Pressurization verification device for liquid level meter of spent fuel pool of nuclear power station
By designing a pressure testing and calibration device for the level gauge in the spent fuel pool of a nuclear power plant, and utilizing components such as a safety vent valve, an isolation valve, and an adjustable pressure reducing valve, the problem of high operational risk and long cycle in level gauge calibration was solved, achieving safe and convenient level gauge calibration.
Patent Information
- Application Number
- CN202520485747.4
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2025-03-18
- Publication Date
- 2026-01-13
- Estimated Expiration
- 2035-03-18
AI Technical Summary
Calibration of level gauges in spent fuel pools at nuclear power plants is fraught with operational risks, has a long cycle, and may pose a potential risk of radioactive leakage.
Design a pressure testing and calibration device for the level gauge of spent fuel pool in a nuclear power plant, including an installation box and a gas pipeline, equipped with a safety exhaust valve, an isolation valve, an adjustable pressure reducing valve and a pressure gauge, for accurately adjusting the gas source pressure to ensure safe calibration.
This achieves both safety and ease of level gauge calibration, shortens the calibration cycle, and reduces the risk of radioactive leakage.
Smart Images
Figure CN223796116U_ABST
Abstract
Description
Technical Field
[0001] This utility model relates to the field of nuclear power technology, and in particular to a pressure testing and calibration device for a level gauge in a spent fuel pool of a nuclear power plant. Background Technology
[0002] Due to design flaws, differential pressure level gauges cannot be used to measure the liquid level in the spent fuel pool of a certain nuclear power plant. Therefore, the liquid level monitoring adopts an integrated device from imported FCI. This calibration requires a realistic simulation of the water level drop condition, which is achieved by draining the spent fuel pool. This poses high operational risks, a long cycle, and the potential for radioactive leakage. Utility Model Content
[0003] The technical problem to be solved by this utility model is to provide a pressure testing and calibration device for the liquid level gauge of the spent fuel pool in a nuclear power plant, so as to solve the problems of high operational risk, long cycle and potential radioactive leakage hazards in the liquid level gauge calibration of related technologies.
[0004] The technical solution adopted by this utility model to solve its technical problem is: to construct a pressure testing and calibration device for a liquid level gauge in a spent fuel pool of a nuclear power plant, including an installation box and a gas transmission pipeline. The installation box includes a box body and a box cover that cooperate with each other. The box body has a first side plate and a second side plate that are arranged in parallel and spaced apart.
[0005] The first end of the gas transmission pipeline is located on the first side plate and is used to connect to the gas source device. The second end of the gas transmission pipeline is located on the second side plate and is used to connect to the interface of the measuring tank in the spent fuel pool of the nuclear power plant.
[0006] The gas pipeline is equipped with a safety exhaust valve, an isolation valve, an adjustable pressure reducing valve, and a pressure gauge in sequence from its first end to its second end.
[0007] In some embodiments, the box body has a square cylindrical structure, the box body includes a bottom plate, the first side plate is connected to the second side plate, the box body also includes a third side plate and a fourth side plate, the third side plate and the fourth side plate are arranged parallel and spaced apart, the two ends of the third side plate are respectively connected to the first side plate and the first side plate of the second side plate, and the two ends of the fourth side plate are respectively connected to the second side plate of the first side plate and the second side plate.
[0008] In some embodiments, the first side of the box cover is connected to the third side plate via a rotating structure;
[0009] The second side of the box cover is connected to the fourth side plate by a locking structure.
[0010] In some embodiments, the rotating structure includes a hinge or a rotating mechanism.
[0011] In some embodiments, the locking structure includes a first connecting ear disposed on a second side of the lid and a second connecting ear disposed on the fourth side plate, and also includes fasteners for connecting the first connecting ear and the second connecting ear.
[0012] In some embodiments, the box body or the box lid is also provided with a handle.
[0013] In some embodiments, the housing is provided with a support block connected to the gas pipeline.
[0014] In some embodiments, the first end of the gas pipeline is provided with a first quick connector, and the second end of the gas pipeline is provided with a second quick connector.
[0015] In some embodiments, the isolation valve includes a manual isolation valve.
[0016] In some embodiments, the pressure gauge includes a direct-reading pressure gauge.
[0017] The following are the beneficial effects of implementing this utility model: the pressure testing and calibration device for the spent fuel water pool level gauge of the nuclear power plant has a relatively simple structure, high safety in use, and is easy to manufacture and promote. In addition, the device has a relatively compact structure, is easy to transport and store, and has high practicality. Attached Figure Description
[0018] To more clearly illustrate the technical solution of this utility model, the present utility model will be further described below in conjunction with the accompanying drawings and embodiments. It should be understood that the following drawings only show some embodiments of this utility model and should not be considered as a limitation of the scope. For those skilled in the art, other related drawings can be obtained from these drawings without creative effort. In the drawings:
[0019] Figure 1 This is a schematic diagram of the installation of a spent fuel pool level gauge in a nuclear power plant according to some embodiments of this utility model;
[0020] Figure 2 This is a schematic diagram of the structure of the pressure testing and calibration device for the liquid level gauge of the spent fuel pool in a nuclear power plant in some embodiments of this utility model;
[0021] Figure 3 This is a schematic diagram of the structure of a pressure testing and calibration device for a spent fuel water pool level gauge in a nuclear power plant, according to some embodiments of this utility model. Detailed Implementation
[0022] To provide a clearer understanding of the technical features, objectives, and effects of this utility model, the specific embodiments of this utility model are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the orientations or positional relationships indicated by terms such as "front," "rear," "upper," "lower," "left," "right," "longitudinal," "horizontal," "vertical," "horizontal," "top," "bottom," "inner," "outer," "head," and "tail" are based on the orientations or positional relationships shown in the accompanying drawings, and are constructed and operated in a specific orientation. They are only for the convenience of describing this technical solution and do not indicate that the device or component referred to must have a specific orientation; therefore, they should not be construed as limitations on this utility model.
[0023] It should also be noted that, unless otherwise explicitly specified and limited, terms such as "installation," "connection," "joining," "fixing," and "setting" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components. When an component is referred to as being "on" or "below" another component, the component can be located "directly" or "indirectly" on the other component, or there may be one or more intermediary components. The terms "first," "second," "third," etc., are only for the convenience of describing this technical solution and should not be construed as indicating or implying relative importance or implicitly specifying the number of indicated technical features. Therefore, features defined with "first," "second," "third," etc., may explicitly or implicitly include one or more of that feature. For those skilled in the art, the specific meaning of the above terms in this utility model can be understood according to the specific circumstances.
[0024] In the following description, specific details such as particular system structures and techniques are set forth for illustrative purposes and not for limitation, in order to provide a thorough understanding of the embodiments of the present invention. However, those skilled in the art will understand that the present invention can be implemented in other embodiments without these specific details. In other instances, detailed descriptions of well-known systems, apparatuses, circuits, and methods are omitted so as not to obscure the description of the present invention with unnecessary detail.
[0025] See Figure 1 The spent fuel pool level gauge 200 in the spent fuel pool 100 of the nuclear power plant is installed in the measuring tank 300. The measuring tank 300 is provided with an interface 400, which can be a quick interface.
[0026] like Figure 2 and Figure 3As shown, this utility model discloses a pressure testing and calibration device for a spent fuel water pool level gauge in a nuclear power plant. The device can be used to pressurize the measuring tank 300, causing the liquid level in the measuring tank 300 to drop, thereby verifying the level gauge and level alarm point of the spent fuel water pool in the nuclear power plant.
[0027] The pressure testing and calibration device for the level gauge in the spent fuel pool of a nuclear power plant includes a mounting box 10 and a gas transmission pipeline 20. The mounting box 10 includes a cooperating housing 11 and a cover 12. The housing 11 has a first side plate 112 and a second side plate 113 arranged in parallel and spaced apart. The first end of the gas transmission pipeline 20 is located on the first side plate 112 and is used to connect to a gas source device. The second end of the gas transmission pipeline 20 is located on the second side plate 113 and is used to connect to the interface 400 of the measuring tank 300 inside the spent fuel pool 100 of the nuclear power plant. From its first end to its second end, the gas transmission pipeline 20 is sequentially equipped with a safety vent valve 30, an isolation valve 40, an adjustable pressure reducing valve 50, and a pressure gauge 60, which can accurately adjust the gas source pressure and accurately calculate the height of the liquid level drop. The safety vent valve 30 is provided to prevent the gas transmission pipeline 20 from rupturing due to excessive gas source pressure, thus avoiding industrial safety risks. The isolation valve 40 and pressure gauge 60 enable the system to cut off the gas supply at any time and monitor the output pressure in real time. The adjustable pressure reducing valve 50 can be an adjustable filter pressure reducing valve to reduce the upstream gas supply pressure and filter impurities from the upstream gas supply.
[0028] In some embodiments, the housing 11 has a square cylindrical structure. The housing 11 includes a bottom plate 111, a first side plate 112 connected to a second side plate 113, and a third side plate 114 and a fourth side plate 115. The third side plate 114 and the fourth side plate 115 are arranged parallel to each other and spaced apart. The two ends of the third side plate 114 are respectively connected to the first sides of the first side plate 112 and the second side plate 113, and the two ends of the fourth side plate 115 are respectively connected to the second sides of the first side plate 112 and the second side plate 113. The housing 11 can be a single-piece structure to improve overall structural strength. Furthermore, the housing 11 can be made of a metal material, including but not limited to stainless steel or aluminum alloy.
[0029] In some embodiments, the first side of the lid 12 is connected to the third side plate 114 via a rotating structure 116; the second side of the lid 12 is connected to the fourth side plate 115 via a locking structure.
[0030] In some embodiments, the rotating structure 116 includes a hinge or a hinge chain.
[0031] In some embodiments, the locking structure includes a first connecting lug 117 disposed on the second side of the lid 12 and a second connecting lug 118 disposed on the fourth side plate 115. It also includes a fastener for connecting the first connecting lug 117 and the second connecting lug 118. The fastener may be a combination of bolts and nuts, including but not limited to. The bolt passes through the first connecting lug 117 and the second connecting lug 118 and is then locked by the nut. This locking method is simple and convenient, and makes the lid 12 difficult to open. Of course, the locking structure may also include a latch or other similar structure; no specific limitation is made here.
[0032] In some embodiments, the housing 11 or the lid 12 is further provided with a handle 13. For example, the first side plate 112, the second side plate 113, the third side plate 114, or the fourth side plate 115 of the housing 11 are provided with handles 13, or the lid 12 is provided with handles 13. The handles 13 facilitate the carrying and transportation of the spent fuel pool level gauge pressure calibration device of the nuclear power plant by the staff.
[0033] In some embodiments, the housing 11 is provided with a support block 14 connected to the gas pipeline 20. The bottom of the support block 14 may be fixed to the base plate 111. There may be two support blocks 14, which are spaced apart along the axial direction of the gas pipeline 20 to support the gas pipeline 20. The support blocks 14 may be made of shock-absorbing material, such as EPDM rubber. Of course, the number, structure and material of the support blocks 14 can be selected according to actual needs, and no specific limitation is made here.
[0034] In some embodiments, the first end of the gas pipeline 20 is provided with a first quick connector, and the second end of the gas pipeline 20 is provided with a second quick connector to facilitate quick connection. The first quick connector may be connected to the interface 400 via a second connecting line. The second quick connector may be connected to a gas source device via a second connecting line, and the second connecting line and the second connecting line may be housed in the installation box 10. The gas source device includes, but is not limited to, an air compressor. Preferably, when the pressure testing and calibration device for the spent fuel pool level gauge of the nuclear power plant is in a non-operating state, the first quick connector and the second quick connector can be sealed with a sealing plug. In addition, during pressure testing, a certain amount of compressed air can be introduced into the gas pipeline 20 first to remove any impurities that may be present in the gas pipeline 20.
[0035] In some embodiments, the isolation valve 40 includes a manual isolation valve. In some embodiments, the pressure gauge 60 includes a direct-reading pressure gauge.
[0036] The pressure testing and calibration device for the spent fuel pool level gauge of the nuclear power plant is applied as follows: The first end of the gas pipeline 20 is connected to the gas source device, and the first end of the gas pipeline 20 is connected to the interface 400. The gas source device inputs a medium (such as compressed air) into the gas pipeline 20. The medium passes through the safety exhaust valve 30 (the function of the safety exhaust valve 30 is to protect the gas pipeline 20 from overpressure, and it automatically exhausts when the pressure exceeds a certain set value). After the safety exhaust valve 30, it passes through the isolation valve 40, then through the adjustable pressure reducing valve 50 and the pressure gauge 60, and finally outputs to the measuring tank 300 to perform pressure testing to verify whether the spent fuel pool level gauge and the action threshold of each alarm point of the spent fuel pool level gauge of the nuclear power plant are accurate, so as to ensure the stable operation of the spent fuel pool level gauge of the nuclear power plant.
[0037] The pressure testing and calibration device for the spent fuel pool level gauge of the nuclear power plant has a relatively simple structure, high safety in use, and is easy to manufacture and promote. In addition, the device has a relatively compact structure, which makes it easy to transport and store, and it is highly practical.
[0038] It is understood that the above embodiments only illustrate preferred embodiments of the present utility model, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present utility model patent. It should be noted that for those skilled in the art, the above technical features can be freely combined, and several modifications and improvements can be made without departing from the concept of the present utility model, all of which fall within the protection scope of the present utility model. Therefore, all equivalent transformations and modifications made within the scope of the claims of the present utility model should fall within the coverage of the claims of the present utility model.
Claims
1. A pressure testing and calibration device for a level gauge in a spent fuel pool of a nuclear power plant, characterized in that, It includes an installation box (10) and a gas pipeline (20). The installation box (10) includes a box body (11) and a box cover (12) that cooperate with each other. The box body (11) has a first side plate (112) and a second side plate (113) that are arranged in parallel and spaced apart. The first end of the gas transmission pipe (20) is located on the first side plate (112), and the first end of the gas transmission pipe (20) is used to connect to the gas source device. The second end of the gas transmission pipe (20) is located on the second side plate (113), and the second end of the gas transmission pipe (20) is used to connect to the interface of the measuring tank in the spent fuel pool of the nuclear power plant. The gas pipeline (20) is provided with a safety exhaust valve (30), an isolation valve (40), an adjustable pressure reducing valve (50) and a pressure gauge (60) in sequence from its first end to its second end.
2. The pressure testing and calibration device for the spent fuel pool level gauge in a nuclear power plant according to claim 1, characterized in that, The box body (11) has a square cylindrical structure. The box body (11) includes a bottom plate (111), the first side plate (112) and the second side plate (113) are connected, and the box body (11) also includes a third side plate (114) and a fourth side plate (115). The third side plate (114) and the fourth side plate (115) are arranged in parallel and spaced apart. The two ends of the third side plate (114) are respectively connected to the first side of the first side plate (112) and the second side plate (113), and the two ends of the fourth side plate (115) are respectively connected to the second side of the first side plate (112) and the second side plate (113).
3. The pressure testing and calibration device for the spent fuel pool level gauge in a nuclear power plant according to claim 2, characterized in that, The first side of the box cover (12) is connected to the third side plate (114) by a rotating structure; The second side of the lid (12) is connected to the fourth side plate (115) by a locking structure.
4. The pressure testing and calibration device for the spent fuel pool level gauge in a nuclear power plant according to claim 3, characterized in that, The rotating structure includes a hinge or a rotating mechanism.
5. The pressure testing and calibration device for the spent fuel pool level gauge in a nuclear power plant according to claim 3, characterized in that, The locking structure includes a first connecting ear on the second side of the cover (12) and a second connecting ear on the fourth side plate (115), and also includes fasteners for connecting the first connecting ear and the second connecting ear.
6. The pressure testing and calibration device for the spent fuel pool level gauge in a nuclear power plant according to claim 1, characterized in that, The box body (11) or the box cover (12) is also provided with a handle (13).
7. The pressure testing and calibration device for the spent fuel pool level gauge of a nuclear power plant according to claim 1, characterized in that, The housing (11) is provided with a support block (14) that is connected to the gas pipeline (20).
8. The pressure testing and calibration device for the spent fuel pool level gauge of a nuclear power plant according to claim 1, characterized in that, The first end of the gas pipeline (20) is provided with a first quick connector, and the second end of the gas pipeline (20) is provided with a second quick connector.
9. The pressure testing and calibration device for the level gauge of the spent fuel pool in a nuclear power plant according to claim 1, characterized in that, The isolation valve (40) includes a manual isolation valve.
10. The pressure testing and calibration device for the spent fuel pool level gauge of a nuclear power plant according to claim 1, characterized in that, The pressure gauge (60) includes a direct-reading pressure gauge.