Nuclear engineering hydraulic valve test bench
The automated loading, unloading, and sealing mechanisms enable fully automated operation of hydraulic valves in nuclear engineering, solving the problems of time-consuming, labor-intensive, and safety hazards associated with manual operation in existing technologies. This improves efficiency and safety and meets the sealing requirements of high-pressure tests in nuclear engineering.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- SOUTHWEAT UNIV OF SCI & TECH
- Filing Date
- 2025-10-22
- Publication Date
- 2026-07-21
AI Technical Summary
In existing technologies, valve loading, unloading, and positioning require manual operation, which makes the operation of hydraulic valves in nuclear engineering time-consuming, labor-intensive, inefficient, and poses safety hazards, especially for heavy precision components and low-radiation risks.
The system employs an automatic loading and unloading mechanism, auxiliary mechanisms, and a power mechanism to achieve fully automated operation of the hydraulic valves. Combined with an annular airbag automatic sealing system, it ensures sealing performance and safety.
It has enabled fully automated testing of hydraulic valves for nuclear engineering, improving testing efficiency by more than 40%, reducing safety risks, ensuring sealing accuracy and testing stability, and meeting the sealing requirements of high-pressure testing in nuclear engineering.
Smart Images

Figure CN224535407U_ABST
Abstract
Description
Technical Field
[0001] This application relates to the field of nuclear engineering technology, and in particular to a test bench for nuclear engineering hydraulic valves. Background Technology
[0002] The hydraulic valve test bench is suitable for pressure performance testing of the sealing and valve body strength of straight-through flange connection type valves. It is mainly used to ensure the reliable sealing quality of newly produced valves and valves after maintenance. The test bench can perform shell tests, top seal tests, and high-pressure water seal tests on valves. During the testing process, it is convenient to visually inspect the workpiece for leakage.
[0003] Publication (Announcement) No.: CN222866214U provides a test bench for nuclear engineering hydraulic valves. This utility model relates to the field of valve testing technology, including a base, on which a test cylinder is fixedly installed. A valve pipe and a booster pump group are respectively installed through both ends of the test cylinder, and a test chamber is connected between the valve pipe and the booster pump group. A valve port is formed through the valve pipe, and a sealing ring is provided around the end of the valve port. Multiple clamps are arranged in a ring on the sealing ring, and clips are slidably fitted on the clamps. A flange frame is provided adjacent to the outer end of the valve pipe. The beneficial effect of this utility model is that, considering the testing requirements of nuclear engineering hydraulic valves, the flange frame with internal and external settings and the sealing ring and clamps in the valve port are used to meet the airtightness requirements of valve body and valve port docking under multiple pressure output test processes. The reserved test chamber ensures the safety of the transition between the booster pump group and the test valve body, thus improving the practicality of the test bench.
[0004] In existing technologies, valve loading, unloading, and positioning require manual operation. However, hydraulic valves in nuclear engineering are mostly heavy and precision components, and some may carry low-level radiation risks. Manual operation is not only time-consuming, labor-intensive, and inefficient, but also prone to safety hazards due to close contact. Utility Model Content
[0005] The purpose of this utility model is to solve the problem that the loading, unloading and positioning of valves in the existing technology requires manual operation. Since most of the hydraulic valves in nuclear engineering are heavy precision parts, and some may have low radiation risks, manual operation is not only time-consuming and labor-intensive and inefficient, but also prone to safety hazards due to close contact. Therefore, a test bench for nuclear engineering hydraulic valves is proposed.
[0006] The nuclear engineering hydraulic valve test bench provided in this application adopts the following technical solution: A test bench for hydraulic valves in nuclear engineering, comprising: The base has support legs at each of its four bottom corners. A bracket 1 and a bracket 2 are fixedly installed on the top left and right sides of the base, respectively. A test cylinder is fixedly installed on the right side of bracket 1. A booster pump assembly is fixedly installed inside the left side of the test cylinder. The base also includes: A U-shaped bracket is installed at the top of the base; An automatic loading and unloading mechanism is located on the left side of bracket two and is used for loading and unloading hydraulic valves. The auxiliary mechanism, located inside the U-shaped bracket, is used to transmit power to the hydraulic valves. A sealing mechanism, located inside the test cylinder, is used to maintain the airtightness of the test. The power mechanism, located on the automatic loading and unloading mechanism, is used to drive the sealing mechanism.
[0007] Furthermore, the automatic loading and unloading mechanism includes a hydraulic cylinder located on the left side of the support frame two. A pressure plate is fixedly connected to the output end of the hydraulic cylinder, and a push plate is slidably connected to the outer side of the pressure plate. Multiple springs are fixedly connected between the push plate and the pressure plate.
[0008] Furthermore, the auxiliary mechanism includes two conveyor wheels rotatably disposed on the front and rear sides inside the U-shaped bracket. The two conveyor wheels are connected to the same conveyor belt. Multiple pads are fixedly installed on the top of the conveyor belt. Placement blocks are fixedly installed on the top of each pad. Placement slots are opened on the top of each placement block. A motor is installed at the front right side of the U-shaped bracket. The output shaft of the motor is fixedly connected to the conveyor wheel located at the front side.
[0009] Furthermore, the sealing mechanism includes an airbag disposed inside the test cylinder, a sealing cavity is provided on the top side inside the test cylinder, a sealing plate is slidably connected inside the sealing cavity, a screw is rotatably connected inside the sealing cavity, the screw is threadedly connected to the sealing plate, and an air tube is fixedly connected between the bottom left side of the sealing cavity and the airbag.
[0010] Furthermore, the power mechanism includes a slider disposed on the top of the pressure plate, the slider sliding on the inner top side of the push plate, a rack fixedly installed on the top of the slider, the rack meshing with a gear, a rotating column fixedly installed on the gear, the rotating column being rotatably connected to the push plate, and a bevel gear fixedly installed on the outer surface of the rotating column.
[0011] Furthermore, the first bevel gear is meshed with a second bevel gear, the top of the second bevel gear is fixedly mounted with a second rotating column, the top of the push plate is fixedly mounted with a fixing block, and the top of the second bracket and the test cylinder are fixedly connected with the same U-shaped protective block, and the fixing block and the U-shaped protective block are slidably connected.
[0012] Furthermore, the rotating column two rotates inside the fixed block, and a bevel gear three is fixedly connected to the top of the rotating column two. The bevel gear three meshes with a bevel gear four, and the left end of the bevel gear four is fixedly connected to the rotating column three. The rotating column three is rotatably connected to the fixed block and the U-shaped protective block.
[0013] Furthermore, a bevel gear five is fixedly installed on the left end of the rotating column three, and a bevel gear six is meshed with the bevel gear five. A rotating column four is fixedly installed on the bevel gear six. The rotating column four is rotatably connected to the U-shaped protective block and the sealing cavity. A bevel gear seven is fixedly connected to the bottom end of the rotating column four. A bevel gear eight is meshed with the bevel gear seven. The bevel gear eight is fixedly connected to the screw.
[0014] In summary, this application includes at least one of the following beneficial technical effects: 1. This solution achieves fully automated testing of hydraulic valves in nuclear engineering, significantly improving efficiency and reducing safety risks. Through the collaboration of auxiliary mechanisms and automatic loading and unloading mechanisms, this solution automates the valve loading, transmission, precise positioning, and clamping operations, eliminating the need for manual handling of heavy nuclear valves weighing tens of kilograms or close contact with low-radiation valves. Compared with existing manual operations, testing efficiency is increased by more than 40%, while avoiding the hidden dangers of valve deformation and radiation contact caused by unstable manual clamping, thus balancing efficiency and nuclear-grade safety. 2. This solution uses a nuclear-grade high-reliability automatic sealing system to ensure test accuracy and stability: This solution adopts an annular airbag, which fits the valve flange and sealing plate inflation structure, and works with an airbag pressure sensor to monitor the sealing pressure in real time to ensure a gapless seal; it solves the problems of low accuracy and easy pressure leakage in existing manual sealing technology, and meets the sealing requirements of 0-25MPa for high-pressure tests in nuclear engineering.
[0015] This invention enables fully automated operation of hydraulic valves in nuclear engineering. Combined with a power-driven annular airbag automatic sealing system, sealing can be completed without manual intervention, greatly improving work efficiency and safety. Attached Figure Description
[0016] Figure 1 This is a schematic diagram of the structure of a nuclear engineering hydraulic valve test bench proposed in this utility model; Figure 2 This is a cross-sectional structural diagram of a nuclear engineering hydraulic valve test bench proposed in this utility model; Figure 3 This is a schematic diagram of the reciprocating screw structure of a nuclear engineering hydraulic valve test bench proposed in this utility model; Figure 4 This utility model proposes a test bench for nuclear engineering hydraulic valves. Figure 2 Enlarged structural diagram of section A; Figure 5 This utility model proposes a test bench for nuclear engineering hydraulic valves. Figure 2 Enlarged structural diagram of section B; Figure 6 This utility model proposes a test bench for nuclear engineering hydraulic valves. Figure 2 Enlarged structural diagram of section C; Figure 7 This utility model proposes a test bench for nuclear engineering hydraulic valves. Figure 2 Enlarged structural diagram of section D.
[0017] Reference numerals: 1. Base; 2. Support leg; 3. Bracket 1; 4. Bracket 2; 5. Test cylinder; 6. Booster pump set; 7. Leakage monitoring sensor; 8. U-shaped bracket; 9. Conveyor wheel; 10. Conveyor belt; 11. Placement block; 12. Motor 1; 13. Hydraulic cylinder; 14. Push plate; 15. Pressure plate; 16. Spring; 17. Clamping plate; 18. U-shaped protective block; 19. Motor 2; 20. Reciprocating screw; 21. Moving plate; 22. Sealing cavity; 23. Airbag; 24. Screw; 25. Sealing plate; 26. Slider; 27. Rack; 28. Gear; 29. Rotating column one; 30. Bevel gear one; 31. Bevel gear two; 32. Rotating column two; 33. Bevel gear three; 34. Bevel gear four; 35. Rotating column three; 36. Bevel gear five; 37. Bevel gear six; 38. Rotating column four; 39. Bevel gear seven; 40. Bevel gear eight. Detailed Implementation
[0018] The technical solutions of the present utility model will be clearly and completely described below with reference to the accompanying drawings of the embodiments of the present utility model. Obviously, the described embodiments are only some embodiments of the present utility model, and not all embodiments.
[0019] Example 1 Reference Figures 1-7 A nuclear engineering hydraulic valve test bench includes: a base 1, with support legs 2 at each of the four corners of the bottom of the base 1; bracket 3 and bracket 4 fixedly installed on the top left and right sides of the base 1, respectively; a test cylinder 5 fixedly installed on the right side of bracket 3; a leakage monitoring sensor 7 installed on the inner wall of the test cylinder 5; a booster pump assembly 6 fixedly installed on the left side inside the test cylinder 5; and a nuclear-grade high-pressure sensor, model PX409-30MPaG, on the outlet pipe of the booster pump assembly 6, capable of real-time monitoring of the test pressure. The test bench also includes: U-shaped bracket 8 is set on top of base 1; An automatic loading and unloading mechanism is located on the left side of bracket 24 and is used for loading and unloading hydraulic valves. The auxiliary mechanism, located inside the U-shaped bracket 8, is used to transmit power to the hydraulic valves. A sealing mechanism, located inside the test cylinder 5, is used to maintain the airtightness of the test. The power mechanism, located on the automatic loading and unloading mechanism, is used to drive the sealing mechanism.
[0020] Reference Figures 1-3 The automatic loading and unloading mechanism includes a hydraulic cylinder 13 located on the left side of the support frame 2 4. A pressure plate 15 is fixedly connected to the output end of the hydraulic cylinder 13. A push plate 14 is slidably connected to the outer side of the pressure plate 15. Multiple springs 16 are fixedly connected between the push plate 14 and the pressure plate 15. A motor 2 19 is fixedly installed on the front left side inside the push plate 14. A reciprocating screw 20 is fixedly installed on the output shaft of the motor 2 19. The reciprocating screw 20 is rotatably connected to the push plate 14. Two moving plates 21 are threadedly connected to the reciprocating screw 20. The two moving plates 21 are slidably connected to the push plate 14. Next, clamping plates 17 are fixedly connected to the left side of both moving plates 21. Clamping force pressure sensors are set on the side of the clamping plates 17 that are close to each other. The reciprocating screw 20 is composed of two threaded rods with opposite threads. These two threaded rods with opposite threads enable the two moving plates 21 to move inward or outward at the same time, thereby realizing the clamping or releasing action of the clamping plates 17 on the hydraulic valve. It can also ensure that the two clamping plates 17 move the same distance, ensuring that the hydraulic valve is in a stable position during the test and avoiding the impact of unstable clamping on the accuracy of the test results.
[0021] Reference Figure 2 The auxiliary mechanism includes two conveyor wheels 9 rotatably disposed on the front and rear sides inside the U-shaped bracket 8. The same conveyor belt 10 is connected to the two conveyor wheels 9. Multiple pads are fixedly installed on the top of the conveyor belt 10. Placement blocks 11 are fixedly installed on the top of each of the multiple pads. Placement slots are opened on the top of the placement blocks 11. A motor 12 is installed at the front right side of the U-shaped bracket 8. The output shaft of the motor 12 is fixedly connected to the conveyor wheel 9 located on the front side.
[0022] Reference Figure 2 and Figure 6 The sealing mechanism includes an airbag 23 disposed inside the test cylinder 5. A sealing cavity 22 is provided on the top side of the inside of the test cylinder 5. A sealing plate 25 is slidably connected inside the sealing cavity 22. A screw 24 is rotatably connected inside the sealing cavity 22. The screw 24 is threadedly connected to the sealing plate 25. An air tube is fixedly connected between the bottom left side of the sealing cavity 22 and the airbag 23. The airbag 23 has a ring structure and is coaxially sleeved at the valve interface inside the test cylinder 5. The inner side of the airbag fits against the outer edge of the hydraulic valve flange to ensure that it can wrap the flange sealing surface after inflation. An airbag pressure sensor is provided at the inflation port of the airbag 23.
[0023] Reference Figure 2 and Figures 4-7The power mechanism includes a slider 26 mounted on the top of the pressure plate 15. The slider 26 slides on the inner top side of the push plate 14. A rack 27 is fixedly mounted on the top of the slider 26. The rack 27 is meshed with a gear 28. A rotating column 29 is fixedly mounted on the gear 28. The rotating column 29 is rotatably connected to the push plate 14. A bevel gear 30 is fixedly mounted on the outer surface of the rotating column 29. A bevel gear 31 is meshed with the bevel gear 30. A rotating column 32 is fixedly mounted on the top of the bevel gear 31. A fixing block is fixedly mounted on the top of the push plate 14. The same U-shaped protective block 18 is fixedly connected to the top of the bracket 2 4 and the test cylinder 5. The fixing block and the U-shaped protective block 18 are slidably connected. The rotating column 32 rotates inside the fixing block. A bevel gear 33 is fixedly connected to the top of the rotating column 32. A bevel gear 33 is meshed with a bevel gear 4 34. A rotating column 35 is fixedly connected to the left end of the bevel gear 4 34. The rotating column 35 is rotatably connected to the fixed block and the U-shaped protective block 18. The rotating column 35 consists of two sections, which are slidably connected to each other. The rightmost end is rotatably connected to the fixed block, and the leftmost end is rotatably connected to the U-shaped protective block 18. A bevel gear 5 36 is fixedly installed on the left end of the rotating column 35. A bevel gear 6 37 is meshed with the bevel gear 5 36. A rotating column 4 38 is fixedly installed on the bevel gear 6 37. The rotating column 4 38 is rotatably connected to the U-shaped protective block 18 and the sealing cavity 22. A bevel gear 7 39 is fixedly connected to the bottom end of the rotating column 4 38. A bevel gear 8 40 is meshed with the bevel gear 7 39. The bevel gear 8 40 is fixedly connected to the screw 24.
[0024] The implementation principle of a nuclear engineering hydraulic valve test bench according to an embodiment of this application is as follows: the hydraulic valve is placed in the placement slot, and then the motor 12 is started. The output shaft of the motor 12 drives the conveyor wheel 9 to rotate, so that the two conveyor wheels 9 can rotate simultaneously through the conveyor belt 10 to transport the hydraulic valve to the appropriate position. Start hydraulic cylinder 13. The output end of hydraulic cylinder 13 pushes pressure plate 15, spring 16, push plate 14, and internal components of push plate 14 to move to the left, so that push plate 14 contacts hydraulic valve. Then start motor 19. The output shaft of motor 19 drives reciprocating screw 20 to rotate, which drives two moving plates 21 to move closer to each other and uses two clamping plates 17 to clamp and fix hydraulic valve. Then continue to start hydraulic cylinder 13 to push hydraulic valve into the test cylinder 5. When hydraulic valve is pushed into the test cylinder 5, it can no longer move. At this time, continue to start hydraulic cylinder 13 to make pressure plate 15 compress spring 16 and move, which drives slider 26 to move to the left, so that rack 27 drives gear 28 to rotate, which drives rotating column 29. Rotating the rotating column 29 causes the bevel gear 30 to rotate, which in turn causes the bevel gear 31 to rotate, which in turn causes the rotating column 32 to rotate, which in turn causes the bevel gear 33 to rotate, which in turn causes the bevel gear 34 to rotate, which in turn causes the rotating column 35 to rotate, which in turn causes the bevel gear 36 to rotate, which in turn causes the bevel gear 37 to rotate, which in turn causes the rotating column 38 to rotate, which in turn causes the bevel gear 39 to rotate, which in turn causes the bevel gear 40 to rotate, which in turn causes the screw 24 to rotate. This causes the sealing plate 25 to move to the left, allowing the air in the sealing cavity 22 to be transmitted through the air pipe to the airbag 23, thus sealing the hydraulic valve. Then, start the booster pump group 6 on the left side of the test cylinder 5 to inject nuclear-grade test medium, such as deionized water or fire-resistant hydraulic oil, into the test cylinder 5; monitor the test pressure in real time through the nuclear-grade high-pressure sensor. When the pressure reaches the set value of 0-25MPa, simulating the actual working conditions of the nuclear facility, the PLC controls the booster pump group 6 to enter the pressure holding state. The pressure holding time is 10-30 minutes, which is adjusted according to the test standard. After the test is completed, start the hydraulic cylinder 13 to move to the right, so that the pressure plate 15 moves to the right and the spring 16 rebounds. At this time, the seal of the airbag 23 can be released. Then, continue to start the hydraulic cylinder 13 to move the hydraulic valve to the placement slot. Then start the motor 19 to rotate in the opposite direction to release the clamp. Then return to the original position.
[0025] Example 2 The difference between this embodiment and Embodiment 1 is that a 1mm thick fluororubber buffer pad, model FKM-70, is pasted on the inner wall of the placement tank to prevent the valve from being damaged by direct collision with the metal tank.
[0026] The above description is only a preferred embodiment of the present utility model, but the protection scope of the present utility model is not limited thereto. Any equivalent substitutions or changes made by those skilled in the art within the technical scope disclosed in the present utility model, based on the technical solution and the inventive concept of the present utility model, should be included within the protection scope of the present utility model.
Claims
1. A test bench for nuclear engineering hydraulic valves, comprising a base (1), characterized in that: The base (1) has support legs (2) at each of its four bottom corners. A bracket (3) and a bracket (4) are fixedly installed on the top left and right sides of the base (1), respectively. A test cylinder (5) is fixedly installed on the right side of the bracket (3). A booster pump assembly (6) is fixedly installed inside the test cylinder (5) on its left side. The base also includes: U-shaped bracket (8) is set on top of base (1); An automatic loading and unloading mechanism is located on the left side of bracket two (4) and is used to load and unload hydraulic valves; An auxiliary mechanism, located inside the U-shaped bracket (8), is used to transmit hydraulic valves; A sealing mechanism is located inside the test cylinder (5) to maintain the airtightness of the test. The power mechanism, located on the automatic loading and unloading mechanism, is used to drive the sealing mechanism.
2. The nuclear engineering hydraulic valve test bench according to claim 1, characterized in that: The automatic loading and unloading mechanism includes a hydraulic cylinder (13) located on the left side of the support (4). The output end of the hydraulic cylinder (13) is fixedly connected to a pressure plate (15). A push plate (14) is slidably connected to the outside of the pressure plate (15). Multiple springs (16) are fixedly connected between the push plate (14) and the pressure plate (15).
3. The nuclear engineering hydraulic valve test bench according to claim 1, characterized in that: The auxiliary mechanism includes two conveyor wheels (9) rotatably disposed on the front and rear sides inside the U-shaped bracket (8). The two conveyor wheels (9) are connected to the same conveyor belt (10). Multiple pads are fixedly installed on the top of the conveyor belt (10). Each pad has a placement block (11) fixedly installed on its top. The placement block (11) has a placement groove on its top. A motor (12) is installed at the front right side of the U-shaped bracket (8). The output shaft of the motor (12) is fixedly connected to the conveyor wheel (9) located on the front side.
4. A nuclear engineering hydraulic valve test bench according to claim 2, characterized in that: The sealing mechanism includes an airbag (23) disposed inside the test cylinder (5). A sealing cavity (22) is provided on the top side inside the test cylinder (5). A sealing plate (25) is slidably connected inside the sealing cavity (22). A screw (24) is rotatably connected inside the sealing cavity (22). The screw (24) is threadedly connected to the sealing plate (25). An air tube is fixedly connected between the bottom left side of the sealing cavity (22) and the airbag (23).
5. A nuclear engineering hydraulic valve test bench according to claim 4, characterized in that: The power mechanism includes a slider (26) disposed on the top of the pressure plate (15). The slider (26) slides on the inner top side of the push plate (14). A rack (27) is fixedly installed on the top of the slider (26). A gear (28) is meshed with the rack (27). A rotating column (29) is fixedly installed on the gear (28). The rotating column (29) is rotatably connected to the push plate (14). A bevel gear (30) is fixedly installed on the outer surface of the rotating column (29).
6. A nuclear engineering hydraulic valve test bench according to claim 5, characterized in that: The first bevel gear (30) is meshed with the second bevel gear (31). The top of the second bevel gear (31) is fixedly mounted with the second rotating column (32). The top of the push plate (14) is fixedly mounted with the fixing block. The top of the second bracket (4) and the test cylinder (5) are fixedly connected with the same U-shaped protective block (18). The fixing block and the U-shaped protective block (18) are slidably connected.
7. A nuclear engineering hydraulic valve test bench according to claim 6, characterized in that: The rotating column 2 (32) rotates inside the fixed block. The top of the rotating column 2 (32) is fixedly connected to the bevel gear 3 (33). The bevel gear 3 (33) is meshed with the bevel gear 4 (34). The left end of the bevel gear 4 (34) is fixedly connected to the rotating column 3 (35). The rotating column 3 (35) is rotatably connected to the fixed block and the U-shaped protective block (18).
8. A nuclear engineering hydraulic valve test bench according to claim 7, characterized in that: A bevel gear five (36) is fixedly installed on the left end of the rotating column three (35). The bevel gear five (36) is meshed with a bevel gear six (37). A rotating column four (38) is fixedly installed on the bevel gear six (37). The rotating column four (38) is rotatably connected to the U-shaped protective block (18) and the sealing cavity (22). A bevel gear seven (39) is fixedly connected to the bottom end of the rotating column four (38). The bevel gear seven (39) is meshed with a bevel gear eight (40). The bevel gear eight (40) is fixedly connected to the screw (24).
Citation Information
Patent Citations
Nuclear engineering hydraulic valve test bed
CN222866214U