Nuclear power plant circulating water pump shaft seal leakage rate monitoring device and flow monitoring equipment
By designing a monitoring device for shaft seal leakage in nuclear power plant circulating water pumps, the device can monitor the shaft seal water flow and filter pressure differential in real time, thus solving the problem of equipment damage and economic losses caused by shaft seal leakage in nuclear power plant circulating water pumps and improving the reliability and economy of the equipment.
Patent Information
- Application Number
- CN202520188753.3
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2025-02-06
- Publication Date
- 2025-12-12
- Estimated Expiration
- 2035-02-06
AI Technical Summary
When the shaft seal leakage of circulating water pumps in nuclear power plants is abnormal, there is a risk of both external and internal leakage, which may lead to equipment damage or unplanned shutdowns. Current technology lacks real-time monitoring methods, resulting in economic losses.
Design a device for monitoring shaft seal leakage of circulating water pump in nuclear power plant, including a three-way valve, a flow measurement module, an industrial control server and a wireless communication module. The device monitors shaft seal water flow and filter pressure difference in real time via wireless communication, generates information and sends it to the host computer.
It enables real-time monitoring of shaft seal leakage in circulating water pumps, timely detection of abnormalities, prevention of equipment damage and unplanned downtime, improvement of equipment reliability, and reduction of economic losses.
Smart Images

Figure CN223662108U_ABST
Abstract
Description
Technical Field
[0001] This utility model relates to the field of nuclear power plant equipment technology, and in particular to a device for monitoring shaft seal leakage and flow rate of a nuclear power plant circulating water pump. Background Technology
[0002] Nucleic acid power plants have repeatedly reported abnormal shaft seal leakage in their circulating water pumps. Large leakage levels pose risks of both external and internal leaks, leading to delayed drainage, water ingress into the bearings, damage to bearing lubrication, and in severe cases, corrosion and damage to components. Conversely, small leakage levels may cause the shaft seal to wear and burn out. During normal unit operation, shaft seal maintenance requires rendering the circulating pumps unusable, resulting in reduced unit power output and economic losses. Therefore, nuclear power plants urgently need a device capable of real-time monitoring of circulating water pump shaft seal leakage. Utility Model Content
[0003] The technical problem to be solved by this utility model is to provide a device for monitoring shaft seal leakage of circulating water pumps in nuclear power plants and a flow monitoring device.
[0004] The technical solution adopted by this utility model to solve its technical problem is: to construct a monitoring device for shaft seal leakage of circulating water pump in nuclear power plant, including a three-way valve, a flow measurement module, an industrial control server and a first wireless communication module;
[0005] The first valve port of the three-way valve is used to mechanically connect to the shaft seal water drain pipe, the second valve port of the three-way valve is used to mechanically connect to the shaft seal water treatment equipment, and the third valve port of the three-way valve is mechanically connected to the inlet of the flow measurement module, so as to guide the shaft seal water to the shaft seal water treatment equipment or to the flow measurement module.
[0006] The outlet of the flow measurement module is mechanically connected to the shaft seal water treatment equipment and measures the flow rate of the shaft seal water to generate shaft seal water flow information.
[0007] The industrial control server is communicatively connected to the flow measurement module and the first wireless communication module, and is used to receive the shaft seal water flow information;
[0008] The first wireless communication module is communicatively connected to the industrial control server, and the first wireless communication module is used to send the shaft seal water flow information to the host computer.
[0009] Preferably, the nuclear power plant circulating water pump shaft seal leakage monitoring device further includes a filter and a pressure measurement module;
[0010] The filter element is mechanically connected between the third valve port of the three-way valve and the inlet of the flow measurement module to filter the shaft seal water introduced into the flow measurement module.
[0011] The pressure measurement module is mechanically connected to the inlet and outlet of the filter element at both ends, and measures the pressure difference between the inlet and outlet of the filter element to generate filter element pressure difference information. The pressure measurement module is also communicatively connected to the industrial control server to send the filter element pressure difference information to the host computer via the industrial control server and the first wireless communication module.
[0012] Preferably, the filter element is a Y-type filter.
[0013] Preferably, the nuclear power plant circulating water pump shaft seal leakage monitoring device further includes a second wireless communication module and a third wireless communication module;
[0014] The second wireless communication module is electrically connected to the pressure measurement module, and the second wireless communication module is communicatively connected to the industrial control server to send the differential pressure information of the filter element to the industrial control server;
[0015] The third wireless communication module is electrically connected to the flow measurement module, and the second wireless communication module is communicatively connected to the industrial control server to send the shaft seal water flow information to the industrial control server.
[0016] Preferably, the flow measurement module includes a flow meter, a data processing module, and a power supply module;
[0017] The flow meter is mechanically connected between the outlet end of the filter element and the shaft seal water treatment equipment. The flow meter is used to measure the flow rate of the shaft seal water to generate shaft seal water flow information.
[0018] The data processing module is electrically connected to the flow meter and the third wireless communication module, and the data processing module is used to receive the shaft seal water flow information;
[0019] The power supply module is electrically connected to the flow meter, the data processing module and the third wireless communication module, and the power supply module is used to supply power to the flow meter, the data processing module and the third wireless communication module.
[0020] Preferably, the industrial control server includes an industrial computer and a fourth wireless communication module;
[0021] The fourth wireless communication module is communicatively connected to the second wireless communication module and the third wireless communication module to obtain the shaft seal water flow information and the filter element pressure difference information.
[0022] The industrial control computer is connected to the first wireless communication module to send the shaft seal water flow information and the filter element pressure difference information to the host computer through the first wireless communication module.
[0023] Preferably, the first wireless communication module is a WiFi communication module; and / or the second wireless communication module, the third wireless communication module, and the fourth wireless communication module are all Bluetooth communication modules.
[0024] Preferably, the nuclear power plant circulating water pump shaft seal leakage monitoring device further includes a detachable connector;
[0025] The detachable connector is used for mechanical connection between the first valve port of the three-way valve and the shaft seal water drain pipe.
[0026] Preferably, the detachable connector is a Straub connector.
[0027] This utility model constructs a flow monitoring device, including a host computer and the above-mentioned nuclear power plant circulating water pump shaft seal leakage monitoring device;
[0028] The host computer is connected to the nuclear power plant circulating water pump shaft seal leakage monitoring device and is used to display shaft seal water flow information.
[0029] The present invention has the following beneficial effects: it provides a device for monitoring the leakage of shaft seals of circulating water pumps in nuclear power plants, which can monitor the flow rate of shaft seal water in real time, enabling staff to determine whether there is any abnormality in the leakage of shaft seals based on the flow rate of shaft seal water, and then conduct early investigation and elimination of defects, which is conducive to improving equipment reliability and avoiding economic losses caused by unplanned shutdowns for maintenance. Attached Figure Description
[0030] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings:
[0031] Figure 1 This is a structural block diagram of a nuclear power plant circulating water pump shaft seal leakage monitoring device according to one embodiment of the present invention;
[0032] Figure 2 This is a schematic diagram of the structure of a nuclear power plant circulating water pump shaft seal leakage monitoring device in one embodiment of the present invention;
[0033] Figure 3 This is a circuit structure block diagram of the flow measurement module in one embodiment of the present invention. Detailed Implementation
[0034] To provide a clearer understanding of the technical features, objectives, and effects of this utility model, the specific embodiments of this utility model will now be described in detail with reference to the accompanying drawings.
[0035] In the following description, it should be understood that the orientations or positional relationships indicated by terms such as "front," "rear," "up," "down," "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.
[0036] Figure 1 This is a structural block diagram of a nuclear power plant circulating water pump shaft seal leakage monitoring device in one embodiment of the present invention. The nuclear power plant circulating water pump shaft seal leakage monitoring device can monitor the shaft seal water flow rate of the circulating water pump in real time, enabling staff to determine whether the shaft seal leakage is abnormal based on the shaft seal water flow rate, and then conduct early investigation and elimination of defects, which is conducive to improving equipment reliability and avoiding economic losses caused by unplanned shutdowns for maintenance.
[0037] Please see Figure 1 The nuclear power plant circulating water pump shaft seal leakage monitoring device may include a three-way valve 1, a flow measurement module 3, an industrial control server 5, and a first wireless communication module 6.
[0038] The first port of the three-way valve 1 is mechanically connected to the shaft seal water drain pipe 10 via a pipeline. The second port of the three-way valve 1 is mechanically connected to the shaft seal water treatment equipment via a pipeline. The third port of the three-way valve 1 is mechanically connected to the inlet of the flow measurement module 3 via a pipeline, so as to guide the shaft seal water to the shaft seal water treatment equipment or to the flow measurement module 3. Specifically, the three-way valve 1 can be an existing three-way ball valve. When flow monitoring is required, the operator can operate the three-way valve 1 to connect its first and third ports, thereby guiding the shaft seal water to the flow measurement module 3. When flow monitoring is not required or when maintenance of the flow measurement module 3 is required, the operator can operate the three-way valve 1 to connect its first and second ports, thereby guiding the shaft seal water directly to the shaft seal water treatment equipment and preventing the shaft seal water from guiding to the flow measurement module 3, thus facilitating maintenance work. It should be noted that the shaft seal water treatment equipment is an existing device used in nuclear power plants to treat shaft seal water, usually a circulating water pump shaft seal water return pipe or a pit.
[0039] The outlet of the flow measurement module 3 is used to mechanically connect to the shaft seal water treatment equipment through a pipeline and measure the flow rate of the shaft seal water to generate shaft seal water flow information that can characterize the magnitude of the shaft seal water flow.
[0040] The industrial control server 5 is communicatively connected to the flow measurement module 3 and the first wireless communication module 6. The industrial control server 5 is used to receive shaft seal water flow information and send the shaft seal water flow information to the first wireless communication module 6.
[0041] The first wireless communication module 6 is connected to the industrial control server 5. The first wireless communication module 6 is used to send the shaft seal water flow information to the host computer, so that the staff can observe the shaft seal water flow information in real time through the host computer, and then determine whether the shaft seal leakage is abnormal in a timely or advance manner based on the shaft seal water flow.
[0042] In some embodiments, such as Figure 1 As shown, the nuclear power plant circulating water pump shaft seal leakage monitoring device may also include a filter element 2 and a pressure measurement module 4.
[0043] like Figure 2 As shown, filter element 2 is mechanically connected via a pipe between the third valve port of three-way valve 1 and the inlet of flow measurement module 3 to filter the shaft seal water introduced into flow measurement module 3. Specifically, filter element 2 can be an existing Y-type filter with a filtration accuracy of 50 microns. Understandably, the filtration effect of the Y-type filter aims to minimize clogging of flow measurement module 3.
[0044] like Figure 2 As shown, the two ends of the pressure measurement module 4 are mechanically connected to the inlet and outlet of the filter element 2 via pipes. It measures the pressure difference between the inlet and outlet of the filter element 2 to generate filter element pressure difference information that characterizes the magnitude of the water pressure difference between the inlet and outlet of the filter element 2. The pressure measurement module 4 is also communicatively connected to the industrial control server 5 to transmit the filter element pressure difference information to the host computer via the industrial control server 5 and the first wireless communication module 6, allowing operators to observe the filter element pressure difference information through the host computer. Understandably, the greater the resistance of the filter element 2 to water, the greater the water pressure difference. Therefore, the real-time clogging status of the filter element 2 can be determined by observing the filter element pressure difference information. When a large water pressure difference is detected, operators can clean the impurities inside the filter element 2 on-site, thereby preventing clogging of the pressure measurement module 4 and inaccurate flow rate testing. The cleaning method is determined by the type of filter element 2. For example, when the filter element 2 is a... Figure 2 When using the Y-type filter shown, staff can clean it by opening the drain outlet.
[0045] Because the pipeline layout of some shaft seal water drainage pipes 10 is quite complex on-site, transmitting shaft seal water flow information and filter pressure difference information via electrical cables would be time-consuming and labor-intensive when laying the cables on-site. Therefore, in one embodiment, as follows... Figure 1As shown, the nuclear power plant circulating water pump shaft seal leakage monitoring device may further include a second wireless communication module 7 and a third wireless communication module 8. The second wireless communication module 7 is electrically connected to the pressure measurement module 4 and communicatively connected to the industrial control server 5 to transmit filter element differential pressure information to the industrial control server 5 via wireless communication. The third wireless communication module 8 is electrically connected to the flow measurement module 3 and communicatively connected to the industrial control server 5 to transmit shaft seal water flow information to the industrial control server 5 via wireless communication. Understandably, this embodiment can eliminate the wiring process. Moreover, as long as the second wireless communication module 7 is installed on the pressure measurement module 4 side, the third wireless communication module 8 is installed on the flow measurement module 3 side, and the industrial control server 5 is installed within the communication range of the second and third wireless communication modules 7 and 8, the transmission of filter element differential pressure information and shaft seal water flow information can be achieved, thus improving the installation flexibility of this device. Furthermore, the pressure measurement module 4 can be an existing pressure measuring instrument.
[0046] In one embodiment, such as Figure 3 As shown, the flow measurement module 3 may include a flow meter 31, a data processing module 32, and a power supply module 33. The flow meter 31 can be an existing Hall effect vortex flow meter.
[0047] The flow meter 31 is mechanically connected between the outlet end of the filter element 2 and the shaft seal water treatment equipment through a pipeline to measure the flow rate of the shaft seal water in the guide flow meter 31 and generate shaft seal water flow rate information that can characterize the size of the shaft seal water flow rate.
[0048] The data processing module 32 is electrically connected to the flow meter 31 and the third wireless communication module 8. The data processing module 32 is used to receive the shaft seal water flow information from the flow meter 31 and send the shaft seal water flow information to the industrial control server 5 through the third wireless communication module 8.
[0049] The power supply module 33 is electrically connected to the flow meter 31, the data processing module 32, and the third wireless communication module 8. The power supply module 33 provides power to the flow meter 31, the data processing module 32, and the third wireless communication module 8. Further, as... Figure 3 As shown, the power supply module 33 may include a battery management module 332 and two batteries 331. The two batteries 331 are connected in series and electrically connected to the battery management module 332. The battery management module 332 is electrically connected to the flow meter 31, the data processing module 32 and the third wireless communication module 8. The battery management module 332 is used to regulate the output voltage of the two series-connected batteries 331 to provide a stable power supply to the various modules connected to it.
[0050] In some embodiments, such as Figure 1As shown, the industrial control server 5 may include an industrial computer 51 and a fourth wireless communication module 52. The fourth wireless communication module 52 is communicatively connected to the second wireless communication module 7 and the third wireless communication module 8 to obtain shaft seal water flow information from the third wireless communication module 8 and filter element differential pressure information from the second wireless communication module 7. The industrial computer 51 is communicatively connected to the first wireless communication module 6 to send the shaft seal water flow information and filter element differential pressure information to a host computer via the first wireless communication module 6. Preferably, the first wireless communication module 6 can be a WiFi communication module, thus utilizing the existing WiFi network of the nuclear power plant for data transmission. Further, the second wireless communication module 7, the third wireless communication module 8, and the fourth wireless communication module 52 can all be Bluetooth communication modules.
[0051] Since this utility model pertains to an add-on device, to improve the installation flexibility of the device, in one embodiment, the nuclear power plant circulating water pump shaft seal leakage monitoring device may further include a detachable connector 9. The detachable connector 9 is used for mechanical connection via a pipe between the first valve port of the three-way valve 1 and the shaft seal water drain pipe 10. Preferably, the detachable connector 9 can be a Straub joint.
[0052] This invention also provides a flow monitoring device, which includes a host computer 20 and a nuclear power plant circulating water pump shaft seal leakage monitoring device provided in this embodiment. The host computer 20 is communicatively connected to the nuclear power plant circulating water pump shaft seal leakage monitoring device and is used to display shaft seal water flow information and filter differential pressure information. The host computer 20 may include a computer in the nuclear power plant monitoring room and a mobile terminal carried by staff.
[0053] 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 device for monitoring shaft seal leakage in a nuclear power plant circulating water pump, characterized in that, It includes a three-way valve (1), a flow measurement module (3), an industrial control server (5), and a first wireless communication module (6); The first valve port of the three-way valve (1) is used to mechanically connect the shaft seal water drain pipe (10), the second valve port of the three-way valve (1) is used to mechanically connect the shaft seal water treatment equipment, and the third valve port of the three-way valve (1) is mechanically connected to the inlet of the flow measurement module (3) to guide the shaft seal water to the shaft seal water treatment equipment or to the flow measurement module (3); The outlet of the flow measurement module (3) is used to mechanically connect to the shaft seal water treatment equipment and measure the flow rate of the shaft seal water to generate shaft seal water flow information; The industrial control server (5) is communicatively connected to the flow measurement module (3) and the first wireless communication module (6), and the industrial control server (5) is used to receive the shaft seal water flow information; The first wireless communication module (6) is communicatively connected to the industrial control server (5), and the first wireless communication module (6) is used to send the shaft seal water flow information to the host computer.
2. The nuclear power plant circulating water pump shaft seal leakage monitoring device according to claim 1, characterized in that, It also includes a filter element (2) and a pressure measurement module (4); The filter element (2) is mechanically connected between the third valve port of the three-way valve (1) and the inlet of the flow measurement module (3) to filter the shaft seal water introduced into the flow measurement module (3); The pressure measurement module (4) is mechanically connected to the inlet and outlet of the filter element (2) at both ends to measure the pressure difference between the inlet and outlet of the filter element (2) to generate filter element pressure difference information; the pressure measurement module (4) is also connected to the industrial control server (5) to send the filter element pressure difference information to the host computer via the industrial control server (5) and the first wireless communication module (6).
3. The nuclear power plant circulating water pump shaft seal leakage monitoring device according to claim 2, characterized in that, The filter element (2) is a Y-type filter.
4. The nuclear power plant circulating water pump shaft seal leakage monitoring device according to claim 2, characterized in that, It also includes a second wireless communication module (7) and a third wireless communication module (8); The second wireless communication module (7) is electrically connected to the pressure measurement module (4), and the second wireless communication module (7) is communicatively connected to the industrial control server (5) to send the differential pressure information of the filter element to the industrial control server (5); The third wireless communication module (8) is electrically connected to the flow measurement module (3), and the second wireless communication module (7) is communicatively connected to the industrial control server (5) to send the shaft seal water flow information to the industrial control server (5).
5. The nuclear power plant circulating water pump shaft seal leakage monitoring device according to claim 4, characterized in that, The flow measurement module (3) includes a flow meter (31), a data processing module (32), and a power supply module (33); The flow meter (31) is mechanically connected between the outlet end of the filter element (2) and the shaft seal water treatment equipment. The flow meter (31) is used to measure the flow rate of the shaft seal water to generate the shaft seal water flow rate information. The data processing module (32) is electrically connected to the flow meter (31) and the third wireless communication module (8), and the data processing module (32) is used to receive the shaft seal water flow information; The power supply module (33) is electrically connected to the flow meter (31), the data processing module (32) and the third wireless communication module (8), and the power supply module (33) is used to supply power to the flow meter (31), the data processing module (32) and the third wireless communication module (8).
6. The nuclear power plant circulating water pump shaft seal leakage monitoring device according to claim 5, characterized in that, The industrial control server (5) includes an industrial control computer (51) and a fourth wireless communication module (52); The fourth wireless communication module (52) is communicatively connected to the second wireless communication module (7) and the third wireless communication module (8) to obtain the shaft seal water flow information and the filter element pressure difference information; The industrial control computer (51) is connected to the first wireless communication module (6) to send the shaft seal water flow information and the filter element pressure difference information to the host computer through the first wireless communication module (6).
7. The nuclear power plant circulating water pump shaft seal leakage monitoring device according to claim 6, characterized in that, The first wireless communication module (6) is a WiFi communication module; and / or the second wireless communication module (7), the third wireless communication module (8) and the fourth wireless communication module (52) are Bluetooth communication modules respectively.
8. The nuclear power plant circulating water pump shaft seal leakage monitoring device according to any one of claims 1 to 7, characterized in that, It also includes a detachable connector (9); The detachable connector (9) is used for mechanical connection between the first valve port of the three-way valve (1) and the shaft seal water drain pipe (10).
9. The nuclear power plant circulating water pump shaft seal leakage monitoring device according to claim 8, characterized in that, The detachable connector (9) is a Straub connector.
10. A flow monitoring device, characterized in that, Includes a host computer (20) and a nuclear power plant circulating water pump shaft seal leakage monitoring device as described in any one of claims 1 to 9; The host computer (20) is connected to the nuclear power plant circulating water pump shaft seal leakage monitoring device and is used to display shaft seal water flow information.