A split type gas detector resistant to radiation

Abstract

The utility model relates to gas detection equipment technical field, the utility model provides a kind of split type gas detector of anti-radiation, including outer bucket, composite bucket for reinforcing structural strength is coaxially sleeved in outer bucket from outside to inside sequentially, first shielding barrel for absorbing neutron and second shielding barrel for shielding gamma ray, gas sensing element is limit installed in second shielding barrel by support, gas diffusion hole that is sequentially penetrated second shielding barrel, first shielding barrel, composite bucket and outer bucket is established in gas sensing element below, and the heat dissipation cavity formed between the outer side wall of first shielding barrel and the inner side wall of second shielding barrel, second shielding barrel is provided with the air inlet pipe and the air outlet pipe being communicated with heat dissipation cavity, air inlet pipe and air outlet pipe are all connected in driven pump, the effective resistance to mixed radiation is realized, adapts complex radiation environment, simultaneously through gas circulation sustained transfer heat dissipation cavity heat, stable control detector internal temperature to meet the demand of radiation scene heat management.

Description

Technical Field

[0001] This utility model relates to the field of gas detection equipment technology, and more specifically, to a radiation-resistant split-type gas detector. Background Technology

[0002] In special scenarios such as nuclear facility operation, radioactive material storage, and nuclear waste disposal, real-time and accurate detection of gas leaks is crucial for ensuring personnel safety, equipment stability, and environmental protection. Split-type gas detectors, due to the ability to independently install probes and processing units, can adapt to complex site layouts and have become an important type of equipment for gas detection in such radiation environments. However, the mixed radiation in the radiation environment, such as gamma rays and neutrons, can directly corrode the gas-sensitive elements and circuit modules inside the detector, leading to decreased detection accuracy or even equipment failure. Simultaneously, if the heat generated by the detector itself and the heat transferred by radiation cannot be dissipated in time, it will accelerate component aging and shorten the equipment's lifespan. Existing split-type gas detectors have significant shortcomings in the coordinated design of radiation shielding performance and heat dissipation efficiency, making it difficult to meet the practical requirements for long-term stable operation in high-radiation scenarios. Utility Model Content

[0003] The purpose of this invention is to provide a radiation-resistant split-type gas detector, which solves the problem that existing split-type gas detectors have poor radiation shielding and heat dissipation coordination, making it difficult to operate stably in high-radiation scenarios.

[0004] This utility model is achieved through the following technical solution: a radiation-resistant split-type gas detector, including an outer barrel, inside which a composite barrel for enhancing structural strength, a first shielding barrel for absorbing neutrons, and a second shielding barrel for shielding gamma rays are coaxially sleeved from the outside to the inside. A gas-sensitive element is installed in the second shielding barrel by a bracket. A gas diffusion hole is opened below the gas-sensitive element, which passes through the second shielding barrel, the first shielding barrel, the composite barrel, and the outer barrel in sequence. A heat dissipation cavity is formed between the outer side wall of the first shielding barrel and the inner side wall of the second shielding barrel. The second shielding barrel is provided with an inlet pipe and an outlet pipe that communicate with the heat dissipation cavity. Both the inlet pipe and the outlet pipe are connected to a drive pump.

[0005] Furthermore, the second shielding barrel is bonded to the first shielding barrel with epoxy resin, and the first shielding barrel is ultrasonically welded to the composite barrel.

[0006] Furthermore, a stepped annular groove is formed on the inner wall of the first shielding barrel.

[0007] Furthermore, the bracket is made of polytetrafluoroethylene, and the outer wall of the bracket is evenly spaced along the circumference with a number of positioning protrusions that abut against the inner wall of the second shielding barrel.

[0008] Furthermore, the first shielding barrel is made of boron polyethylene or zirconium boride ceramic.

[0009] Furthermore, the second shielding barrel is made of lead-tin alloy or tungsten alloy.

[0010] Furthermore, the composite barrel is made of carbon fiber.

[0011] Furthermore, the outer barrel is made of stainless steel.

[0012] This utility model has at least the following advantages and beneficial effects: the cylindrical closed structure formed by the multi-layer coaxially connected outer barrel, composite barrel, first shielding barrel and second shielding barrel effectively resists mixed radiation and is suitable for complex radiation environments. At the same time, the heat of the heat dissipation cavity is continuously transferred through gas circulation, and the internal temperature of the detector is stably controlled to meet the thermal management requirements of the radiation scene. Attached Figure Description

[0013] Figure 1 A cross-sectional view of a radiation-resistant split-type gas detector provided by this utility model.

[0014] Reference numerals: 1-Outer barrel, 2-Composite barrel, 3-First shielding barrel, 31-Stepped annular groove, 4-Second shielding barrel, 41-Inlet pipe, 42-Outlet pipe, 5-Support, 6-Gas-sensitive element, 7-Gas diffusion hole, 8-Heat dissipation cavity. Detailed Implementation

[0015] The specific implementation method is described below with reference to the accompanying drawings.

[0016] Example like Figure 1As shown, this embodiment mainly discloses a radiation-resistant split-type gas detector, including an outer barrel 1. Inside the outer barrel 1, from the outside to the inside, are a composite barrel 2 for enhancing structural strength, a first shielding barrel 3 for absorbing neutrons, and a second shielding barrel 4 for shielding gamma rays, all coaxially fitted together. A gas-sensitive element 6 is installed inside the second shielding barrel 4 by a bracket 5. Below the gas-sensitive element 6, a gas diffusion hole 7 is opened, passing through the second shielding barrel 4, the first shielding barrel 3, the composite barrel 2, and the outer barrel 1 in sequence. A heat dissipation cavity 8 is formed between the outer side wall of the first shielding barrel 3 and the inner side wall of the second shielding barrel 4. The second shielding barrel 4 is provided with an inlet pipe 41 and an outlet pipe 42 communicating with the heat dissipation cavity 8. Both the inlet pipe 41 and the outlet pipe 42 are connected to a drive pump. Specifically, the drive pump can be a peristaltic pump in the prior art. The outer barrel 1, the composite barrel 2, the first shielding barrel 3, and the second shielding barrel 4 are all cylindrical structures with a closed bottom and an open top, and the top opening is limited and closed by a top cover. The composite barrel 2 ensures structural strength, the first shielding barrel 3 specifically absorbs neutrons, and the second shielding barrel 4 efficiently shields gamma rays, thus resisting mixed radiation and adapting to complex radiation environments. Gas diffusion holes 7 penetrate the multi-layered structure, ensuring precise contact between the gas to be detected and the gas-sensitive element 6. The heat dissipation cavity 8 is connected to the drive pump via the inlet pipe 41 and the outlet pipe 42, forming a closed flow channel. The heat generated by the gas-sensitive element 6 and external radiation are transferred to the second shielding barrel 4 and the first shielding barrel 3, and then conducted to the heat dissipation cavity 8. The drive pump is activated, driving the gas to circulate within the closed flow channel, continuously carrying the heat-absorbing gas away from the heat dissipation cavity 8. Simultaneously, the gas is naturally cooled through the outlet pipe 42, or a cooling pipe can be fitted onto the outlet pipe 42 and the inlet pipe 41 to further enhance the gas cooling effect. Then, the cooler gas is reintroduced into the cavity. Through this continuous gas circulation, the heat inside the device is continuously transferred to the outside, achieving stable temperature control of the detector and meeting the thermal management requirements for equipment operation in radiation environments.

[0017] In addition, the gas-sensitive element 6 is connected to the processing unit via a connecting assembly. The connecting assembly is a shielded cable with an outer lead-tin alloy foil layer for radiation shielding and a brass braided mesh in the middle for interference resistance. The interface of the connecting assembly, combined with a fluororubber sealing ring, can achieve IP68 protection, making it suitable for harsh environments such as nuclear facilities that are humid and dusty, thus improving the applicability of the equipment. The processing unit adopts a single-layer thin stainless steel shell, which not only achieves physical separation between the detection end and the control end to adapt to installation in narrow spaces, but also reduces the overall weight through differentiated shielding design (strong shielding at the detection end and lightweight design of the processing unit).

[0018] Furthermore, in specific implementation, the second shielding barrel 4 provided in this embodiment of the present invention is bonded to the first shielding barrel 3 with epoxy resin, and the first shielding barrel 3 is ultrasonically welded to the composite barrel 2. Specifically, the epoxy resin bonding has high temperature resistance, adapts to temperature fluctuations in the radiation environment, and the bonding surface can enhance adhesion through a preset annular groove, ensuring that the second shielding barrel 4 and the first shielding barrel 3 are in long-term contact, avoiding radiation leakage caused by interlayer gaps; ultrasonic welding achieves a seamless connection between the first shielding barrel 3 and the composite barrel 2, with good weld seam sealing, which not only prevents external dust and moisture from entering the shielding interior and corroding the gas-sensitive element 6, but also ensures the supporting role of the composite barrel 2 for the overall structure, avoiding deformation of the shielding layer due to loose connection, and further improving the structural stability and service life of the equipment under complex working conditions.

[0019] Furthermore, in a specific implementation, a stepped annular groove 31 is provided on the inner wall of the first shielding barrel 3 provided in this embodiment of the present invention. Specifically, the inner wall of the stepped annular groove 31 and the second shielding barrel 4 together form a heat dissipation cavity 8. The stepped annular groove 31 can increase the flow disturbance of the gas in the heat dissipation cavity 8, expand the contact area between the medium and the inner wall of the first shielding barrel 3, and improve the heat exchange efficiency.

[0020] Furthermore, in specific implementation, the bracket 5 provided in this embodiment of the present invention is made of polytetrafluoroethylene (PTFE), and the outer wall of the bracket 5 is provided with a plurality of positioning protrusions evenly spaced along the circumference, which abut against the inner wall of the second shielding barrel 4. Specifically, PTFE has excellent radiation resistance and insulation properties, which can prevent the bracket 5 from aging and breaking under radiation environment; at the same time, the positioning protrusions can accurately limit the gas-sensitive element 6 to the center position inside the device, preventing the gas-sensitive element 6 from sticking to the second shielding barrel 4, which would lead to an increase in local radiation dose, reduce the detection accuracy attenuation of the gas-sensitive element 6 due to radiation erosion, and prevent the element from shifting due to equipment vibration, thereby further extending the service life of the gas-sensitive element 6.

[0021] Furthermore, in specific implementations, the first shielding barrel 3 provided in this embodiment of the present invention is made of boron polyethylene or zirconium boride ceramic. Specifically, boron polyethylene has a low density (approximately 0.96 g / cm³), which effectively reduces the weight of the device and has high neutron absorption efficiency, making it suitable for low to medium radiation intensity scenarios; zirconium boride ceramic has higher high-temperature resistance and neutron absorption cross-section, making it suitable for high-temperature and high-radiation scenarios such as near nuclear reactors. This allows for flexible adjustments based on different radiation environments, expanding the product's applicability.

[0022] Furthermore, in specific implementations, the second shielding barrel 4 provided in this embodiment of the present invention is made of lead-tin alloy or tungsten alloy. Specifically, lead-tin alloy has excellent gamma-ray shielding effect, is soft and easy to process, and has a lower density than pure lead, which can reduce the weight of the device; tungsten alloy has a higher gamma-ray shielding efficiency than lead-tin alloy at the same thickness, and has high mechanical strength, making it suitable for high radiation dose scenarios (such as nuclear waste repositories). The two materials cover different radiation intensity requirements, ensuring shielding performance while also taking into account processing and lightweight objectives.

[0023] Furthermore, in specific implementations, the composite tank 2 provided in this embodiment of the present invention is made of carbon fiber. Specifically, carbon fiber has good tensile strength, which can ensure the overall structural rigidity of the outer tank 1 even with a relatively thin thickness (1-2mm), preventing the shielding layer from deforming due to external force collisions in a radiation environment; at the same time, carbon fiber has a density of only about 1.7g / cm³, which can significantly reduce the overall weight of the device; in addition, carbon fiber is radiation-resistant and corrosion-resistant, and can adapt to the harsh environment of nuclear facilities for a long time, extending the service life of the equipment.

[0024] Furthermore, in specific implementations, the outer barrel 1 provided in this embodiment of the present invention is made of stainless steel. Specifically, stainless steel has good corrosion resistance and rust resistance, and can resist the humid moisture and corrosive gases in the nuclear facility environment, preventing the inner shielding layer from being exposed and damaged due to the corrosion of the outer barrel 1; at the same time, stainless steel is easy to process and form, and can be made into a high-precision fitting structure to ensure the fit with the inner composite barrel 2, the first shielding barrel 3 and the second shielding barrel 4, and to prevent radiation leakage or gas retention due to structural gaps.

Claims

1. A radiation hard split gas detector, characterized in that The device includes an outer barrel (1), inside which a composite barrel (2) for enhancing structural strength, a first shielding barrel (3) for absorbing neutrons, and a second shielding barrel (4) for shielding gamma rays are coaxially sleeved from the outside to the inside. A gas-sensitive element (6) is installed in the second shielding barrel (4) by means of a bracket (5). A gas diffusion hole (7) is provided below the gas-sensitive element (6) and passes through the second shielding barrel (4), the first shielding barrel (3), the composite barrel (2), and the outer barrel (1) in sequence. A heat dissipation cavity (8) is formed between the outer side wall of the first shielding barrel (3) and the inner side wall of the second shielding barrel (4). The second shielding barrel (4) is provided with an air inlet pipe (41) and an air outlet pipe (42) that communicate with the heat dissipation cavity (8). Both the air inlet pipe (41) and the air outlet pipe (42) are connected to a drive pump.

2. The radiation-resistant split-type gas detector according to claim 1, characterized in that, The second shielding barrel (4) is bonded to the first shielding barrel (3) with epoxy resin, and the first shielding barrel (3) is ultrasonically welded to the composite barrel (2).

3. The radiation hard split gas detector of claim 1, wherein, The inner wall of the first shielding barrel (3) is provided with a stepped annular groove (31).

4. The radiation harden split gas detector of claim 1, wherein, The bracket (5) is made of polytetrafluoroethylene, and the outer wall of the bracket (5) is provided with a number of positioning protrusions that abut against the inner wall of the second shielding barrel (4) at even intervals along the circumference.

5. The radiation harden split gas detector of claim 1, wherein, The first shielding barrel (3) is made of boron polyethylene or zirconium boride ceramic.

6. The radiation harden split gas detector of claim 1, wherein, The second shielding barrel (4) is made of lead-tin alloy or tungsten alloy.

7. The radiation harden split gas detector of claim 1, wherein, The composite barrel (2) is made of carbon fiber.

8. A radiation-resistant split-type gas detector according to claim 1, characterized in that, The outer barrel (1) is made of stainless steel.

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