Nuclear-grade high-temperature cut-off valve testing device

Abstract

The utility model discloses a nuclear-grade high-temperature cut-off valve testing device, which comprises an inter-process simulation device, a testing medium supply system and a leak detection system, a cut-off valve is accommodated in the inter-process simulation device, and two ends of the cut-off valve are respectively connected with an air inlet pipeline and an air outlet pipeline; the test medium supply system is connected to the cut-off valve through an air inlet pipeline and comprises a steam generation device and an energy storage device connected with the steam generation device, and the energy storage device can store steam conveyed by the steam generation device to the energy storage device. The steam generation device and the energy storage device are both used for supplying steam to the cut-off valve through the air inlet pipeline. The leak detection system is used for detecting whether the cut-off valve leaks or not. According to the utility model, various performance tests can be carried out, the actual installation process environment of the cut-off valve can be accurately simulated, the working temperature of actual operation of the valve can be reached, and the reliability of long-term operation of the cut-off valve in a high-temperature environment can be more accurately verified.

Description

Technical Field

[0001] This utility model relates to the field of valve testing technology, and in particular to a nuclear-grade high-temperature shut-off valve testing device. Background Technology

[0002] Nuclear-grade high-temperature shut-off valves are critical components in nuclear facilities, and their stable operation under various conditions is essential for the safety of nuclear power plants. In recent years, high-temperature reactors such as sodium-cooled fast reactors, high-temperature gas-cooled reactors, molten salt reactors, and lead / lead-bismuth reactors have developed rapidly in my country. Compared with valves in traditional pressurized water reactors, the critical valves in these high-temperature nuclear facilities must cope with challenges such as higher operating temperatures and greater thermal shock under accident conditions.

[0003] Currently, there are many problems to be solved in the performance testing of nuclear-grade high-temperature shut-off valves. On the one hand, the experimental capabilities of domestic nuclear power high-temperature valves are limited. The test bench temperatures of most valve manufacturers cannot meet the qualification requirements of nuclear-grade high-temperature valves, leading nuclear power plant operators to be cautious about using domestically produced high-temperature valves. According to the requirement that nuclear-grade high-temperature valves should be tested at their actual service temperatures, there is still a gap between the maximum testing temperature capability of domestic high-temperature valves and the qualification requirements of nuclear-grade high-temperature valves. This makes it impossible to effectively verify the service life and reliability of nuclear-grade high-temperature valves at high temperatures. On the other hand, existing testing equipment is difficult to comprehensively simulate the complex operating conditions of nuclear-grade high-temperature shut-off valves in actual operation. It cannot flexibly and stably supply steam flow according to the different test requirements. Common testing equipment often can only test the valve's performance under a single specific condition, failing to comprehensively consider the synergistic effects of multiple actual operating conditions on valve performance. In some tests with strict steam flow requirements, such as thermal shock tests and cycle life tests, it is difficult to obtain accurate and reliable test results. Therefore, it is necessary to improve existing technologies to overcome their shortcomings. Utility Model Content

[0004] To address the aforementioned technical issues, this utility model provides a nuclear-grade high-temperature shut-off valve testing device that can comprehensively and accurately simulate the actual operating conditions of nuclear-grade high-temperature shut-off valves. It also possesses comprehensive performance testing methods and a stable steam supply system, thereby more accurately verifying the reliability of valves operating in high-temperature environments over long periods.

[0005] The technical solution adopted by this utility model to solve its technical problem is: a nuclear-grade high-temperature shut-off valve testing device, comprising:

[0006] A process room simulation device is used to construct an environment similar to the actual installation process room of the shut-off valve. The shut-off valve is housed in the process room simulation device, and its two ends are respectively connected to an air inlet pipe and an air outlet pipe.

[0007] A test medium supply system is connected to the shut-off valve via the air inlet pipe. The test medium supply system includes a steam generator and an energy storage device connected to the steam generator. The energy storage device is capable of storing steam supplied to it by the steam generator. Both the steam generator and the energy storage device are used to supply steam to the shut-off valve via the air inlet pipe.

[0008] And a leak detection system for detecting whether the shut-off valve is leaking;

[0009] The air inlet pipe and the air outlet pipe are each equipped with one or more shut-off valves.

[0010] As a further improvement of this utility model, the process room simulation device is provided with a cold air inlet pipe and a cold air outlet pipe. The cold air inlet pipe is connected to a cooling fan, and the cold air outlet pipe is provided with a ventilation valve. When the ventilation valve is opened, the cold air input into the process room simulation device by the cooling fan through the cold air inlet pipe can be discharged to the outside through the cold air outlet pipe.

[0011] As a further improvement of this utility model, the interior of the process room simulation device is equipped with a heat preservation device.

[0012] As a further improvement of this utility model, the steam generator is connected to the air inlet pipe through a first output pipe, and a first shut-off valve is provided on the first output pipe; the energy storage device is connected to the air inlet pipe through an energy storage pipe and a second output pipe, and a second shut-off valve is provided on the energy storage pipe; a third shut-off valve is provided on the section between the air inlet pipe and the connection node of the energy storage pipe and the second output pipe.

[0013] As a further improvement of this utility model, the nuclear-grade high-temperature shut-off valve test device also includes a bypass pipe, the two ends of which are respectively connected to the inlet pipe and the outlet pipe, and an eighth shut-off valve is provided on the bypass pipe.

[0014] As a further improvement of this utility model, the intake pipe is provided with a fourth shut-off valve and a fifth shut-off valve, and one end of the bypass pipe connected to the intake pipe is located between the fourth shut-off valve and the fifth shut-off valve; the outlet pipe is provided with a ninth shut-off valve and a tenth shut-off valve, and the other end of the bypass pipe connected to the outlet pipe is located between the ninth shut-off valve and the tenth shut-off valve.

[0015] As a further improvement of this utility model, the nuclear-grade high-temperature shut-off valve test device also includes an exhaust pipe connected to the air inlet pipe. One end of the exhaust pipe connected to the air inlet pipe is located between the fifth shut-off valve and the shut-off valve, and a sixth shut-off valve is provided on the exhaust pipe.

[0016] As a further improvement of this utility model, the leak detection system includes a valve internal leakage detection device and a leak detection gas source device for filling the shut-off valve with detection gas. The leak detection gas source device is connected to the air inlet pipe through a leak detection pipe, and a seventh shut-off valve is provided on the leak detection pipe. The valve internal leakage detection device is used to detect whether the detection gas filled into the shut-off valve is leaking.

[0017] As a further improvement of this utility model, temperature and pressure measuring devices are installed on the air inlet pipe, the air outlet pipe, and the energy storage device.

[0018] As a further improvement of this utility model, the shut-off valve is equipped with multiple temperature measuring devices, which are respectively arranged on the valve body, valve cover, bolts, middle flange, packing, valve stem and electric actuator of the shut-off valve.

[0019] The beneficial effects of this utility model are:

[0020] 1. This utility model provides a nuclear-grade high-temperature shut-off valve test device. By using a process room simulation device, it can accurately simulate the environment of the actual installation process room of the shut-off valve and can realistically reproduce different working conditions such as normal ventilation and emergency ventilation. It can comprehensively test the characteristics of the shut-off valve under various actual operating conditions, so that the test results are closer to the real performance of the shut-off valve in nuclear facilities, and provide a reliable basis for evaluating the actual application performance of the shut-off valve.

[0021] 2. The test medium supply system adopted in this utility model can be flexibly adjusted according to the steam flow requirements of different tests. This steam supply method can not only meet the special requirements of different tests for steam flow and reach the actual operating temperature of the existing nuclear-grade high-temperature shut-off valves in new-type and new-domain reactors, but also more accurately verify the reliability of the shut-off valves in long-term operation under high-temperature environments. It can also ensure the stability of steam supply, providing a solid guarantee for the smooth progress of various tests and effectively improving the accuracy and reliability of test results. At the same time, the internal heating method is adopted as the heat source scheme, and the heat is transferred from the inside of the shut-off valve to the outside. Compared with the external heating test device commonly used in the industry, it is closer to the actual heat transfer method of nuclear-grade high-temperature shut-off valves in nuclear facilities.

[0022] 3. This utility model, by setting up a process simulation device, a test medium supply system, and process pipelines, can conduct various key performance tests on high-temperature shut-off valves, such as high-temperature operating performance tests, sealing performance tests, thermal shock tests, and cycle life tests. It can meet the multi-faceted performance testing needs of nuclear-grade high-temperature shut-off valves in one stop. Through the systematic test process design, it can comprehensively evaluate the performance of valves under different operating conditions, promptly identify potential performance defects of valves, and provide strong support for valve optimization design and quality improvement.

[0023] 4. This utility model, by arranging temperature measuring devices in the critical temperature-sensitive areas of the shut-off valve, can measure the actual temperature values ​​of these parts in real time during high-temperature testing. This helps to gain a deeper understanding of the temperature distribution of each component of the shut-off valve under high-temperature conditions, providing important data support for evaluating the thermal performance of the shut-off valve and ensuring its reliable operation in high-temperature environments. At the same time, based on this data, the structure, materials, and sealing methods of the shut-off valve can be optimized and improved in a targeted manner to enhance its adaptability, reliability, and safety in complex environments, ensuring that the shut-off valve can operate stably and efficiently under various possible process environment conditions. Attached Figure Description

[0024] To more clearly illustrate the technical solutions of the embodiments of this application, the drawings used in the embodiments will be briefly introduced below. Obviously, the drawings described below are only some embodiments of this application. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0025] Figure 1 This is a schematic diagram of the structure of the nuclear-grade high-temperature shut-off valve test device of this utility model;

[0026] Figure 2 This is a cross-sectional view of the shut-off valve to be tested according to this utility model.

[0027] Referring to the accompanying drawings, the following explanations are provided:

[0028] 1. Shut-off valve; 101. Valve body; 102. Valve cover; 103. Bolt; 104. Middle flange; 105. Packing; 106. Valve stem; 107. Electric actuator; 2. Process room simulation device; 201. Cold air inlet pipe; 202. Cold air outlet pipe; 203. Insulation device; 3. Air inlet pipe; 4. Air outlet pipe; 5. Steam generator; 6. Energy storage device; 7. Cooling fan; 8. Ventilation valve; 9. First output pipe; 10. 11. Energy storage pipeline; 12. Second output pipeline; 13. Bypass pipeline; 14. Valve internal leakage detection device; 15. Leak detection gas source device; 16. Leak detection pipeline; 17. Temperature and pressure measuring device; 18. Exhaust pipeline; a. First shut-off valve; b. Second shut-off valve; c. Third shut-off valve; d. Fourth shut-off valve; e. Fifth shut-off valve; f. Sixth shut-off valve; g. Seventh shut-off valve; h. Eighth shut-off valve; i. Ninth shut-off valve; j. Tenth shut-off valve. Detailed Implementation

[0029] The present application will now be described in detail with reference to the accompanying drawings and specific embodiments.

[0030] The following specific examples illustrate the implementation of this application. Those skilled in the art can easily understand other advantages and effects of this application from the content disclosed in this specification. Obviously, the described embodiments are only a part of the embodiments of this application, and not all of them. This application can also be implemented or applied through other different specific embodiments, and the details in this specification can also be modified or changed based on different viewpoints and applications without departing from the spirit of this application. It should be noted that, in the absence of conflict, the following embodiments and features in the embodiments can be combined with each other. Based on the embodiments in this application, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of this application.

[0031] It should be noted that various aspects of embodiments within the scope of the appended claims are described below. It will be apparent that the aspects described herein can be embodied in a wide variety of forms, and any particular structure and / or function described herein is merely illustrative. Based on this application, those skilled in the art will understand that one aspect described herein can be implemented independently of any other aspect, and two or more of these aspects can be combined in various ways. For example, any number and aspects set forth herein can be used to implement the device and / or practice the method. Additionally, this device and / or method can be implemented using structures and / or functionalities other than one or more of the aspects set forth herein.

[0032] It should also be noted that the illustrations provided in the following embodiments are only schematic representations of the basic concept of this application. The illustrations only show the components related to this application and are not drawn according to the number, shape and size of the components in actual implementation. In actual implementation, the form, quantity and proportion of each component can be arbitrarily changed, and the layout of the components may also be more complex.

[0033] Additionally, specific details are provided in the following description to facilitate a thorough understanding of the examples. However, those skilled in the art will understand that practice can be carried out without these specific details.

[0034] The technical solutions provided by the various embodiments of this application are described below with reference to the accompanying drawings.

[0035] See Figure 1 and Figure 2 This utility model provides a nuclear-grade high-temperature shut-off valve testing device for testing shut-off valve 1, which includes: a process room simulation device 2, a test medium supply system, and a leak detection system.

[0036] Among them, the process room simulation device 2 can construct an environment similar to the actual installation process room of the nuclear-grade high-temperature shut-off valve 1, including but not limited to the internal structural form, size specifications and placement position of the shut-off valve 1. By accurately restoring the actual spatial conditions of the shut-off valve 1, the test environment is closer to the real use scenario, thereby ensuring that the test results can accurately reflect the performance of the shut-off valve 1 under actual working conditions.

[0037] like Figure 1 As shown, the shut-off valve 1 is housed in the process room simulation device 2, and the left and right ends of the shut-off valve 1 are respectively connected to the air inlet pipe 3 and the air outlet pipe 4. The test medium supply system is connected to the shut-off valve 1 through the air inlet pipe 3.

[0038] In this invention, the test medium supply system includes a steam generator 5 and an energy storage device 6 connected to the steam generator 5. The energy storage device 6 is capable of storing the steam supplied to it by the steam generator 5. Both the steam generator 5 and the energy storage device 6 are used to supply steam to the shut-off valve 1 through the air inlet pipe 3.

[0039] During the test, the steam flow rate can be flexibly adjusted according to the different test requirements. When conducting high-temperature performance tests, the required steam volume is small, and the steam generator 5 can directly supply the steam test medium. When conducting large-displacement steam tests such as thermal shock tests and cycle life tests, the steam generator 5 first supplies steam to the storage tank 6. When there is enough medium, the storage tank 6 supplies steam to the test station, i.e., the shut-off valve 1. This steam supply method can not only meet the special requirements of different tests for steam flow rate and reach the actual operating temperature of the existing new-type new-domain reactor nuclear-grade high-temperature shut-off valve 1, more accurately verifying the reliability of the shut-off valve 1 in long-term operation under high-temperature environment, but also ensure the stability of steam supply, providing a solid guarantee for the smooth progress of various tests and effectively improving the accuracy and reliability of test results.

[0040] Furthermore, the nuclear-grade high-temperature shut-off valve test device of this utility model adopts an internal heating method as the heat source scheme, with heat transferred from the inside of the shut-off valve 1 to the outside. Compared with the external heating test device commonly used in the industry, it is closer to the actual heat transfer method of the nuclear-grade high-temperature shut-off valve 1 in nuclear facilities.

[0041] For example, the steam generating device 5 may be a flash boiler.

[0042] In this invention, the steam generator 5 is connected to the air inlet pipe 3 through the first output pipe 9, and the energy storage device 6 is connected to the air inlet pipe 3 through the energy storage pipe 10 and the second output pipe 11. Thus, the steam generator 5 can deliver steam to the energy storage device 6 through the first output pipe 9, a partial section of the air inlet pipe 3, and the energy storage pipe 10, and the steam stored in the energy storage device 6 can also be delivered to the shut-off valve 1 through the second output pipe 11 and the air inlet pipe 3.

[0043] The first output pipe 9 is equipped with a first shut-off valve a, and the energy storage pipe 10 is equipped with a second shut-off valve b.

[0044] In addition, both the steam generator 5 and the accumulator 6 are equipped with safety valves, and the accumulator 6 is also equipped with a drain valve to discharge condensate during the test; at the same time, a check valve is installed between the steam generator 5 and the accumulator 6 to prevent steam backflow.

[0045] It is worth mentioning that the process room simulation device 2 is equipped with a cold air inlet pipe 201 and a cold air outlet pipe 202. The cold air inlet pipe 201 is connected to a cooling fan 7 and is equipped with a check valve. The cold air outlet pipe 202 is equipped with a ventilation valve 8. When the ventilation valve 8 is opened, the cold air input into the process room simulation device 2 by the cooling fan 7 through the cold air inlet pipe 201 can be discharged outward through the cold air outlet pipe 202. By adopting this structural design, this utility model enables the process room simulation device 2 to simulate the environment of the actual process room where the shut-off valve 1 is installed and the changes in ambient temperature during the operation of the shut-off valve 1, so as to verify the actual operating characteristics of the shut-off valve 1 under different operating conditions such as normal ventilation and emergency ventilation.

[0046] Normal ventilation simulation: Cooling fan 7 and ventilation valve 8 are turned on to simulate the operating characteristics of shut-off valve 1 under normal ventilation conditions in the process room. Under this condition, it is possible to test whether the various performance indicators of shut-off valve 1 meet the requirements under normal heat dissipation conditions, such as temperature distribution, operational stability, and sealing performance, to ensure the reliability of shut-off valve 1 in normal operating environments.

[0047] Simulation of accident ventilation conditions: Cooling fan 7 and ventilation valve 8 are shut down to simulate an accident condition in which the heat dissipation conditions of the process room are lost. This helps to test the operating characteristics of shut-off valve 1 under extreme conditions, such as ventilation system failure, and to evaluate the tolerance, performance changes and potential safety risks of shut-off valve 1 in high temperature accumulation environment, so as to provide data support for ensuring the safety of nuclear facilities in accident conditions.

[0048] In addition, the process simulation device 2 is equipped with a heat preservation device 203. The heat preservation device 203 can effectively reduce the heat exchange between the process simulation device 2 and the external environment, and keep the internal temperature of the device stable at the set value required to simulate the actual working conditions, so as to make the test results more realistic and reliable.

[0049] As can be seen, the process room simulation device 2 of the nuclear-grade high-temperature shut-off valve test apparatus of this utility model consists of an outer process room simulation device, an insulation device 203, a cooling fan 7, and a ventilation valve 8. It can accurately simulate the environment of the actual installation process room of the shut-off valve 1 and the changes in ambient temperature during valve operation. By controlling the opening and closing of the cooling fan 7 and the ventilation valve 8, it can realistically reproduce different operating conditions such as normal ventilation and emergency ventilation, comprehensively test the characteristics of the shut-off valve 1 under various actual operating conditions, and make the test results closer to the real performance of the shut-off valve 1 in nuclear facilities, providing a reliable basis for evaluating the actual application performance of the shut-off valve 1.

[0050] In this utility model, one or more shut-off valves are provided on both the air inlet pipe 3 and the air outlet pipe 4, so as to control the corresponding shut-off valves to perform various tests on the shut-off valve 1.

[0051] Specifically, such as Figure 1 As shown, from left to right, the intake pipe 3 is equipped with a third shut-off valve c, a fourth shut-off valve d, and a fifth shut-off valve e. The third shut-off valve c is located in the section between the intake pipe 3 and the energy storage pipe 10 and the second output pipe 11. From left to right, the exhaust pipe 4 is equipped with a ninth shut-off valve i and a tenth shut-off valve j.

[0052] It is worth mentioning that the nuclear-grade high-temperature shut-off valve test device of this utility model also includes a bypass pipe 12, with its two ends connected to the inlet pipe 3 and the outlet pipe 4, respectively, and an eighth shut-off valve h is installed on the bypass pipe 12. Specifically, the end of the bypass pipe 12 connected to the inlet pipe 3 is located between the fourth shut-off valve d and the fifth shut-off valve e, and the other end of the bypass pipe 12 connected to the outlet pipe 4 is located between the ninth shut-off valve i and the tenth shut-off valve j. By providing the bypass pipe 12, this utility model can be used to preheat the pipes before and after the test station, namely the inlet pipe 3 and the outlet pipe 4, to conduct high-temperature thermal shock tests.

[0053] Furthermore, this utility model also includes a leak detection system, which is used to detect whether there is a leak in the shut-off valve 1. After the shut-off valve 1 has undergone a high-temperature test, the leak detection is performed on the shut-off valve 1 to verify its sealing performance during long-term operation in a high-temperature environment.

[0054] In this invention, the leak detection system includes a valve internal leakage detection device 13 and a leak detection gas source device 14 for introducing detection gas into the shut-off valve 1. The leak detection gas source device 14 is connected to the air inlet pipe 3 via a leak detection pipe 15, and a seventh shut-off valve g is installed on the leak detection pipe 15. The valve internal leakage detection device 13 is used to detect whether the detection gas introduced into the shut-off valve 1 is leaking.

[0055] For example, the leak detection gas source device 14 can be a helium cylinder, and the valve internal leakage detection device 13 is a helium leak detection device. By bringing the detection head of the valve internal leakage detection device 13 close to the middle flange 104 of the cut-off valve 1, it is possible to detect whether there is a helium leak.

[0056] Furthermore, the nuclear-grade high-temperature shut-off valve testing device of this utility model also includes an exhaust pipe 17 connected to the inlet pipe 3. One end of the exhaust pipe 17 connected to the inlet pipe 3 is located between the fifth shut-off valve e and the shut-off valve 1, and a sixth shut-off valve f is provided on the exhaust pipe 17. The exhaust pipe 17 is used to discharge the high-temperature steam inside the shut-off valve 1, so as to facilitate the sealing performance test of the shut-off valve 1, that is, to detect leaks in the shut-off valve 1 through a leak detection system.

[0057] In this utility model, temperature and pressure measuring devices 16 are installed on the inlet pipe 3, the outlet pipe 4 and the energy storage device 6, which can monitor the steam parameters of the high-temperature test medium in real time to ensure that they always meet the test conditions. This not only helps to accurately grasp the state of the steam during the test and ensure the accuracy and reliability of the test, but also simulates the temperature and pressure changes faced by the shut-off valve 1 in actual operation, and comprehensively evaluates the performance of the shut-off valve 1 under different steam parameters.

[0058] The temperature and pressure measuring device 16 consists of a temperature gauge and a pressure gauge.

[0059] See Figure 2 The shut-off valve 1 is equipped with multiple temperature measuring devices (such as temperature sensors, not shown in the figure). These devices are respectively arranged on the valve body 101, valve cover 102, bolts 103, middle flange 104, packing 105, valve stem 106, and electric actuator 107 of the shut-off valve 1. By arranging the temperature measuring devices in the key temperature-sensitive areas of the shut-off valve 1, this invention can measure the actual temperature values ​​of these parts in real time during high-temperature testing. This helps to gain a deeper understanding of the temperature distribution of each component of the shut-off valve 1 under high-temperature conditions, providing important data support for evaluating the thermal performance of the shut-off valve 1 and ensuring its reliable operation in high-temperature environments. Furthermore, based on this data, the structure, materials, and sealing methods of the shut-off valve 1 can be optimized and improved in a targeted manner to enhance its adaptability, reliability, and safety in complex environments, ensuring stable and efficient operation of the shut-off valve 1 under various possible process environment conditions.

[0060] The specific test procedure for this nuclear-grade high-temperature shut-off valve test device is described below.

[0061] Steam preparation: Open the first shut-off valve a, and the steam generator 5 will produce steam to supply the steam medium to the energy storage tank 6 and the shut-off valve 1 respectively. During small flow tests, close the second shut-off valve b, and the steam generated by the steam generator 5 will directly enter the process pipeline of the test loop through the third shut-off valve c; during large flow tests (such as cycle life tests and thermal shock tests), close the third shut-off valve c, open the second shut-off valve b, and when the steam quantity is sufficient, open the fourth shut-off valve d to supply test steam to the shut-off valve 1.

[0062] Pipeline preheating: Close the eighth shut-off valve h, the sixth shut-off valve f and the seventh shut-off valve g, open the fourth shut-off valve d, the fifth shut-off valve e and the ninth shut-off valve i, let the steam pass through the cut-off valve 1 from the inlet pipe 3, and then open the tenth shut-off valve j to vent, and slowly heat the entire test pipeline to the test temperature.

[0063] High-temperature operating performance test: After the test pipeline is heated to the test temperature, close the tenth shut-off valve j to stop venting, and carry out the high-temperature operating performance test on the shut-off valve 1 according to the test procedure.

[0064] Cyclic life test: After the test pipeline reaches the test temperature, close the tenth shut-off valve j to stop venting. Following the test procedure, allow shut-off valve 1 to perform the specified number of actions at high temperature. Then, close the fifth shut-off valve e and simultaneously open the ninth shut-off valve i and the tenth shut-off valve j to discharge high-temperature steam. Once shut-off valve 1 cools to room temperature, allow it to perform the specified number of actions at high temperature again, following the test procedure. This constitutes one cycle. Repeat the above cycle according to the test procedure to conduct a cyclic life test on shut-off valve 1.

[0065] Thermal shock test: Before the pipeline is preheated, close the fifth shut-off valve e and the ninth shut-off valve i before and after the test station (shut-off valve 1), open the eighth shut-off valve h, slowly heat the pipeline before and after the test station to the test temperature, close the eighth shut-off valve h, open the fifth shut-off valve e and the ninth shut-off valve i before and after the test station, and carry out a high temperature thermal shock test on the cold shut-off valve 1.

[0066] Sealing performance test: After the aforementioned high temperature performance test, cycle life test or thermal shock test, close the fifth shut-off valve e, the seventh shut-off valve g and the ninth shut-off valve i before and after the test station, open the sixth shut-off valve f, and discharge the high temperature steam in the shut-off valve 1. Then close the sixth shut-off valve f and open the seventh shut-off valve g. Fill the shut-off valve 1 with helium gas through the leak detection gas source device 14, i.e., the helium cylinder, and perform helium leak detection on the shut-off valve 1 through the valve internal leakage detection device 13 to verify its sealing performance.

[0067] The above description is merely a specific embodiment of this application, but the scope of protection of this application is not limited thereto. Any variations or substitutions that can be easily conceived by those skilled in the art within the technical scope disclosed in this application should be included within the scope of protection of this application. Therefore, the scope of protection of this application should be determined by the scope of the claims.

Claims

1. A test device for a nuclear class high temperature block valve, characterized in that, The utility model relates to a kind of process simulation device (2) for building out similar environment with actual installation process room of intercept valve (1), the intercept valve (1) is housed in the process simulation device (2), and the two ends of the intercept valve (1) are connected with inlet pipe (3) and outlet pipe (4) respectively. Test medium supply system connected to the intercept valve (1) through the inlet pipe (3), the test medium supply system includes steam generating device (5) and energy storage (6) connected with the steam generating device (5), the energy storage (6) can store steam delivered to it by the steam generating device (5), the steam generating device (5) and the energy storage (6) are used to supply steam to the intercept valve (1) through the inlet pipe (3). And leak detection system for detecting whether the intercept valve (1) has leakage condition. Wherein, one to more stop valves are provided on the inlet pipe (3) and the outlet pipe (4). The process simulation device (2) is provided with cold air inlet pipe (201) and cold air outlet pipe (202), the cold air inlet pipe (201) is connected with cooling fan (7), and the cold air outlet pipe (202) is provided with ventilation valve (8), when the ventilation valve (8) is opened, the cooling fan (7) can output the cold air in the process simulation device (2) to the outside through the cold air outlet pipe (202) by the cold air inlet pipe (201).

2. The nuclear class high temperature block valve testing apparatus of claim 1, wherein: The inside of the process simulation device (2) is provided with heat preservation device (203).

3. The nuclear class high temperature block valve testing apparatus of claim 1, wherein: The steam generating device (5) is connected to the inlet pipe (3) through first output pipe (9), and the first output pipe (9) is provided with first stop valve (a);The energy storage (6) is connected to the inlet pipe (3) through energy storage pipe (10) and second output pipe (11), and the energy storage pipe (10) is provided with second stop valve (b), and the section between the inlet pipe (3) and the connection node of the energy storage pipe (10) and the second output pipe (11) is provided with third stop valve (c).

4. The nuclear class high temperature block valve testing apparatus of claim 1, wherein: It also includes bypass pipe (12), the two ends of the bypass pipe (12) are connected to the inlet pipe (3) and the outlet pipe (4) respectively, and the bypass pipe (12) is provided with eighth stop valve (h).

5. The nuclear class high temperature block valve testing apparatus of claim 1, wherein: The fourth stop valve (d) and the fifth stop valve (e) are provided on the inlet pipe (3), and the end of the bypass pipe (12) connected with the inlet pipe (3) is between the fourth stop valve (d) and the fifth stop valve (e);The ninth stop valve (i) and the tenth stop valve (j) are provided on the outlet pipe (4), and the other end of the bypass pipe (12) connected with the outlet pipe (4) is between the ninth stop valve (i) and the tenth stop valve (j).

6. The nuclear class high temperature block valve testing apparatus of claim 5, wherein: ​ 7. The nuclear class high temperature block valve testing apparatus of claim 6, wherein: An exhaust pipeline (17) is connected to the air inlet pipeline (3), and the exhaust pipeline (17) is connected to the air inlet pipeline (3) at a position between the fifth stop valve (e) and the cutoff valve (1), and a sixth stop valve (f) is arranged on the exhaust pipeline (17).

8. The nuclear class high temperature block valve testing apparatus of claim 1, wherein: The leak detection system comprises a valve internal leakage detection device (13) and a leak detection gas source device (14) for filling the cutoff valve (1) with detection gas, the leak detection gas source device (14) is connected to the air inlet pipeline (3) through a leak detection pipeline (15), and a seventh stop valve (g) is arranged on the leak detection pipeline (15); the valve internal leakage detection device (13) is used for detecting whether the detection gas filled in the cutoff valve (1) leaks.

9. The nuclear class high temperature block valve testing apparatus of claim 4, wherein: Temperature pressure measuring devices (16) are arranged on the air inlet pipeline (3), the air outlet pipeline (4) and the energy accumulator (6).

10. The nuclear class high temperature block valve testing apparatus of claim 1, wherein: A plurality of temperature measuring devices are arranged on the cutoff valve (1), and the plurality of temperature measuring devices are arranged on a valve body (101), a valve cover (102), a bolt (103), a middle flange (104), a packing (105), a valve stem (106) and an electric actuator (107) of the cutoff valve (1) respectively.

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