Device and method for measuring performance of dynamic pressure sealing interstage coil pipe of main pump of nuclear power plant

Abstract

The invention discloses a nuclear power plant main pump dynamic pressure sealing interstage coil performance measurement device and method, and the device comprises a water supply module, a pressure adjustment module, a flow resistance measurement module, a to-be-measured coil and a flow measurement module, and the water supply module, the pressure adjustment module, the to-be-measured coil and the flow measurement module are sequentially connected through a through-flow pipeline to form a communication line. The to-be-measured coil pipe is detachably connected with the pressure adjusting module and the flow measuring module, and the flow resistance measuring module is connected with an inlet and an outlet of the to-be-measured coil pipe so as to measure the pressure difference between the inlet and the outlet of the to-be-measured coil pipe. The flow detection module measures the water delivery volume of the to-be-measured coil pipe in the preset time and is used for calculating the flow of the to-be-measured coil pipe in combination with the preset time. The device can be used for providing the operation environment of the to-be-measured coil pipe, simulating the actual operation condition, measuring the pressure difference between the inlet and the outlet of the to-be-measured coil pipe and the water delivery volume within the preset time, calculating the flow of the to-be-measured coil pipe, and providing a basis for evaluating the related performance of the to-be-measured coil pipe.

Description

Technical Field

[0001] This invention relates to the field of nuclear-grade equipment maintenance technology, and in particular to a device and method for measuring the performance of the interstage coil of the dynamic pressure sealing stage of a nuclear power plant main pump. Background Technology

[0002] The main pump of my country's third-generation nuclear power technology uses a cutting-edge dynamic pressure seal, which can evenly withstand the 15.5 MPa pressure of the primary circuit and distribute it across the three-stage seal. The key to achieving this is the interstage coil of the seal, a multi-turn annular thin tube approximately 3 meters long and 2 meters in diameter. Each coil generates a pressure drop of approximately 5.2 MPa, thus evenly distributing the high pressure of the primary circuit medium. Simultaneously, under this pressure drop, the flow rate is designed to be around 600 L / h to meet system requirements and dissipate the frictional heat from the seal.

[0003] During commercial operation of a nuclear power plant, the operating parameters of the entire hydrodynamic seal system may deteriorate over long-term operation, including abnormal pressure and flow rates. If the seal parameters exceed standards, the sealing of the primary loop radioactive medium cannot be guaranteed, leading to main pump shutdown, reactor shutdown, significant economic losses, and compromises to nuclear safety. Coil performance deterioration, including blockage, deformation, and scaling, is one of the main causes of hydrodynamic seal parameter deterioration, necessitating an inspection of the coil's performance parameters. However, domestic hydrodynamic seals are primarily sourced from Austria and France, lacking key design processes, making accurate performance assessment of the seal difficult. Summary of the Invention

[0004] The technical problem to be solved by the present invention is to provide a device and method for measuring the performance of the interstage coil of the dynamic pressure sealing stage of the main pump in a nuclear power plant.

[0005] The technical solution adopted by this invention to solve its technical problem is: a performance measurement device for the interstage coil of the dynamic pressure sealing stage of a nuclear power plant main pump, comprising a water supply module, a pressure regulating module, a flow resistance measurement module, a coil to be tested, and a flow measurement module. The water supply module, the pressure regulating module, the coil to be tested, and the flow measurement module are sequentially connected through a flow pipe to form a connected circuit. The coil to be tested is detachably connected to the pressure regulating module and the flow measurement module, respectively, and the flow resistance measurement module is connected to the inlet and outlet of the coil to be tested to measure the pressure difference between the inlet and outlet of the coil to be tested. The flow detection module measures the water volume delivered by the coil to be tested within a preset time, and calculates the flow rate of the coil to be tested in combination with the preset time.

[0006] In some embodiments, the flow measurement module includes a measuring tank and at least one liquid level monitoring device, the liquid level monitoring device being correspondingly configured with the measuring tank to measure the liquid level height inside the measuring tank.

[0007] In some embodiments, the flow resistance measurement module includes a differential pressure indicator, at least one inlet pressure gauge, and at least one flow meter. The differential pressure indicator is connected to the inlet and outlet of the coil under test, respectively, to measure the pressure difference between the inlet and outlet of the coil under test. The inlet pressure gauge is connected to the flow passage of the inlet of the coil under test to measure the inlet pressure of the coil under test. The flow meter is connected to the inlet of the coil under test to measure the inlet flow rate of the coil under test.

[0008] In some embodiments, the pressure regulating module includes a water pump, an outlet pressure gauge, and at least one first regulating valve. The water pump is connected between the water supply module and the coil to be tested. The outlet pressure gauge is connected to the outlet of the water pump. The first regulating valve is connected in parallel with the water pump and the outlet pressure gauge.

[0009] In some embodiments, the water supply module includes a water storage tank, a heating element, and a temperature monitoring element. The outlet of the water storage tank is connected to the pressure regulating module. The heating element is disposed inside the water storage tank for heating the fluid. The temperature monitoring element is installed on the water storage tank and comes into contact with the fluid inside the water storage tank to measure the fluid temperature.

[0010] In some embodiments, a protection module is also included, which is connected in series between the coil under test and the water supply module via a flow pipe;

[0011] The protection module includes at least one of a filter, a voltage regulator, and a second regulating valve.

[0012] In some embodiments, the system further includes a return water pipeline and a return water pump, wherein the return water pump is disposed on the return water pipeline to form a return water line, and the return water line is connected to the flow measurement module and the water supply module respectively, so as to return the fluid collected by the flow measurement module to the water supply module;

[0013] The return water pipeline and the connecting line form a circulation pipeline.

[0014] In some embodiments, a central control system is also included. The central control system is electrically connected to the flow resistance measurement module and the flow rate measurement module to obtain the pressure difference between the inlet and outlet of the coil under test and the water volume delivered by the coil under test within a preset time. The flow rate of the coil under test is calculated according to the calculation logic set by the central control system: flow rate = water volume / preset time.

[0015] The present invention also constructs a method for measuring the performance of the interstage coil of the dynamic pressure sealing stage of the main pump in a nuclear power plant, comprising: creating an operating environment for the coil under test, wherein the operating environment includes at least the pressure of supplying fluid to the coil under test and regulating the pressure of the fluid; detecting and comparing the inlet pressure and outlet pressure of the coil under test during operation, or directly measuring the differential pressure between the inlet and outlet of the coil under test; measuring the volume of the coil under test within a preset time period, and calculating the flow rate of the coil under test.

[0016] In some embodiments, a performance measurement device for the interstage coil of the dynamic pressure sealing stage of a nuclear power plant main pump is used. This device includes a water supply module, a pressure regulating module, a flow resistance measurement module, a coil under test, and a flow measurement module. The water supply module, the pressure regulating module, the coil under test, and the flow measurement module are sequentially connected via a flow pipe to form a continuous circuit. The coil under test is detachably connected to both the pressure regulating module and the flow measurement module, and the flow resistance measurement module is connected to both the inlet and outlet of the coil under test. The flow detection module measures the water volume delivered by the coil under test within a preset time.

[0017] The water supply module is activated to provide fluid to the coil under test. The pressure of the fluid is adjusted by the pressure regulating module. The pressure difference between the inlet and outlet of the coil under test is measured by the flow resistance measuring module. The water volume delivered by the coil under test within a preset time is measured by the flow detection module. The flow rate of the coil under test is calculated according to the calculation logic: flow rate = water volume / preset time.

[0018] By implementing this invention, the following beneficial effects are achieved:

[0019] The performance measurement device for the interstage coil of the main pump dynamic pressure seal in a nuclear power plant of the present invention provides the operating environment of the coil under test through a water supply module and a pressure regulation module, simulating the actual operation of the coil in the dynamic pressure seal of the main pump in a nuclear power plant. The device measures the pressure difference between the inlet and outlet of the coil under test through a flow resistance measurement module, measures the water delivery volume within a preset time through a flow measurement module, and calculates the flow rate of the coil under test, providing a basis for evaluating the relevant performance of the coil under test.

[0020] The method for measuring the performance of the interstage coil of the main pump in a nuclear power plant, as described in this invention, creates an operating environment for the coil under test, simulates actual operating conditions, measures the pressure difference between the inlet and outlet of the coil under test, the water volume delivered within a preset time, and calculates the flow rate of the coil under test, thus providing a basis for evaluating the relevant performance of the coil under test. Attached Figure Description

[0021] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings:

[0022] Figure 1 This is a schematic diagram of the structure of a nuclear power plant main pump dynamic pressure sealing stage intercoil performance measurement device according to an embodiment of the present invention. Detailed Implementation

[0023] To provide a clearer understanding of the technical features, objectives, and effects of the present invention, specific embodiments of the present invention will now be described in detail with reference to the accompanying drawings.

[0024] In the description of the invention, it should be understood that the terms "center," "longitudinal," "lateral," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," and "outer," etc., indicating orientation or positional relationships based on the orientation or positional relationships shown in the accompanying drawings, are only for the convenience of describing the invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation of the invention. Furthermore, the terms "first," "second," etc., are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of indicated technical features. Thus, a feature defined with "first," "second," etc., may explicitly or implicitly include one or more of that feature. In the description of the invention, unless otherwise stated, "a plurality of" means two or more.

[0025] In the description of this invention, it should be noted that, unless otherwise explicitly specified and limited, the terms "installation," "connection," and "linking" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral connection; they can refer to a mechanical connection or a chemical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; and they can refer to the internal communication between two components. Those skilled in the art will understand the specific meaning of the above terms in this invention based on the specific circumstances.

[0026] Example 1:

[0027] See Figure 1Embodiment 1 of the present invention discloses a performance measurement device for the interstage coil of the dynamic pressure sealing stage of a main pump in a nuclear power plant, comprising a water supply module 1, a pressure regulating module 2, a flow resistance measurement module 3, a coil under test 4, and a flow measurement module 5. The water supply module 1, pressure regulating module 2, coil under test 4, and flow measurement module 5 are sequentially connected through a flow passage 6 to form a continuous circuit. The coil under test 4 is detachably connected to the pressure regulating module 2 and the flow measurement module 5, respectively, and the flow resistance measurement module 3 is connected to the inlet and outlet of the coil under test 4 to measure the pressure difference between the inlet and outlet of the coil under test 4. The flow detection module measures the water volume delivered by the coil under test 4 within a preset time, and uses this measurement to calculate the flow rate of the coil under test 4 in conjunction with the preset time. The calculation of the flow rate or other performance parameters of the coil under test 4 can be performed manually or by setting a program in computer software, as needed.

[0028] By adjusting the fluid pressure using pressure regulation module 2 and monitoring the flow rate at various pressures, a verification method for the pressure drop and flow rate of the tested coil 4 can be found to ensure that the coil performance meets the operational requirements of the nuclear power plant. Furthermore, through a sufficient number of tests using the nuclear power plant main pump dynamic pressure seal interstage coil performance measurement device of this invention, when the coil performance deteriorates, sufficient parameters are available for nuclear power plant engineers to identify the cause of parameter changes and to assess the overall performance of the coil seal.

[0029] In some embodiments, the water supply module 1 supplies fluid to the entire system. The water supply module 1 includes a water storage tank 11, a heating element, and a temperature monitoring element 12. The outlet of the water storage tank 11 is connected to the pressure regulating module 2. The heating element is located inside the water storage tank 11 to heat the fluid. The temperature monitoring element is installed on the water storage tank 11 and contacts the fluid inside to measure its temperature. By adjusting the fluid temperature, viscosity, density, etc., within the water storage tank 11, the actual operating conditions of a nuclear power plant can be simulated. The viscosity and density can be changed by adding relevant substances through a feeding port on the water storage tank 11. The heating element can be a resistance rod or a heating base integrated with the water storage tank 11, similar to a heating barrel in the prior art. The heating element is shielded by the water storage tank 11 and is not shown in the figure.

[0030] In some embodiments, the pressure regulating module 2 adjusts the inlet pressure of the coil under test 4 to simulate the working pressure of the coils under different pressure conditions in the main loop of a nuclear power plant. The pressure regulating module 2 includes a water pump 21, an outlet pressure gauge 22, and at least one first regulating valve 23. The water pump 21 is connected between the water supply module 1 and the coil under test 4. The outlet pressure gauge 22 is connected to the outlet of the water pump 21. The first regulating valve 23 is connected in parallel with the water pump 21 and the outlet pressure gauge 22. The water pump 21 is used to supply water to the coil under test 4; the water pump 21 can be a plunger pump. The outlet pressure gauge 22 monitors the output pressure of the water pump 21. By observing the displayed value of the outlet pressure gauge 22 and adjusting the first regulating valve 23, accurate pressure control is achieved.

[0031] In some embodiments, the flow resistance measurement module 3 can calculate the pressure difference between the inlet and outlet of the coil 4 under test, obtain the pressure drop and flow resistance of the coil 4 under test, and calculate fluid dynamic parameters such as flow coefficient and kinematic viscosity. The flow resistance measurement module 3 includes a differential pressure indicator 31, at least one inlet pressure gauge 32, and at least one flow meter 33. The differential pressure indicator 31 is connected to the inlet and outlet of the coil 4 under test, respectively, to measure the pressure difference between the inlet and outlet of the coil 4 under test; the inlet pressure gauge 32 is connected to the flow passage 6 at the inlet of the coil 4 under test to measure the inlet pressure of the coil 4 under test; and the flow meter 33 is connected to the inlet of the coil 4 under test to measure the inlet flow rate of the coil 4 under test. The differential pressure indicator 31 is used to indicate the pressure difference between the inlet and outlet of the coil 4 under test. If the pressure difference is small or there is no pressure difference, it can be considered a qualified product. If the pressure difference is large, it is considered a substandard product, which can be cleaned, retested, and then judged. The inlet pressure gauge 32 monitors the inlet pressure of the coil under test 4 and can be compared with the outlet pressure gauge 22 to prevent other factors from affecting the pressure difference between the inlet and outlet of the coil under test 4. The inlet flow rate, the pressure difference between the inlet and outlet of the coil under test 4, and the inlet pressure of the coil under test 4 monitored by the flow meter 33 can be used to reflect the pressure change of the fluid before and after passing through the coil under test 4, thereby calculating parameters such as pressure drop and flow resistance of the coil under test 4.

[0032] In some embodiments, the flow measurement module 5 is used to measure the water delivery volume of the coil 4 under test within a preset time, with an accuracy of 0.1 mm change, to calculate the flow rate of the coil 4 under test. The flow measurement module 5 includes a measuring tank 51 and at least one liquid level monitoring element 52. The liquid level monitoring element 52 is correspondingly set with the measuring tank 51 to measure the liquid level height inside the measuring tank 51. The measuring tank 51 is a barrel-shaped structure with the same cross-sectional area. The water delivery volume can be calculated by dividing the height of the liquid level change detected by the liquid level monitoring element by the cross-sectional area. The flow rate of the coil 4 under test during the preset operating time can be calculated by dividing the water delivery volume by the preset time. The liquid level monitoring element 52 can be a liquid level indicator transmitter for real-time monitoring and transmission of liquid level data in the measuring tank 51. The liquid level monitoring element 52 can also be a window level gauge, where the liquid level change can be obtained by direct manual reading. Understandably, a liquid level indicator transmitter and a window level gauge can be set simultaneously to improve monitoring accuracy.

[0033] In some embodiments, the performance measurement device for the interstage coil of the main pump dynamic pressure sealing stage in a nuclear power plant further includes a protection module 7, which is connected in series between the coil under test 4 and the water supply module 1 via a flow passage 6. For example, the protection module 7 is connected in series between the flow resistance measurement module 3 and the pressure regulating module 2. The protection module 7 includes at least one of a filter element 71, a pressure stabilizer 72, and a second regulating valve 73. The pressure stabilizer 72 is used to maintain the short-term pressure of the connected line to prevent equipment malfunction. The pressure stabilizer 72 can be an energy storage device, which can prevent damage to the coil under test 4 and instruments caused by plunger pump pressure fluctuations. The filter element 71 is used to filter impurities and can be a filter, simulating the shaft seal water filter screen of the main pump in a nuclear power plant. The second regulating valve 73 is used for secondary pressure regulation and pressure compensation. For example, an energy storage device, a filter, and a second regulating valve 73 are connected in series between the pressure regulating module 2 and the flow resistance measurement module 3.

[0034] In some embodiments, the performance measurement device for the interstage coil of the main pump dynamic pressure seal in a nuclear power plant further includes a return water pipeline 8 and a return water pump 9. The return water pump 9 is installed on the return water pipeline 8 to form a return water line. The return water line is connected to the flow measurement module 5 and the water supply module 1, respectively, to return the fluid collected by the flow measurement module 5 to the water supply module 1. The return water line and the connecting line form a circulation pipeline. Fluid circulation can be performed, saving resources. Generally, the return water pump 9 is started again to recover the fluid after the test is completed.

[0035] In some embodiments, the performance measurement device for the interstage coil of the main pump in a nuclear power plant also includes a central control system. By inputting relevant parameters, it can be started with a single button and the relevant parameters can be calculated. The central control system is electrically connected to the flow resistance measurement module 3 and the flow rate measurement module 5 to obtain the pressure difference between the inlet and outlet of the coil 4 under test and the water volume delivered by the coil 4 within a preset time. Based on the calculation logic set by the central control system: flow rate = water volume / preset time, the flow rate of the coil 4 under test is calculated. Among them, the inlet pressure gauge 32, flow meter 33, outlet pressure gauge 22, differential pressure indicator 31, liquid level monitoring device 52, and temperature monitoring device 12 can all be electrically connected to the central control system to send relevant data, such as the inlet pressure of the coil under test 4, the flow rate of the flow meter 33, the outlet pressure of the water pump 21, the differential pressure between the inlet and outlet of the coil under test 4, the liquid level, and the temperature. According to the calculation logic set by the central control system, the flow rate, pressure drop, fluid kinematic viscosity, flow coefficient, Reynolds number, etc. of the coil under test 4 can be automatically calculated. The specific calculation logic is existing technology and will not be described in detail here. The central control system is not shown in the figure.

[0036] Example 2:

[0037] This invention also constructs a method for measuring the performance of the interstage coil of the dynamic pressure sealing stage of a main pump in a nuclear power plant, comprising: creating an operating environment for the coil under test 4, wherein the operating environment includes at least the pressure of supplying fluid to the coil under test 4 and regulating the fluid pressure; detecting and comparing the inlet and outlet pressures of the coil under test 4 during operation, or directly measuring the differential pressure between the inlet and outlet of the coil under test 4; measuring the volume of the coil under test 4 within a preset time period and calculating the flow rate of the coil under test 4.

[0038] By monitoring the flow rate under various pressures, a method for verifying the pressure drop and flow rate of the tested coil 4 can be found to ensure that the coil performance meets the operational requirements of the nuclear power plant. Furthermore, through a sufficient number of tests using the nuclear power plant main pump dynamic pressure seal interstage coil performance measurement device of this invention, when the coil performance deteriorates, sufficient parameters are available for nuclear power plant engineers to identify the cause of parameter changes and to assess the overall performance of the coil seal.

[0039] like Figure 1As shown, in some embodiments, a performance measurement device for the interstage coil of the main pump dynamic pressure sealing stage in a nuclear power plant is used. This device includes a water supply module 1, a pressure regulating module 2, a flow resistance measurement module 3, a coil under test 4, and a flow measurement module 5. The water supply module 1, pressure regulating module 2, coil under test 4, and flow measurement module 5 are sequentially connected via a flow passage pipe 6 to form a continuous circuit. The coil under test 4 is detachably connected to both the pressure regulating module 2 and the flow measurement module 5, and the flow resistance measurement module 3 is connected to both the inlet and outlet of the coil under test 4. The flow detection module measures the water volume delivered by the coil under test 4 within a preset time.

[0040] The water supply module 1 is activated to provide fluid to the coil under test 4. The pressure of the fluid is adjusted by the pressure regulating module 2. The pressure difference between the inlet and outlet of the coil under test 4 is measured by the flow resistance measuring module 3. The water volume delivered by the coil under test 4 within a preset time is measured by the flow detection module. Based on the calculation logic, the flow rate of the coil under test 4 is calculated as: Flow rate = Water volume / Preset time.

[0041] The other structures and methods of the device for measuring the performance of the interstage coil of the main pump dynamic pressure sealing stage in nuclear power plants are the same as in Example 1, and will not be repeated here.

[0042] By implementing this invention, the following beneficial effects are achieved:

[0043] The performance measurement device for the interstage coil of the main pump dynamic pressure seal in a nuclear power plant of the present invention provides the operating environment of the coil under test 4 through the water supply module 1 and the pressure regulation module 2, simulating the actual operation of the coil in the dynamic pressure seal of the main pump in a nuclear power plant. The pressure difference between the inlet and outlet of the coil under test is measured by the flow resistance measurement module 3, and the water delivery volume within a preset time is measured by the flow measurement module 5. The flow rate of the coil under test 4 is calculated, providing a basis for evaluating the relevant performance of the coil under test 4.

[0044] The method for measuring the performance of the interstage coil of the main pump in a nuclear power plant, as described in this invention, creates an operating environment for the coil under test 4, simulates actual operating conditions, measures the pressure difference between the inlet and outlet of the coil under test 4, the water volume delivered within a preset time, and calculates the flow rate of the coil under test 4, thus providing a basis for evaluating the relevant performance of the coil under test 4.

[0045] It is understood that the above embodiments only illustrate preferred embodiments of the present invention, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present invention. It should be noted that for those skilled in the art, the above embodiments or technical features can be freely combined, and several modifications and improvements can be made without departing from the concept of the present invention. These all fall within the protection scope of the present invention. That is, the embodiments described "in some embodiments" can be freely combined with any of the embodiments above and below. Therefore, all equivalent transformations and modifications made within the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. A device for measuring the performance of the interstage coil of the dynamic pressure sealing stage of a main pump in a nuclear power plant, characterized in that, The system includes a water supply module (1), a pressure regulating module (2), a flow resistance measurement module (3), a test coil (4), and a flow measurement module (5). The water supply module (1), the pressure regulating module (2), the test coil (4), and the flow measurement module (5) are connected in sequence through a flow pipe (6) to form a continuous circuit. The test coil (4) is detachably connected to the pressure regulating module (2) and the flow measurement module (5), and the flow resistance measurement module (3) is connected to the inlet and outlet of the test coil (4) to measure the pressure difference between the inlet and outlet of the test coil (4). The flow detection module measures the water volume delivered by the coil (4) under test within a preset time, and calculates the flow rate of the coil (4) under test in combination with the preset time.

2. The performance measurement device for the interstage coil of the main pump dynamic pressure sealing stage in a nuclear power plant according to claim 1, characterized in that, The flow measurement module (5) includes a measuring tank (51) and at least one liquid level monitoring device (52), which is correspondingly set with the measuring tank (51) to measure the liquid level height in the measuring tank (51).

3. The performance measurement device for the interstage coil of the dynamic pressure sealing stage of the main pump in a nuclear power plant according to claim 1, characterized in that, The flow resistance measurement module (3) includes a differential pressure indicator (31), at least one inlet pressure gauge (32) and at least one flow meter (33). The differential pressure indicator (31) is connected to the inlet and outlet of the coil under test (4) to measure the pressure difference between the inlet and outlet of the coil under test (4). The inlet pressure gauge (32) is connected to the flow passage (6) at the inlet of the coil under test (4) to measure the inlet pressure of the coil under test (4). The flow meter (33) is connected to the inlet of the coil under test (4) to measure the inlet flow rate of the coil under test (4).

4. The performance measurement device for the interstage coil of the dynamic pressure sealing stage of the main pump in a nuclear power plant according to claim 1, characterized in that, The pressure regulating module (2) includes a water pump (21), an outlet pressure gauge (22), and at least one first regulating valve (23). The water pump (21) is connected between the water supply module (1) and the coil to be tested (4). The outlet pressure gauge (22) is connected to the outlet of the water pump (21). The first regulating valve (23) is connected in parallel with the water pump (21) and the outlet pressure gauge (22).

5. The performance measurement device for the interstage coil of the dynamic pressure sealing stage of the main pump in a nuclear power plant according to claim 1, characterized in that, The water supply module (1) includes a water storage tank (11), a heating element and a temperature monitoring element (12). The outlet of the water storage tank (11) is connected to the pressure regulating module (2). The heating element is located inside the water storage tank (11) to heat the fluid. The temperature monitoring element is installed on the water storage tank (11) and comes into contact with the fluid inside the water storage tank (11) to measure the fluid temperature.

6. The performance measurement device for the interstage coil of the dynamic pressure sealing stage of the main pump in a nuclear power plant according to any one of claims 1-5, characterized in that, It also includes a protection module (7), which is connected in series between the coil to be tested (4) and the water supply module (1) through a flow pipe (6); The protection module (7) includes at least one of the following: a filter (71), a voltage regulator (72), and a second regulating valve (73).

7. The performance measurement device for the interstage coil of the dynamic pressure sealing stage of the main pump in a nuclear power plant according to any one of claims 1-5, characterized in that, It also includes a return water pipeline (8) and a return water pump (9). The return water pump (9) is installed on the return water pipeline (8) to form a return water line. The return water line is connected to the flow measurement module (5) and the water supply module (1) respectively, so as to return the fluid collected by the flow measurement module (5) to the water supply module (1). The return water pipeline and the connecting line form a circulation pipeline.

8. The performance measurement device for the interstage coil of the dynamic pressure sealing stage of the main pump in a nuclear power plant according to any one of claims 1-5, characterized in that, It also includes a central control system, which is electrically connected to the flow resistance measurement module (3) and the flow measurement module (5) to obtain the pressure difference between the inlet and outlet of the coil to be tested (4) and the water volume of the coil to be tested (4) within a preset time. The flow rate of the coil to be tested (4) is calculated according to the calculation logic set by the central control system: flow rate = water volume / preset time.

9. A method for measuring the performance of the interstage coil of the dynamic pressure sealing stage of a main pump in a nuclear power plant, characterized in that, include: Create an operating environment for the coil (4) under test, wherein the operating environment includes at least supplying fluid to the coil (4) under test and adjusting the pressure of the fluid; detecting and comparing the inlet pressure and outlet pressure of the coil (4) under test during operation, or directly measuring the differential pressure between the inlet and outlet of the coil (4) under test; measuring the volume of the coil (4) under test within a preset time period, and calculating the flow rate of the coil (4) under test.

10. The method for measuring the performance of the interstage coil of the dynamic pressure sealing stage of a nuclear power plant main pump according to claim 9, characterized in that, The device for measuring the performance of the interstage coil of the main pump in a nuclear power plant includes a water supply module (1), a pressure regulating module (2), a flow resistance measuring module (3), a coil to be tested (4), and a flow measurement module (5). The water supply module (1), the pressure regulating module (2), the coil to be tested (4), and the flow measurement module (5) are connected in sequence through a flow pipe (6) to form a continuous circuit. The coil to be tested (4) is detachably connected to the pressure regulating module (2) and the flow measurement module (5), and the flow resistance measuring module (3) is connected to the inlet and outlet of the coil to be tested (4), respectively. The flow detection module measures the water delivery volume of the coil to be tested (4) within a preset time. The water supply module (1) is activated to provide fluid to the coil (4) under test. The pressure of the fluid is adjusted by the pressure regulating module (2). The pressure difference between the inlet and outlet of the coil (4) under test is measured by the flow resistance measuring module (3). The water volume delivered by the coil (4) under test within a preset time is measured by the flow detection module. The flow rate of the coil (4) under test is calculated according to the calculation logic: flow rate = water volume / preset time.

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