Reactor primary pump seal performance experiment system
By constructing a test system for the performance of the main pump shaft seal, the problem of testing the performance of the main pump shaft seal was solved. The test system was used to detect the shaft seal under high temperature and high pressure, ensuring the safety and reliability of the shaft seal and providing experimental data support for the development of new shaft seals.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- CHINA NUCLEAR POWER TECH RES INST CO LTD
- Filing Date
- 2026-05-11
- Publication Date
- 2026-07-24
AI Technical Summary
Existing technologies cannot effectively conduct performance tests on the reactor main pump shaft seal, which could lead to shaft seal failure and potentially result in the loss of the pressure boundary integrity of the primary loop in a nuclear power plant, posing a risk of small-break loss-of-water accidents.
A test system for the performance of the main pump shaft seal of a reactor was constructed, including a simulator, thermal shock test pipeline, durability test pipeline, water replenishment and pressurization pipeline, and leakage measurement pipeline. The system simulates the performance and durability of the shaft seal under high temperature and high pressure conditions, and conducts experimental tests through the thermal shock test pipeline and the durability test pipeline respectively.
It provides experimental data on thermal shock start-up, thermal shock testing, and durability testing of shaft seals for different types of main pumps, ensuring the safety and reliability of the shaft seals and providing experimental support for the research and development of new shaft seals.
Smart Images

Figure CN122447296A_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of nuclear power technology, and more specifically, to a test system for the shaft seal performance of a reactor main pump. Background Technology
[0002] The reactor coolant pump (main pump) is the only large rotating piece of equipment in the primary loop system of a pressurized water reactor nuclear power plant. It plays a crucial role in driving the circulation of coolant within the primary loop and preventing the leakage of radioactive materials. The shaft seal is a critical component of the main pump and represents the safety boundary of the reactor primary loop. Failure of the main pump's shaft seal will result in the loss of the pressure boundary integrity of the nuclear power plant's primary loop. If the leakage rate exceeds the capacity of the makeup water system, it can lead to a potential small-break loss-of-coolant accident, ultimately resulting in core exposure and meltdown, impacting the normal operation and safety of the nuclear power plant.
[0003] For the development of shaft seals for main pumps, performance tests are required to provide experimental data to support the selection of materials and structures for shaft seal development, and to ensure its safety and reliability after it is put into use. Summary of the Invention
[0004] The technical problem to be solved by the present invention is to provide a reactor main pump shaft seal performance test system in view of the above-mentioned defects of the prior art.
[0005] The technical solution adopted by this invention to solve its technical problem is: constructing a reactor main pump shaft seal performance test system, comprising: The simulation body has a first chamber and a second chamber located on opposite sides of the shaft seal simulation component; A thermal shock test pipeline includes an injection pipe and a heat source generator disposed at the inlet end of the injection pipe; the heat source generator defines a space for containing and heating a medium; a second chamber is connected to the outlet end of the injection pipe; The durability test pipeline includes a circulation pipeline and a preheater installed on the circulation pipeline; the second chamber is connected end to end to the circulation pipeline to form a circulation loop; A water replenishment and pressurization pipeline, wherein the outlet end of the water replenishment and pressurization pipeline is connected to the circulation pipeline; and The leakage measurement pipeline has at least one measurement branch, the inlet end of which is connected to the first chamber.
[0006] Furthermore, the simulation body includes an upper pump shaft simulation component, a lower pump shaft simulation component, and a pressure-bearing shell; the upper pump shaft simulation component passes through the pressure-bearing shell; the lower pump shaft simulation component is disposed inside the pressure-bearing shell; the lower pump shaft simulation component and the pressure-bearing shell are arranged radially at intervals, and the space between them is used to arrange the shaft seal simulation component.
[0007] Furthermore, a guide plate is also provided in the space between the pressure-bearing shell and the lower pump shaft simulation component, and the guide plate is correspondingly arranged at the inlet end of the second chamber.
[0008] Furthermore, a cavity heater is also provided outside the pressure-bearing shell; the cavity heater corresponds axially to the second cavity.
[0009] Furthermore, the durability test pipeline includes a circulation pump and two flow meters; the two flow meters are respectively located at the upstream end and downstream end of the circulation pipeline; the circulation pump is located downstream of the connection point between the circulation pipeline and the water replenishment and pressurization pipeline.
[0010] Furthermore, the durability test pipeline also includes a heat exchanger and a first regulating valve; the preheater is located upstream of the connection between the circulation pipeline and the water replenishment and pressurization pipeline, and the circulation pump, the heat exchanger, and the first regulating valve are located downstream of the connection between the circulation pipeline and the water replenishment and pressurization pipeline.
[0011] Furthermore, the downstream section of the injection pipe shares a pipe with the downstream section of the circulation pipe; a filter and one of the flow meters are installed on the shared pipe.
[0012] Furthermore, it also includes at least one pressure stabilizing pipeline, the pressure stabilizing pipeline including a pressure stabilizer disposed at the inlet end of the pressure stabilizing pipeline; the outlet end of the pressure stabilizing pipeline is connected to the injection pipeline and / or the circulation pipeline.
[0013] Furthermore, the water replenishment and pressurization pipeline includes a water replenishment and pressurization pipe and a deoxygenated water tank located at the inlet end of the water replenishment and pressurization pipe, and the outlet end of the water replenishment and pressurization pipe is connected to the circulation pipeline.
[0014] Furthermore, the outlet end of the water replenishment and pressurization pipeline is also connected to the injection pipeline.
[0015] Furthermore, the water replenishment and pressurization pipeline is also equipped with a water replenishment pump, a check valve, and a pressure stabilizing tank; the water replenishment pump is located between the deoxygenated water tank and the check valve, and the pressure stabilizing tank is located downstream of the check valve.
[0016] Furthermore, the water replenishment and pressurization pipeline also includes a water replenishment bypass, which is arranged in parallel with the water replenishment and pressurization pipeline. The two ends of the water replenishment bypass are respectively connected to the deoxygenated water tank and the circulation pipeline downstream of the water replenishment pump.
[0017] Furthermore, the leakage measurement pipeline includes multiple parallel measurement branches, each of which is equipped with a flow meter, and the flow meter range of each measurement branch is different.
[0018] Furthermore, a medium cooling device for reducing the temperature of the medium is provided upstream of the measuring branch.
[0019] Furthermore, an electronic scale is installed at the downstream end of the measuring branch where the flow meter with the smallest measuring range is located.
[0020] Furthermore, a throttling and pressure-reducing branch is provided between the at least one measuring branch and the first chamber, and the throttling and pressure-reducing branch includes at least one pressure-reducing mechanism.
[0021] Furthermore, the pressure-reducing mechanism includes an electrically adjustable valve; and / or The pressure-reducing mechanism includes an orifice plate assembly; and / or The pressure-reducing mechanism includes a reducing connector.
[0022] Furthermore, the at least one pressure-reducing mechanism includes an orifice plate assembly, which includes an upstream reducer, a downstream reducer, a connecting pipe, and a throttling orifice plate; the connecting pipe is disposed between the upstream reducer and the downstream reducer, and the throttling orifice plate is disposed within the connecting pipe.
[0023] Furthermore, the distance between the throttling orifice plate and the downstream reducer is greater than or equal to 1 / 3 of the axial length of the pipe and less than or equal to 1 / 2 of the pipe length.
[0024] The technical solution constructed by implementing the present invention has at least the following beneficial effects: The reactor main pump shaft seal performance test system set up in this invention can conduct thermal shock start-up tests, thermal shock test tests, and durability test tests on different types of nuclear main pump shaft seals to measure the leakage of various main pump shaft seal structures under high temperature shock or test, and provide experimental data support for shaft seal research and development. Attached Figure Description
[0025] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings: Figure 1 This is a schematic diagram of the structure of a reactor main pump shaft seal performance test system according to an embodiment of the present invention; Figure 2 yes Figure 1 A schematic diagram of the cross-sectional structure of the simulated object in the diagram; Figure 3 yes Figure 2 Schematic diagram of the AA-direction cross-section structure; Figure 4 yes Figure 2 Schematic diagram of the BB-direction cross-sectional structure in the middle; Figure 5 yes Figure 1 A cross-sectional structural diagram of the orifice plate assembly. Detailed Implementation
[0026] To provide a clearer understanding of the technical features, objectives, and effects of the present invention, specific embodiments are now described in detail with reference to the accompanying drawings. Many specific details are set forth in the following description to provide a thorough understanding of the invention. However, the invention can be practiced in many ways different from those described herein, and those skilled in the art can make similar modifications without departing from the spirit of the invention. Therefore, the invention is not limited to the specific embodiments disclosed below.
[0027] In the description of this invention, it should be understood that the terms "longitudinal", "lateral", "up", "down", "top", "bottom", "inner", "outer", etc., indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings or the orientation or positional relationship commonly used when the product of this invention is in use. They are only for the convenience of describing this 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. Therefore, they should not be construed as limitations on this invention.
[0028] Furthermore, the terms "first" and "second" 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 as "first" or "second" may explicitly or implicitly include at least one of that feature. In the description of this invention, "a plurality of" means at least two, such as two, three, etc., unless otherwise explicitly specified.
[0029] In this invention, unless otherwise explicitly specified and limited, the terms "installation," "connection," "linking," and "fixing," etc., 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, unless otherwise explicitly limited. Those skilled in the art can understand the specific meaning of the above terms in this invention according to the specific circumstances.
[0030] In this invention, unless otherwise explicitly specified and limited, "above" or "below" the second feature can mean that the first feature is in direct contact with the second feature, or that the first feature is in indirect contact with the second feature through an intermediate medium. Furthermore, "above" the second feature can mean that the first feature is directly above or diagonally above the second feature, or simply that the first feature is at a higher horizontal level than the second feature. "Below" the second feature can mean that the first feature is directly below or diagonally below the second feature, or simply that the first feature is at a lower horizontal level than the second feature.
[0031] like Figures 1 to 5As shown, the present invention constructs a reactor main pump shaft seal performance testing system 1, which can conduct performance tests on various types of shaft seals of reactor main pumps. The reactor main pump shaft seal performance testing system 1 includes a simulator 10, a thermal shock test pipeline 20, a durability test pipeline 30, a water replenishment and pressurization pipeline 40, a leakage measurement pipeline 50, and a pressure stabilization pipeline 60.
[0032] The simulator 10 is used to install the shaft seal simulator 2 and provide it with the operating environment of the reactor main pump. The outlet end of the thermal shock test pipeline 20 is connected to the inlet end of the simulator 10, providing a high-temperature, high-pressure test environment for the shaft seal simulator 2 to test its thermal performance. The two ends of the durability test pipeline 30 are connected to the inlet and outlet ends of the simulator 10, respectively, providing a high-temperature, high-pressure test environment for the shaft seal simulator 2 to test its service life. The outlet end of the water replenishment and pressurization pipeline 40 is connected to both the thermal shock test pipeline 20 and the durability test pipeline 30 to replenish and pressurize the two pipelines during the experiment. The inlet end of the leakage measurement pipeline 50 is connected to the leakage port 111 of the simulator 10 to measure the leakage of the shaft seal simulator 2 during the experiment. The pressure stabilizing pipeline 60 is connected to both the thermal shock test pipeline 20 and the durability test pipeline 30 to stabilize the system pressure during the experiment.
[0033] This invention, by setting up a thermal shock test pipeline 20 and a durability test pipeline 30, addresses the testing requirements of different types of shaft seals in nuclear main pumps. The coupling of the open thermal shock test pipeline 20 and the closed durability test pipeline 30 allows for experimental testing of the thermal shock resistance and service life of the main pump shaft seals, thereby providing experimental data support for the development of new shaft seals and ensuring the safety and reliability of the new shaft seals after they are put into use.
[0034] It should be noted that the specific shaft seal simulation component 2 can be different depending on the type of shaft seal to be tested, such as static pressure shaft seal, dynamic pressure shaft seal, passive shutdown seal, and high temperature resistant O-ring, etc., and no specific limitation is made here.
[0035] In some other embodiments, the reactor main pump shaft seal performance test system 1 may not include a pressure stabilizing pipeline 60. Alternatively, the pressure stabilizing pipeline 60 may be connected to only one of the test pipelines. Alternatively, there may be two pressure stabilizing pipelines 60, each corresponding to one of the two test pipelines.
[0036] In some other embodiments, the water replenishment and pressurization pipeline 40 may be connected only to the durability test pipeline 30. Alternatively, the number of water replenishment and pressurization pipelines 40 may be set to two, corresponding one-to-one with the two test pipelines.
[0037] like Figure 1 and Figure 2 As shown, in some embodiments, the shaft seal simulation component 2 is detachably disposed within the simulation body 10, dividing the space within the simulation body 10 into a first chamber 101 and a second chamber 102. The first chamber 101 has a leak port 111 and an exhaust port 112 on its chamber wall. The leak port 111 is used to connect to the inlet end of the leak measurement pipeline 50, and the exhaust port 112 is used for venting. The second chamber 102 has a first pipe interface 131 (i.e., the inlet end of the simulation body 10), a second pipe interface 132 (i.e., the outlet end of the simulation body 10), and a media discharge port 133 on its chamber wall. The first pipe interface 131 is connected to the outlet ends of the thermal shock test pipeline 20 and the durability test pipeline 30, respectively, and the second pipe interface 132 is connected to the inlet end of the durability test pipeline 30. The media discharge port 133 is used to discharge the experimental medium.
[0038] Specifically, please refer to the following: Figures 2 to 4 The simulation body 10 may include an upper pump shaft simulation component 11, a lower pump shaft simulation component 12, a pressure-bearing shell 13, a guide plate 14, and a cavity heater 15. The lower pump shaft simulation component 12 is disposed within the pressure-bearing shell 13, coaxially arranged with the pressure-bearing shell 13, and the two are radially spaced apart. The upper pump shaft simulation component 11 is coaxially inserted within the pressure-bearing shell 13, and its end face within the pressure-bearing shell 13 is spaced apart from the lower pump shaft simulation component 12.
[0039] The shaft seal simulation component 2 can be coaxially assembled within the gap between the pressure-bearing shell 13 and the lower pump shaft simulation component 12, thereby axially dividing the space defined by the upper pump shaft simulation component 11, the lower pump shaft simulation component 12, and the pressure-bearing shell 13 into a first chamber 101 and a second chamber 102. The first chamber 101 is jointly defined by the upper pump shaft simulation component 11, the pressure-bearing shell 13, the lower pump shaft simulation component 12, and the shaft seal simulation component 2. The second chamber 102 is jointly defined by the lower pump shaft simulation component 12, the pressure-bearing shell 13, and the shaft seal simulation component 2.
[0040] The guide plate 14 is disposed in the second chamber 102. It is a plate with an arc-shaped cross section. It is radially disposed in the gap between the pressure shell 13 and the lower pump shaft simulation component 12, and its thickness is less than the radial dimension of the gap. It is used to enhance the medium exchange at different locations in the pressure shell 13.
[0041] The cavity heater 15 is a cylindrical tube with both ends open, coaxially arranged outside the pressure shell 13, and corresponding to the second chamber 102 along the axial direction, used to assist in adjusting the temperature of the medium inside the simulation body 10.
[0042] The simulation body 10 provided in this invention can accurately simulate the working environment of the shaft seal inside the reactor pump shaft. At the same time, it can also measure the leakage amount by defining the first chamber 101 and cooperating with the leakage measurement pipeline 50.
[0043] By setting up a cavity heater 15, the present invention can work in conjunction with the heat source generator 21 in the thermal shock test pipeline 20 and the preheater 31 in the durability test pipeline 30 to further ensure that the environment of the second chamber 102 can accurately simulate the high-temperature environment conditions in which it is used in the reactor pump shaft.
[0044] Furthermore, the upper pump shaft simulation component 11 is generally a cylindrical tube extending through both ends, with one end penetrating inside the pressure-bearing shell 13, and the space inside the tube communicating with the space inside the pressure-bearing shell 13. The opening at the end away from the pressure-bearing shell 13 can be regarded as the exhaust port 112. The leakage port 111 is provided on the side wall of the upper pump shaft simulation component 11 and communicates with its internal space.
[0045] The pressure-bearing shell 13 is generally hollow cylindrical in shape, with a through hole at the top for the upper pump shaft simulation component 11 to pass through, and a medium discharge port 133 at the bottom.
[0046] The lower pump shaft simulator 12 is generally cylindrical, with a support foot at the axial end away from the upper pump shaft simulator 11. A positioning groove 134 is provided on the inner wall of the bottom end of the pressure-bearing housing 13 to accommodate the support foot. During the experiment, the positioning groove 134 provides radial positioning for the lower pump shaft simulator 12, which can achieve axial positioning through its own weight, thus preventing displacement due to media impact.
[0047] The pressure-bearing shell 13 has a first pipe interface 131 and a second pipe interface 132 respectively on opposite sides of its sidewall. The high-temperature and high-pressure medium in the thermal shock test pipeline 20 or the durability test pipeline 30 can enter the second chamber 102 through the first pipe interface 131. When the shaft seal simulation component 2 leaks, the medium in the second chamber 102 seeps into the first chamber 101 through the leak point and enters the leakage measurement pipeline 50 through the leak port 111 for leakage measurement.
[0048] During durability testing, the medium in the second chamber 102 can return to the durability test pipeline 30 via the second pipeline interface 132 to achieve medium circulation.
[0049] In some other embodiments, the lower pump shaft simulation component 12 can also be fixed relative to the pressure shell 13 by means of welding, threaded connection, glue connection, etc.
[0050] In some other embodiments, the number of the first pipe interface 131 may also be set to two, to correspond to the thermal shock test pipe 20 and the durability test pipe 30 respectively.
[0051] In some embodiments, the baffle 14 is positioned within the second chamber 102 approximately corresponding to the first pipe interface 131, in order to disperse the medium output from the first pipe interface 131 and improve the degree of medium exchange. Simultaneously, the radial arrangement of the baffle 14 between the first pipe interface 131 and the lower pump shaft simulator 12 can also reduce the impact of the medium output from the first pipe interface 131 on the lower pump shaft simulator 12.
[0052] In other embodiments, the guide plate 14 may also be in the form of a planar plate, a bent plate, an irregular plate, a non-circular arc plate, or other shapes. The number of guide plates 14 may also be multiple, arranged at intervals along the circumference of the lower pump shaft simulation component 12.
[0053] In some embodiments, the cavity heater 15 includes a plurality of heating elements arranged in a fish-scale pattern to form a tubular cavity heater 15. Each heating element includes a heating resistor and an insulating ceramic sheet wrapped around the heating resistor.
[0054] This allows for a tight enclosure of the pressure shell 13, improving the uniformity and efficiency of heat transfer. By incorporating fish-scale-arranged heating elements into the cavity heater 15, heating blind spots can be eliminated, ensuring a uniform temperature field on the surface of the pressure shell. Furthermore, it can accommodate the thermal expansion and contraction of the pressure shell 13 during thermal shock experiments, preventing deformation and damage to the cavity heater 15 and ensuring the long-term stability of the system.
[0055] In other embodiments, the cavity heater 15 may also be implemented using other existing heating structures such as a heating mesh made of heating resistance wires or an electric heating tape.
[0056] like Figure 1 As shown, in some embodiments, the thermal shock test pipeline 20 may include an injection pipeline 200 and a heat source generator 21, a first electric shut-off valve 23, a manual shut-off valve 70, a first heat exchanger 22, a first flow meter 24, and a filter 25 arranged sequentially on the injection pipeline 200.
[0057] The outlet end of the injection pipe 200 is connected to the first pipe interface 131 of the simulation body 10. The heat source generator 21 is connected to the inlet end of the injection pipe 200 and is used to supply high-temperature and high-pressure media to the pipeline. The first electric shut-off valve 23 is located between the manual shut-off valve 70 and the heat source generator 21, and both are used to control the opening and closing of the injection pipe 200. The first heat exchanger 22 is located downstream of the manual shut-off valve 70 and is used to regulate the temperature of the media in the injection pipe 200 through heat exchange, in conjunction with the heat source generator 21 and the cavity heater 15, to further ensure the accuracy of the high-temperature environment simulation. The first flow meter 24 is located downstream of the first heat exchanger 22, approximately at the injection pipe 200 near the first pipe interface 131, and is used to detect the flow rate of the media injected into the first pipe interface 131. The filter 25 is located downstream of the first flow meter 24 and is used to filter impurities in the media.
[0058] By setting up a heat source generator 21, which can be used in conjunction with a water replenishment and pressurization pipeline 40, this invention enables the system to simultaneously have a high-flow transient impact heat source and a low-flow steady-state test heat source, which is beneficial for accurately simulating different real-world working conditions.
[0059] Specifically, the filter 25 can be a centrifugal filter to avoid damage to the simulation body 10 and the shaft seal simulation component 2 by utilizing high filtration accuracy. Of course, the filter 25 can also be implemented using other existing filters with high-precision filtration effects.
[0060] In some other embodiments, the positions of the first heat exchanger 22 and the first flow meter 24 on the injection pipe 200 can be flexibly adjusted.
[0061] In some embodiments, the heat source generator 21 may include a steam pressure tank 211 and an electric heating element 212. The steam pressure tank 211 is used to contain the medium and provide a high-pressure environment. The electric heating element 212 is used to heat the medium in the steam pressure tank 211 to create a high-temperature and high-pressure environment.
[0062] Specifically, the volume of the steam pressure stabilizing tank 211 is greater than or equal to 6m³. 3 The average flow rate of 4m³ / min is provided to the second chamber 102 under operating conditions with a maximum temperature of 301℃ and a maximum pressure of 15.5MPa for no less than 30 minutes. 3 / h of media injection, or provide an average flow rate of 6m³ / min for not less than 5 minutes. 3 The medium is injected at a rate of / h, or an average flow rate of 10m³ / h is provided for at least 30 seconds. 3 The medium is injected at a rate of / h. Meanwhile, after injection, the drop in the liquid level of the steam pressure tank 211 will not expose the electric heating element 212.
[0063] In this way, the safety of the experiment can be ensured, and the thermal shock experiment constructed can accurately simulate the real environmental conditions of the shaft seal, thereby improving the reliability of the experiment.
[0064] In some embodiments, the durability test pipeline 30 may include a circulation pipeline 300 and a preheater 31, a second heat exchanger 32, a circulation pump 34, a filter 25, a first regulating valve 35, two pneumatic quick-closing valves, two manual shut-off valves 70, and two flow meters arranged on the circulation pipeline 300.
[0065] The inlet end of the circulation pipe 300 is connected to the second pipe interface 132, and the outlet end is connected to the first pipe interface 131, so that the durability test pipe 30 and the simulation body 10 are connected to form a relatively closed circulation loop, and the durability test of the shaft seal can be carried out through the circulation of the medium to measure the service life of the shaft seal.
[0066] Two flow meters are respectively installed at the upstream and downstream ends of the circulation pipe 300 to measure the flow rate of the medium at the first pipe interface 131 and the second pipe interface 132. The filter 25 is installed at the outlet end of the circulation pipe 300, downstream of the corresponding flow meter, and is used to filter impurities in the medium. The preheater 31 is installed upstream of the connection between the circulation pipe 300 and the water replenishment and pressurization pipe 400 to preheat the medium in the pipe.
[0067] The second heat exchanger 32, the first regulating valve 35, and the circulating pump 34 are all located downstream of the connection point between the circulating pipeline 300 and the makeup water pressurization pipeline 400. The circulating pump 34 is located upstream of the second heat exchanger 32 and the first regulating valve 35, and is used to pump the medium in the makeup water pressurization pipeline 400 into the circulating pipeline 300. The second heat exchanger 32 is located downstream of the first regulating valve 35.
[0068] One of the pneumatic switching valves and the manual shut-off valve 70 is located upstream of the flow meter near the second pipe interface 132, and the other pneumatic quick-closing valve and the manual shut-off valve 70 are located downstream of the second heat exchanger 32, for controlling the connection and disconnection of the durability test pipeline 30 and the simulation body 10.
[0069] This invention, by installing flow meters at the upstream and downstream ends of the circulation pipe 300, allows for the measurement of the leakage of the shaft seal simulation component 2 using the difference between the readings from the two flow meters. This, combined with the leakage measurement pipe 50, serves as a reference group for measuring the shaft seal leakage, thereby improving the accuracy of the leakage measurement.
[0070] The present invention provides a preheater 31 installed upstream of the connection between the circulation pipe 300 and the water replenishment and pressurization pipe 400. This preheater can heat the medium output by the simulation body 10 in advance, thus preventing the medium output by the simulation body 10 from mixing with the medium output by the water replenishment and pressurization pipe 400 and disrupting the temperature, pressure and experimental conditions of the entire circulation system.
[0071] The present invention provides a second heat exchanger 32 downstream of the connection between the circulation pipe 300 and the water replenishment and pressurization pipe 400. This allows for further adjustment of the temperature of the medium output from the simulation body 10 after mixing with the medium output from the water replenishment and pressurization pipe 400, thereby ensuring that the medium input into the simulation body 10 meets the experimental operating conditions and improving the accuracy of the experiment.
[0072] This invention provides a first regulating valve 35 downstream of the connection between the circulation pipe 300 and the water replenishment and pressurization pipe 400. This valve allows for flexible adjustment of the total flow rate of the medium after mixing the medium output from the simulator 10 and the medium output from the water replenishment and pressurization pipe 400. This stabilizes the total flow rate and total pressure in the circulation loop formed by the circulation pipe 300 and the simulator 10, eliminates disturbances caused by liquid replenishment, further ensures that the medium input into the simulator 10 meets the experimental operating conditions, and improves the accuracy of the experiment.
[0073] Furthermore, the injection pipe 200 of the thermal shock test pipeline 20 and the downstream pipe section of the circulation pipeline 300 can share a pipeline to reduce the total length of the system pipeline and lower the system construction cost.
[0074] Specifically, the two flow meters of the durability test pipeline 30 are defined as a first flow meter 24 and a second flow meter 33. The first flow meter 24 is installed on the shared pipeline, located at the position corresponding to the first pipeline interface 131 of the simulation body 10. The second flow meter 33 is installed at the position corresponding to the second pipeline interface 132. The first flow meter 24 is the flow meter installed at the outlet end of the thermal shock test pipeline 20.
[0075] The two pneumatic quick-closing valves of the durability test pipeline 30 are defined as a first pneumatic quick-closing valve 36 and a second pneumatic quick-closing valve 37. The first pneumatic quick-closing valve 36 and a manual shut-off valve 70 form a group, located at the inlet end of the circulation pipeline 300. The second pneumatic quick-closing valve 37 and another manual shut-off valve 70 form a group, located at the connection point before the circulation pipeline 300 and the injection pipeline 200 converge into a common pipeline.
[0076] Thus, when a thermal shock test is required, the two pneumatic quick-closing valves and two manual shut-off valves 70 on the durability test pipeline 30 can be closed to ensure that the injection pipeline 200 is connected to the simulation body 10 through a common pipeline.
[0077] In some other embodiments, the circulation pipe 300 may be equipped with only one flow meter, or no flow meter at all.
[0078] In some other embodiments, the downstream positions of the first regulating valve 35 and the second heat exchanger 32 at the connection between the circulation pipe 300 and the water replenishment and pressurization pipe 400 can be flexibly adjusted.
[0079] In some embodiments, the circulating pump 34 may be implemented using existing pump body structures such as canned pumps, and no specific limitation is made here.
[0080] In some embodiments, the pressure stabilizing line 60 may include a pressure stabilizing line 600, a pressure regulator 61, and a third pneumatic quick-closing valve 62.
[0081] The pressure regulator 61 is located at the inlet end of the pressure stabilizing pipeline 600 and is used to stabilize the system pressure. The third pneumatic quick-closing valve 62 is located downstream of the pressure regulator 61 and is used to control the opening and closing of the pressure stabilizing pipeline 60.
[0082] Specifically, the outlet end of the pressure stabilizing pipe 600 can be connected to the shared pipe of the thermal shock test pipe 20 and the durability test pipe 30, so as to act on the two pipes respectively.
[0083] The voltage regulator 61 is used in conjunction with other pipelines to establish a stable high-pressure condition. Specifically, it can be implemented using existing voltage regulators that utilize nitrogen for pressure stabilization. By setting the voltage regulator 61 to use nitrogen for pressure stabilization, the properties of nitrogen—anti-oxidation, anti-pollution, safety, and high-temperature resistance—can be utilized to further ensure the accuracy of experimental data in conjunction with the high-temperature, high-pressure, closed, and liquid media conditions in the system.
[0084] In some other embodiments, when the thermal shock test pipeline 20 and the durability test pipeline 30 do not share a pipeline, the pressure stabilizing pipeline 60 may be connected only to either the thermal shock test pipeline 20 or the durability test pipeline 30. Alternatively, the number of pressure stabilizing pipelines 60 may be set to two, with both the thermal shock test pipeline 20 and the durability test pipeline 30 connected to a pressure stabilizing pipeline 60.
[0085] In some embodiments, the water replenishment and pressurization pipeline 40 may include a water replenishment and pressurization pipeline 400, a deoxygenated water tank 41, a water replenishment pump 42, a check valve 43, a pressure stabilizing tank 44, and a manual shut-off valve 70.
[0086] The outlet end of the water replenishment and pressurization pipeline 400 is connected to both the thermal shock test pipeline 20 and the durability test pipeline 30. The deoxygenated water tank 41 is located at the inlet end of the water replenishment and pressurization pipeline 400 and is used to replenish deoxygenated water to either the thermal shock test pipeline 20 or the durability test pipeline 30 via the water replenishment and pressurization pipeline 400. The water replenishment pump 42 is located downstream of the deoxygenated water tank 41 and pumps water from the deoxygenated water tank 41 to either the thermal shock test pipeline 20 or the durability test pipeline 30. The check valve 43 is located downstream of the water replenishment pump 42 and controls the flow direction of the medium to prevent the high-pressure medium in the thermal shock test pipeline 20 or the durability test pipeline 30 from flowing back into the water replenishment and pressurization pipeline 40. The pressure stabilizing tank 44 is located downstream of the check valve 43 and mitigates pressure fluctuations in the thermal shock test pipeline 20 or the durability test pipeline 30 caused by the operation of the water replenishment pump 42.
[0087] Manual shut-off valves 70 are installed downstream of the pressure tank 44 to the thermal shock test pipeline 20 and the durability test pipeline 30 to control the connection and disconnection between the water replenishment and pressurization pipeline 40 and the thermal shock test pipeline 20 and the durability test pipeline 30.
[0088] The water replenishment pump 42 can be implemented using existing technologies such as plunger pumps, and no specific limitations are made here.
[0089] Furthermore, the water replenishment and pressurization pipeline 40 may also include a water replenishment bypass 410. The water replenishment bypass 410 is connected in parallel with part of the water replenishment and pressurization pipeline 400 and is used to replenish water to the thermal shock test pipeline 20 or the durability test pipeline 30 under the action of the non-water replenishment pump 42.
[0090] Specifically, the inlet end of the water supply bypass 410 is connected to the deaerated water tank 41, and the outlet end is connected to the pipeline between the water supply pump 42 and the check valve 43. A second regulating valve 45 is installed on the water supply bypass 410, and a manual shut-off valve 70 is installed between the deaerated water tank 41 and the water supply pump 42, so as to realize the on-off control of each parallel branch using the valves on the two branches.
[0091] The second regulating valve 45 can be an electric regulating valve, so that the system can automatically control the valve opening and achieve automatic pressure stabilization.
[0092] This invention, by setting up a water supply bypass 410, can serve as a backup to the water supply booster pipeline 400, ensuring that water supply function can still be achieved even if the water supply pump 42 fails. Simultaneously, by installing the water supply pump 42 on the water supply booster pipeline 400, and eliminating the pump body on the water supply bypass 410, the water supply booster pipeline 400 can handle high-pressure water supply, meeting the high flow and high pressure requirements of the experimental pipeline. This allows the water supply bypass 410 to handle precise and stable pressure water supply, achieving automatic, micro-volume, and continuous adjustment, and avoiding water supply shock.
[0093] In some other embodiments, the second regulating valve 45 may also be configured as a manual shut-off valve.
[0094] In some other embodiments, the water replenishment and pressurization pipeline 40 may be connected only to the thermal shock test pipeline 20 or the durability test pipeline 30. Alternatively, the number of water replenishment and pressurization pipelines 40 may be set to two, with the durability test pipeline 30 and the thermal shock test pipeline 20 respectively connected to the water replenishment and pressurization pipeline 40.
[0095] In some embodiments, the leakage measurement line 50 may include a throttling and pressure-reducing branch 51 and at least one measuring branch. The throttling and pressure-reducing branch 51 is disposed between the measuring branch and the simulator 10, and is used to throttle and reduce the pressure of the medium output from the simulator 10. The measuring branch is used to measure the medium output from the simulator 10.
[0096] Specifically, the throttling and pressure-reducing branch 51 includes at least one pressure-reducing mechanism for throttling and pressure reduction. There can be multiple measuring branches, which are connected in parallel downstream of the throttling and pressure-reducing branch 51. Each measuring branch is equipped with a flow meter, each with a different range, to ensure measurement accuracy by using flow meters with different ranges for different experiments.
[0097] For example in Figure 1 In the embodiment shown, there are three measurement branches, which are now defined as the first measurement branch 52, the second measurement branch 53, and the third measurement branch 54, respectively.
[0098] The first measuring branch 52 includes a third flow meter 521, the flow meter 521 having a range greater than or equal to 0.05m. 3 / h, less than or equal to 0.5 m 3 / h. The second measuring branch 53 has a fourth flow meter 531, the range of which is greater than or equal to 0.4 m. 3 / h, less than or equal to 4 m 3 / h. The third measuring branch 54 has a fifth flow meter 541, the range of which is greater than or equal to 3 m. 3 / h, less than or equal to 30 m 3 / h.
[0099] It should be noted that the number of measurement branches and the specific range of the flow meter on each measurement branch can be flexibly adjusted according to specific experimental requirements. There are too many potential embodiments to list them all here.
[0100] In some embodiments, the throttling and pressure-reducing branch 51 may include a throttling and pressure-reducing pipeline 510, a second electrically operated shut-off valve 514, and three pressure-reducing mechanisms. The three pressure-reducing mechanisms are connected in series on the throttling and pressure-reducing pipeline 510 to achieve three-stage pressure reduction. The second electrically operated shut-off valve 514 is located on the throttling and pressure-reducing pipeline 510 and is used to quickly switch the leakage measurement pipeline 50 on and off, rapidly cutting off the leaking pipeline in the event of a potential large leak.
[0101] Specifically, the three pressure-reducing mechanisms can be a third regulating valve 511, an orifice plate assembly 512, and a reducing connector 513, respectively. The third regulating valve 511 is located at the inlet end of the throttling and pressure-reducing pipeline 510, the second electric shut-off valve 514 is located between the third regulating valve 511 and the orifice plate assembly 512, and the reducing connector 513 is located downstream of the orifice plate assembly 512. The third regulating valve 511 serves as the first-stage pressure reduction mechanism for adjustable pressure reduction. The orifice plate assembly 512 serves as the second-stage pressure reduction mechanism, and the reducing connector 513 serves as the third-stage pressure reduction mechanism; both, along with the orifice plate assembly 512, are used for fixed pressure reduction.
[0102] By setting up the throttling and depressurizing branch 51, this invention can simulate the flow distance and resistance characteristics of the leakage pipeline from the main pump leak outlet to the RCV system in a real nuclear power plant. While depressurizing the leaking medium to ensure the safety of the terminal equipment, it can accurately simulate the real nuclear power environment, thereby further improving the accuracy of the experiment.
[0103] Meanwhile, by setting up a throttling and pressure-reducing branch 51 including multiple pressure-reducing mechanisms, multiple safety barriers can be set up. When the shaft seal simulation component 2 under test is unable to achieve a sealing effect under high temperature and high pressure environment, a large amount of high temperature and high pressure medium is output through the leakage port 111. Under the action of multiple pressure-reducing mechanisms, the medium can be cut off, thereby improving the safety of the high temperature and high pressure experiment.
[0104] It should be noted that the second electric shut-off valve 514 and the reducing fitting 513 can be implemented using existing technologies, and will not be elaborated further here.
[0105] In some other embodiments, the pressure-reducing mechanism may also include at least one of these components.
[0106] See also Figure 5 In some embodiments, the orifice plate assembly 512 may include an upstream reducer 5121, a connecting pipe 5122, a downstream reducer 5123, and a throttling orifice plate 5124.
[0107] The upstream reducer 5121 and the downstream reducer 5123 are two reducers with the same large-diameter end dimensions. The two ends of the connecting pipe 5122 are respectively connected to the large-diameter ends of the upstream reducer 5121 and the downstream reducer 5123. The orifice plate 5124 is horizontally disposed within the connecting pipe 5122 to divide the space within the upstream reducer 5121, the connecting pipe 5122, and the downstream reducer 5123 into two parts.
[0108] The orifice plate 5124 is fixed inside the pipe 5122 by welding. The outer periphery of the side facing downstream reducer 5123 is welded to the peripheral wall of the pipe 5122 to achieve the fixation of the orifice plate 5124 inside the pipe 5122.
[0109] Specifically, the fixed position of the orifice plate 5124 within the connector 5122 along the axial direction allows the axial spacing between the orifice plate 5124 and the downstream reducer 5123 to be 1 / 3 to 1 / 2 of the length of the connector 5122.
[0110] This allows for ample transition space, preventing welding at adjacent connection points from reducing structural strength. It also facilitates welding operations.
[0111] For example Figure 1 As shown, in some embodiments, a medium cooling device is provided upstream of each measurement branch to reduce the temperature of the medium, so as to cool the high-temperature and high-pressure medium into a liquid state for measurement.
[0112] Specifically, the leakage measurement pipeline 50 also includes a third heat exchanger 55, located upstream of the second measurement branch 53 and the third measurement branch 54, for reducing the temperature of the medium flowing to the second measurement branch 53 or the third measurement branch 54 through heat exchange. The first measurement branch 52 also includes a water-cooled jacket 522, located upstream of the third flow meter 521, for reducing the temperature of the medium within the first measurement branch 52.
[0113] It is important to understand that heat exchangers typically have complex internal structures with numerous flow channels and high resistance at bends. Since the first measuring branch 52 corresponds to minor leaks, if the medium with a minor leak enters the first measuring branch 52 through the heat exchanger, it will affect the measurement accuracy of the first measuring branch 52, and may even prevent the medium with a minor leak from flowing out of the heat exchanger.
[0114] The present invention uses a water-cooling jacket 522 specifically set in the first measurement branch 52 for water cooling, and sets a third heat exchanger 55 upstream of the second measurement branch 53 and the third measurement branch 54, which can effectively avoid the influence of the heat exchanger 55 on the measurement accuracy and further ensure the accuracy of the experimental data.
[0115] The present invention improves the service life of the equipment by setting a throttling and pressure-reducing branch 51 between the measuring branch and the simulation body 10, and by reducing the impact of the high-pressure medium on the third heat exchanger 55 through various pressure-reducing mechanisms.
[0116] In some embodiments, the third heat exchanger 55 may specifically be an existing all-welded plate heat exchanger with a heat transfer coefficient greater than or equal to 1000 W / (m²). 2 C), taking advantage of its smaller volume under the same heat exchange, quickly cools the leaked two-phase high-temperature and high-pressure medium into a liquid medium for measurement.
[0117] In some other embodiments, water-cooled jackets 522 may also be provided on each of the three measuring branches, and the medium is cooled by water cooling.
[0118] In some embodiments, the first measuring branch 52 may include a first measuring pipe 520, a third flow meter 521, a water-cooled jacket 522, an electronic scale 523, and a manual shut-off valve 70. The third flow meter 521, the manual shut-off valve 70, and the water-cooled jacket 522 are all disposed on the first measuring pipe 520, with the manual shut-off valve 70 located downstream of the third flow meter 521. The electronic scale 523 is disposed at the outlet end of the first measuring pipe 520 and is used to measure the amount of media leakage by weighing.
[0119] The electronic scale 523 can be electrically connected to the system control module to remotely transmit measurement data to the control module, so that the control module can display the leakage data in real time.
[0120] In some embodiments, the electronic scale 523 may have a weighing range of 0-50 kg and may be equipped with a closed container to mitigate the impact of medium evaporation on weighing.
[0121] In some embodiments, the second measuring branch 53 includes a second measuring pipe 530, a fourth flow meter 531, and a manual shut-off valve 70. The fourth flow meter 531 and the manual shut-off valve 70 are both disposed on the second measuring pipe 530, and the fourth flow meter 531 is disposed upstream of the manual shut-off valve 70.
[0122] In some embodiments, the third measuring branch 54 includes a third measuring pipe 540, a fifth flow meter 541, and a manual shut-off valve 70. The fifth flow meter 541 and the manual shut-off valve 70 are both disposed on the third measuring pipe 540, and the fifth flow meter 541 is disposed upstream of the manual shut-off valve 70.
[0123] It should be noted that all flow meters in the reactor main pump shaft seal performance test system 1 can be existing Venturi flow meters, so as to take advantage of their one-piece molded fully enclosed, low pressure loss and no dead corners in the structure to further ensure the accuracy of the experimental measurement data.
[0124] The present invention will be further explained below through specific experimental procedures.
[0125] When the shaft seal simulation component 2 is a passive shutdown seal and the experiment is a thermal shock start-up experiment, the pipelines used may include the simulation body 10, the thermal shock test pipeline 20, the water replenishment and pressurization pipeline 40, the leakage measurement pipeline 50, and the pressure stabilizing pipeline 60.
[0126] Before the experiment begins, the relevant pipelines can be tested for leaks to ensure that a stable high-temperature and high-pressure environment can be constructed during the experiment.
[0127] Specifically, the valves of each pipeline can be opened first, and deionized water with a chloride ion content not exceeding 25 mg / L can be used to make the pressure of each pipeline greater than or equal to 1.5 times the vaporization pressure of the medium at the highest temperature that the circuit can reach during the experiment, in order to test the sealing performance of the experimental pipeline.
[0128] Furthermore, isolation boundaries required for the experiment can be constructed to isolate pipelines that are not involved in the experiment.
[0129] Specifically, the two manual shut-off valves 70 on the durability test pipeline 30 and the manual shut-off valves 70 on the pipeline connected to the durability test pipeline 30 in the water replenishment and pressurization pipeline 40 are closed.
[0130] Furthermore, confirm the status of the pipelines required for the experiment.
[0131] Specifically, the first electric shut-off valve 23, the third regulating valve 511, the second electric shut-off valve 514, the manual shut-off valve 70 on the first measuring branch 52, the manual shut-off valve 70 on the third measuring branch 54, and the manual shut-off valve 70 on the pipeline of the water replenishment and pressurization pipeline 40 that is connected to the thermal shock test pipeline 20 are closed.
[0132] Open all other valves on the pipeline required for the experiment along the direction of medium flow, and fill the pipeline with medium to complete gravity water injection and venting, as well as dynamic venting under pressure. At the same time, ensure that the secondary circulating cooling water flow of the first heat exchanger 22 and the third heat exchanger 55 is regulated, and that the heat source generator 21 has established a liquid level.
[0133] Furthermore, a formal measurement experiment was conducted, controlling the temperature of the medium inside the heat source generator 21 to 301°C at a flow rate of 1m. 3The shaft seal simulation component 2 inside the impact simulation body 10 was used to verify that the shaft seal simulation component 2 can be activated and achieve sealing under high temperature and high pressure impact.
[0134] Specifically, a normal temperature and high pressure state is first established by using the water replenishment and pressurization pipeline 40 and the pressure stabilization pipeline 60 to maintain the pressure in the pipeline at 15.5MPa.
[0135] Furthermore, the electric heating element 212 is activated to prepare a high-temperature medium of 345°C and 15.5MPa within the heat source generator 21, in order to establish a high-temperature and high-pressure state.
[0136] Further, the first electric shut-off valve 23 and the second electric shut-off valve 514 are opened sequentially, and the third regulating valve 511 is slowly opened, so that the reading of the first flow meter 24 is 1m³. 3 / h. At the same time, the secondary side circulating cooling water flow rate of the first heat exchanger 22 is adjusted so that the medium temperature at the first pipe interface 131 is 301℃.
[0137] Furthermore, the third pneumatic quick-closing valve 62 is closed, and the timer is run for five minutes. During this period, the medium temperature at the first pipe interface 131 is kept constant by controlling the electric heating element 212 and the first heat exchanger 22.
[0138] Furthermore, data on the leakage rate over time were recorded to complete the experiment.
[0139] When the shaft seal simulation component 2 is a static pressure shaft seal and the experiment is a thermal shock test, the pipelines used may include the simulation body 10, the thermal shock test pipeline 20, the water replenishment and pressurization pipeline 40, the leakage measurement pipeline 50, and the pressure stabilizing pipeline 60.
[0140] The experimental procedure is roughly the same as the aforementioned thermal shock start-up experiment. The main difference is that, based on the different type of shaft seal being tested, in this experiment, the leakage measurement pipeline 50 uses the third measurement branch 54, while the first measurement branch 52 and the second measurement branch 53 are closed. Simultaneously, the third regulating valve 511 needs to be quickly and fully opened during the formal experiment.
[0141] Meanwhile, after the temperature adjustment is completed in the formal experiment, the timing should be run for no more than 30 minutes. When the measurement data of the fifth flow meter 541 stabilizes, or when the heat source generator 21 generates a low liquid level alarm, the experiment should be stopped, and the leakage data during this period should be recorded.
[0142] When the shaft seal simulation component 2 is a dynamic pressure shaft seal or a high temperature resistant O ring, and the experiment is a durability test, the pipeline used may include the simulation body 10, the durability test pipeline 30, the water replenishment and pressurization pipeline 40, the leakage measurement pipeline 50, and the pressure stabilizing pipeline 60.
[0143] Before starting the experiment, the relevant pipelines should be tested for leaks to ensure a stable high-temperature and high-pressure environment can be constructed during the experiment. The specific operating procedure is similar to that of the thermal shock start-up experiment, and will not be repeated here.
[0144] Furthermore, isolation boundaries required for the experiment can be constructed to isolate pipelines that are not involved in the experiment.
[0145] Specifically, the manual shut-off valve 70 on the thermal shock test pipeline 20, the first electric shut-off valve 23, and the manual shut-off valve 70 on the pipeline connected to the thermal shock test pipeline 20 in the water replenishment and pressurization pipeline 40 are closed.
[0146] Furthermore, confirm the status of the pipelines required for the experiment.
[0147] Specifically, the third regulating valve 511, the second electric shut-off valve 514, the manual shut-off valve 70 on the second measuring branch 53, and the manual shut-off valve 70 on the third measuring branch 54 are closed.
[0148] Open all other valves on the pipeline required for the experiment along the direction of medium flow, and fill the pipeline with medium to complete gravity water injection and venting, as well as dynamic venting with pressurization. At the same time, ensure that the secondary side circulating cooling water flow of the second heat exchanger 32 and the third heat exchanger 55 is regulated, and that the pressure stabilizer 61 has established a liquid level.
[0149] Furthermore, formal measurement experiments were conducted, and the temperature, pressure, and flow rate provided by the durability test pipeline 30 to the shaft seal simulation component 2 were controlled to meet the experimental operating conditions. The medium circulated and impacted the shaft seal simulation component 2, and the leakage data of the shaft seal simulation component 2 under experimental conditions over time were obtained.
[0150] Specifically, the temperature is adjusted by the preheater 31 and the second heat exchanger 32, and the pressure is adjusted by the water replenishment and pressurization pipeline 40 to establish the high temperature and high pressure conditions required for the experiment.
[0151] Furthermore, open the second electric shut-off valve 514 and the third regulating valve 511, and start timing for no less than 72 hours. During this period, record the changes in the readings of the third flow meter 521 and the electronic scale 523 over time to obtain data on the change in leakage over time, thus completing the experiment.
[0152] Understandably, the above-mentioned technical features can be used in any combination without restriction.
[0153] The above embodiments merely illustrate specific implementations 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 those skilled in the art can freely combine the above technical features without departing from the concept of the present invention, and can also make several modifications and improvements, all of which fall within the protection scope of the present invention. Therefore, all equivalent transformations and modifications made with respect to the scope of the claims of the present invention should fall within the scope of the claims of the present invention.
Claims
1. A test system for the shaft seal performance of a reactor main pump, characterized in that, include: The simulation body (10) has a first chamber (101) and a second chamber (102) located on opposite sides of the shaft seal simulation part (2); The thermal shock test pipeline (20) includes an injection pipe (200) and a heat source generator (21) disposed at the inlet end of the injection pipe (200); the heat source generator (21) defines a space for containing and heating the medium; the second chamber (102) is connected to the outlet end of the injection pipe (200); The durability test pipeline (30) includes a circulation pipeline (300) and a preheater (31) installed on the circulation pipeline (300); the second chamber (102) is connected end to end to the circulation pipeline (300) to form a circulation loop; A water replenishment and pressurization pipeline (40), the outlet end of which is connected to the circulation pipeline (300); and The leakage measurement pipeline (50) has at least one measurement branch, the inlet end of which is connected to the first chamber (101).
2. The reactor main pump shaft seal performance test system according to claim 1, characterized in that, The simulation body (10) includes an upper pump shaft simulation component (11), a lower pump shaft simulation component (12), and a pressure-bearing shell (13); the upper pump shaft simulation component (11) passes through the pressure-bearing shell (13); the lower pump shaft simulation component (12) is disposed inside the pressure-bearing shell (13); the lower pump shaft simulation component (12) and the pressure-bearing shell (13) are arranged radially apart, and the space between them is used to arrange the shaft seal simulation component (2).
3. The reactor main pump shaft seal performance test system according to claim 2, characterized in that, A guide plate (14) is also provided in the space between the pressure shell (13) and the lower pump shaft simulation component (12), and the guide plate (14) is correspondingly provided with the inlet end of the second chamber (102).
4. The reactor main pump shaft seal performance test system according to claim 2, characterized in that, A cavity heater (15) is also provided outside the pressure shell (13); the cavity heater (15) is axially aligned with the second cavity (102).
5. The reactor main pump shaft seal performance test system according to claim 1, characterized in that, The durability test pipeline (30) includes a circulation pump (34) and two flow meters; the two flow meters are respectively located at the upstream end and downstream end of the circulation pipeline (300); the circulation pump (34) is located downstream of the connection between the circulation pipeline (300) and the water replenishment and pressurization pipeline (40).
6. The reactor main pump shaft seal performance test system according to claim 5, characterized in that, The durability test pipeline (30) also includes a heat exchanger and a first regulating valve (35); the preheater (31) is located upstream of the connection between the circulation pipeline (300) and the water replenishment and pressurization pipeline (40), and the circulation pump (34), the heat exchanger and the first regulating valve (35) are located downstream of the connection between the circulation pipeline (300) and the water replenishment and pressurization pipeline (40).
7. The reactor main pump shaft seal performance test system according to claim 5, characterized in that, The downstream section of the injection pipe (200) shares a pipe with the downstream section of the circulation pipe (300); a filter (25) and one of the flow meters are installed on the shared pipe.
8. The reactor main pump shaft seal performance test system according to any one of claims 1 to 7, characterized in that, It also includes at least one pressure stabilizing line (60), the pressure stabilizing line (60) including a pressure regulator (61) disposed at the inlet end of the pressure stabilizing line (600); the outlet end of the pressure stabilizing line (600) is connected to the injection line (200) and / or the circulation line (300).
9. The reactor main pump shaft seal performance test system according to any one of claims 1 to 7, characterized in that, The water replenishment and pressurization pipeline (40) includes a water replenishment and pressurization pipe (400) and a deoxygenated water tank (41) located at the inlet end of the water replenishment and pressurization pipe (400). The outlet end of the water replenishment and pressurization pipe (400) is connected to the circulation pipe (300).
10. The reactor main pump shaft seal performance test system according to any one of claims 1 to 7, characterized in that, The outlet end of the water replenishment and pressurization pipeline (40) is also connected to the injection pipeline (200).
11. The reactor main pump shaft seal performance test system according to claim 9, characterized in that, The water replenishment and pressurization pipeline (400) is also equipped with a water replenishment pump (42), a check valve (43) and a pressure stabilizing tank (44); the water replenishment pump (42) is located between the deoxygenated water tank (41) and the check valve (43), and the pressure stabilizing tank (44) is located downstream of the check valve (43).
12. The reactor main pump shaft seal performance test system according to claim 11, characterized in that, The water replenishment and pressurization pipeline (40) also includes a water replenishment bypass (410), which is connected in parallel with the water replenishment and pressurization pipeline (400). The two ends of the water replenishment bypass (410) are respectively connected to the deoxygenated water tank (41) and the circulation pipeline (300) downstream of the water replenishment pump (42).
13. The reactor main pump shaft seal performance test system according to any one of claims 1 to 7, characterized in that, The leakage measurement pipeline (50) includes multiple parallel measurement branches, each of which is equipped with a flow meter, and the flow meter range of each measurement branch is different.
14. The reactor main pump shaft seal performance test system according to claim 13, characterized in that, A medium cooling device for reducing the temperature of the medium is installed upstream of the measurement branch.
15. The reactor main pump shaft seal performance test system according to claim 13, characterized in that, An electronic scale is installed at the downstream end of the measuring branch where the flow meter with the smallest measuring range is located.
16. The reactor main pump shaft seal performance test system according to any one of claims 1 to 7, characterized in that, A throttling and pressure-reducing branch (51) is also provided between the at least one measuring branch and the first chamber (101), and the throttling and pressure-reducing branch (51) includes at least one pressure-reducing mechanism.
17. The reactor main pump shaft seal performance test system according to claim 16, characterized in that, The pressure-reducing mechanism includes an electrically adjustable valve (511); and / or The pressure reduction mechanism includes an orifice plate assembly (512); and / or The pressure-reducing mechanism includes a reducing connector (513).
18. The reactor main pump shaft seal performance test system according to claim 16, characterized in that, The at least one pressure-reducing mechanism includes an orifice plate assembly (512), which includes an upstream reducer (5121), a downstream reducer (5123), a connecting pipe (5122), and a throttling orifice plate (5124); the connecting pipe (5122) is disposed between the upstream reducer (5121) and the downstream reducer (5123), and the throttling orifice plate (5124) is disposed within the connecting pipe (5122).
19. The reactor main pump shaft seal performance test system according to claim 18, characterized in that, The distance between the throttling orifice plate (5124) and the downstream reducer (5123) is greater than or equal to 1 / 3 of the axial length of the connecting pipe (5122) and less than or equal to 1 / 2 of the length of the connecting pipe (5122).