiation source, the radiation protection device is connected to a radiation protection cover, and a second magnet matching the first magnet is provided on the connection side of the radiation protection cover.

5. A nuclear density meter according to claim 1, characterized in that: The radiation source is a Na-22 radiation source, and the activity of the radiation source is ≤1×106Bq.

6. A nuclear density meter according to claim 1, characterized in that: The detection device is a photomultiplier tube sensor.

7. A nuclear density meter according to claim 1, characterized in that: The first frame includes a fixing frame sleeved on the outside of the radiation protection device, and the fixing frame is provided with evenly distributed fastening bolts corresponding to the surroundings of the radiation protection device.

8. A nuclear density meter according to claim 1, characterized in that: The first frame and the second frame are fixedly connected via a connecting piece.

9. A nuclear density meter according to claim 1, characterized in that: The second frame is provided with a protective shell of the package detection device and a signal collection window of the detection head of the exposure detection device.

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