Nuclear power plant valve rod lifting test device

Abstract

The utility model discloses a nuclear power plant valve rod lifting test device, which comprises a shell, an electric wrench and a torque sensor, a driving gear, a transmission gear and a driven gear which are sequentially meshed with one another are arranged in the shell, the axial end part of the driving gear is provided with a driving connecting hole, the electric wrench is connected with the torque sensor, and the torque sensor is connected with the transmission gear. The torque sensor is connected with the driving connecting hole; a through hole penetrating through the upper surface and the lower surface of the shell is formed in the shell, the driven gear is in an annular column shape, a nut in threaded connection with a valve rod of a nuclear power plant valve is arranged in an inner cavity of the driven gear, and an inner cavity of the nut is communicated with the through hole. According to the nuclear power plant valve rod lifting test device, a lifting test can be rapidly carried out on the valve under the condition of independent operation of one person, the labor cost is reduced, the maintenance period is shortened, meanwhile, the staying time of operators in a nuclear island high-dose area is shortened, and therefore the safety risk is greatly reduced.

Description

Technical Field

[0001] The utility model relates to the technical field of nuclear power, in particular to a valve stem lifting and lowering test device for a nuclear power plant valve. Background Art

[0002] During the overhaul of the nuclear island of a nuclear power plant, gate valves in high-dose areas need to be regularly calibrated and inspected. After the inspection is completed, before the valve body is assembled, it is necessary to test the valve stem lifting to determine whether there are any jamming or other faults in the transmission mechanism of the valve body. For large gate valves, manual operation is extremely labor-intensive, inefficient and difficult to perform the lifting test. In addition, working in the high-dose area of ​​the nuclear island for a long time will cause personnel to be exposed to high radiation doses, which poses a great safety risk to the operators. Utility Model Content

[0003] The technical problem to be solved by the utility model is to provide a valve stem lifting and lowering testing device for a nuclear power plant valve.

[0004] The utility model solves the technical problem by adopting a technical solution: constructing a valve stem lifting test device for a nuclear power plant valve, comprising a housing, an electric wrench, and a torque sensor. A driving gear, a transmission gear, and a driven gear that mesh with each other in sequence are provided in the housing. A driving connection hole is provided at the axial end of the driving gear. The electric wrench is connected to the torque sensor, and the torque sensor is connected to the driving connection hole.

[0005] The shell is provided with through holes passing through its upper and lower surfaces. The driven gear is annular and cylindrical. The inner cavity of the driven gear is provided with a nut threadedly connected to the valve stem of the nuclear power plant valve. The inner cavity of the nut is connected to the through hole.

[0006] In some embodiments, the bottom of the housing is further provided with a mounting plate for connecting to a valve cover of a nuclear power plant valve.

[0007] In some embodiments, the mounting plate is provided with a long waist-shaped hole.

[0008] In some embodiments, the drive connection hole is a square hole.

[0009] In some embodiments, there are two transmission gears, and both of the transmission gears are engaged with the driving gear and the driven gear.

[0010] In some embodiments, the line connecting the axis of the driving gear and the axis of the driven gear is the first line; the line connecting the axes of the two transmission gears is the second line; the first line and the second line are arranged perpendicularly.

[0011] In some embodiments, the inner cavity of the driven gear is provided with a plurality of protrusions, the plurality of protrusions are spaced apart along the circumferential direction of the inner cavity of the driven gear, each of the protrusions is provided with a plurality of rectangular teeth, the plurality of rectangular teeth are spaced apart along the circumferential direction of the inner cavity of the driven gear, and a groove is defined between adjacent rectangular teeth;

[0012] The nut is annular and cylindrical, and an inner wall surface of the nut is provided with an internal thread. A plurality of convex teeth are provided at intervals on the outer peripheral side surface of the nut. The plurality of convex teeth are arranged at intervals along the circumferential direction of the outer peripheral side surface of the nut, and the convex teeth are engaged with the grooves.

[0013] In some embodiments, limiting grooves are formed between adjacent protrusions;

[0014] The lower side of the nut is provided with a plurality of mounting grooves, and the plurality of mounting grooves are arranged at intervals along the axis of the nut; the circumferential side wall of the nut is also provided with a limiting hole, and the limiting hole is used to connect the mounting groove and the limiting groove;

[0015] The nuclear power plant valve stem lifting test device also includes a plurality of bearings and a plurality of screws. The bearings are installed in the installation grooves. The screws are passed through the limiting holes to connect the bearings. The nuts of the screws are located in the limiting grooves.

[0016] In some embodiments, a portion of the bearing protrudes from a lower surface of the nut.

[0017] In some embodiments, the housing includes a shell and a cover that are detachably connected.

[0018] The implementation of the utility model has the following beneficial effects: the valve stem lifting test device of the nuclear power plant of the present application can realize the rapid lifting test of the valve under the condition of independent operation by one person, reducing the labor cost, shortening the maintenance cycle and reducing the time the operator stays in the high-dose area of ​​the nuclear island, thereby greatly reducing the safety risk. BRIEF DESCRIPTION OF THE DRAWINGS

[0019] In order to more clearly illustrate the technical solution of the present invention, the present invention will be further described below in conjunction with the accompanying drawings and embodiments. It should be understood that the following drawings only illustrate certain embodiments of the present invention and should not be considered as limiting the scope. A person of ordinary skill in the art can derive other relevant drawings based on these drawings without inventive effort. In the drawings:

[0020] Figure 1 This is a schematic diagram of an application of a valve stem lifting test device for a nuclear power plant in some embodiments of the present utility model;

[0021] Figure 2It is a schematic diagram of the bottom structure of a valve stem lifting test device for a nuclear power plant in some embodiments of the present utility model;

[0022] Figure 3 Schematic diagram of the structure of the electric wrench and torque sensor in some embodiments of the present invention;

[0023] Figure 4 It is a schematic diagram of the internal structure of a valve stem lifting test device for a nuclear power plant in some embodiments of the present utility model;

[0024] Figure 5 It is a schematic diagram of the bottom structure of the nut in some embodiments of the present invention. DETAILED DESCRIPTION

[0025] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific embodiments of the present invention are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the directions or positional relationships indicated by "front", "back", "up", "down", "left", "right", "longitudinal", "horizontal", "vertical", "horizontal", "top", "bottom", "inside", "outside", "head", "tail", etc. are based on the directions or positional relationships shown in the accompanying drawings and are constructed and operated in specific directions. They are only for the convenience of describing the present technical solution and do not indicate that the devices or components referred to must have specific directions. Therefore, they should not be understood as limiting the present invention.

[0026] It should also be noted that, unless otherwise clearly specified and limited, terms such as "installed", "connected", "connected", "fixed", and "set" should be understood in a broad sense. For example, they can be fixedly connected, detachably connected, or integrated; they can be mechanically connected or electrically connected; they can be directly connected or indirectly connected through an intermediate medium, and they can be internal connections between two elements or interactions between two elements. When an element is referred to as being "on" or "under" another element, the element can be "directly" or "indirectly" located on the other element, or there may be one or more intervening elements. The terms "first", "second", and "third" are only used to facilitate the description of the present technical solution and cannot be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, features defined as "first", "second", and "third" can explicitly or implicitly include one or more of these features. For those of ordinary skill in the art, the specific meanings of the above terms in the present utility model can be understood according to specific circumstances.

[0027] In the following description, specific details such as specific system structures and techniques are provided for purposes of illustration, not limitation, to facilitate a thorough understanding of the embodiments of the present invention. However, it will be apparent to those skilled in the art that the present invention may be implemented in other embodiments without these specific details. In other cases, detailed descriptions of well-known systems, devices, circuits, and methods are omitted to avoid obscuring the description of the present invention with unnecessary detail.

[0028] See Figures 1 to 5 The utility model shows a valve stem lifting test device for nuclear power plant valves, which is suitable for valve stem lifting test of nuclear power plants, especially for valve stem lifting test of large gate valves in nuclear power plants.

[0029] The nuclear power plant valve stem lifting test device includes a housing 10, an electric wrench 20 and a torque sensor 30. The housing 10 is provided with a driving gear 40, a transmission gear 50 and a driven gear 60 that are meshed with each other in sequence. The axial end of the driving gear 40 is provided with a driving connection hole 41. The electric wrench 20 is connected to the torque sensor 30, and the torque sensor 30 is connected to the driving connection hole 41.

[0030] The housing 10 is provided with through holes passing through the upper and lower surfaces thereof. The driven gear 60 is annular and cylindrical. The inner cavity of the driven gear 60 is provided with a nut 70 threadedly connected to the valve stem 100 of the nuclear power plant valve. The inner cavity of the nut 70 is connected to the through hole.

[0031] In some embodiments, the housing 10 may include a detachably connected shell and cover plate. The shell and cover plate may be connected by fasteners, including but not limited to bolts or screws. The shell may have a generally cylindrical structure, and the cover plate may have a generally cylindrical or plate-like structure. The housing 10 may be made of a metal material, including but not limited to stainless steel, aluminum alloy, or carbon steel. The interior of the housing 10 may be used to accommodate components such as the drive gear 40, the transmission gear 50, and the driven gear 60.

[0032] like Figure 1 and Figure 2 As shown, in some embodiments, the bottom of the housing 10 is further provided with a mounting plate 80 for connecting to the valve cover 200 of a nuclear power plant valve. The mounting plate 80 can be detachably connected to the bottom of the housing 10, and the two can be fixed by a threaded connection. The mounting plate 80 is provided with an elongated waist-shaped hole 81.

[0033] like Figure 1 and Figure 2As shown, the mounting plate 80 can be a long strip of plate. The number of mounting plates 80 can be two, and two mounting plates 80 can be provided. The two mounting plates 80 have the same length. The mounting plate 80 is provided with a waist-shaped hole 81, and the length direction of the waist-shaped hole 81 is the same as the length direction of the mounting plate 80. The waist-shaped hole 81 can be connected to the upper surface of the valve cover 200 via a fixing member, and the installation position of the nuclear power plant valve stem lifting test device can be appropriately adjusted. The fixing member includes but is not limited to a bolt or a fastening pin.

[0034] like Figure 3 and Figure 4 As shown, in some embodiments, the drive connection hole 41 is a square hole. A torque sensor 30 is mounted on the output shaft end of the electric wrench 20. The square rod of the output end of the torque sensor 30 is inserted into the drive connection hole 41, and the output end of the electric wrench 20 drives the drive gear 40 to rotate.

[0035] like Figure 4 As shown, in some embodiments, there are two transmission gears 50 , and both of the transmission gears 50 are engaged with the driving gear 40 and the driven gear 60 .

[0036] In some embodiments, the line connecting the axis of the driving gear 40 and the axis of the driven gear 60 is a first line, and the line connecting the axes of the two transmission gears 50 is a second line. The first line is perpendicular to the second line.

[0037] Combine Figure 4 and Figure 5 As shown, in some embodiments, the inner cavity of the driven gear 60 is provided with a plurality of protrusions 61 , and the number of the protrusions 61 may be five. Of course, the number of the protrusions 61 may be selected according to actual needs.

[0038] Several protrusions 61 are spaced apart along the circumference of the inner cavity of the driven gear 60. Each protrusion 61 is provided with a plurality of rectangular teeth 62, for example, three rectangular teeth 62. These rectangular teeth 62 are spaced apart along the circumference of the inner cavity of the driven gear 60, and a groove 63 is defined between adjacent rectangular teeth 62. The nut 70 is annular and cylindrical. The inner wall of the nut 70 is provided with an internal thread 71 (threaded hole), which is threadedly connected to the valve stem 100 of the nuclear power plant valve. The outer side surface of the nut 70 is provided with a plurality of protruding teeth 72 spaced apart along the circumference of the outer side surface of the nut 70. The protruding teeth 72 engage with the groove 63.

[0039] Combine Figure 4 and Figure 5As shown, in some embodiments, a limiting groove 64 is formed between adjacent protrusions 61. The limiting groove 64 can be a through groove or a non-through groove. The lower side of the nut 70 is provided with a plurality of mounting grooves 73. The mounting grooves 73 can be non-through grooves. The plurality of mounting grooves 73 are spaced apart along the axis of the nut 70. The circumferential side wall of the nut 70 is further provided with a limiting hole 74. The limiting hole 74 is used to connect the mounting groove 73 with the limiting groove 64. The number of the limiting grooves 64, the mounting grooves 73 and the limiting hole 74 can all be five. Of course, the number of the setting can be selected according to actual needs and is not specifically limited here.

[0040] Combine Figure 4 and Figure 5 As shown, the nuclear power plant valve stem lifting test device also includes a plurality of bearings 90 and a plurality of screws 91. The bearing 90 is installed in the installation groove 73. The screw 91 is passed through the limiting hole 74 to connect the bearing 90. The nut of the screw 91 is located in the limiting groove 64.

[0041] Furthermore, a portion of the bearing 90 protrudes from the lower surface of the nut 70 .

[0042] In some embodiments, the nuclear power plant valve stem lifting test device is used as follows: the nuclear power plant valve stem lifting test device is fixed to the upper surface of the valve cover 200 through the mounting plate 80, the nuclear power plant valve stem 100 passes through the inner cavity (threaded hole) at the center of the nut 70, and a torque sensor 30 is installed at the output shaft end of the electric wrench 20. The square rod at the output end of the torque sensor 30 is inserted into the drive connection hole 41. The electric wrench 20 is turned on, and the drive gear 40 is rotated under the drive of the output end of the electric wrench 20. The drive gear 40 drives the driven gear 60 to rotate through the transmission gear 50, and then drives the nut 70 to rotate. Under the action of the reaction force of the central thread of the nut 70, the valve stem 100 of the nuclear power plant valve can be lifted or dropped. During this process, the bearing 90 on the lower surface of the nut 70 rolls on the upper surface of the valve cover 200, thereby reducing the friction between the lower surface of the nut 70 and the upper surface of the valve cover 200. When the valve stem 100 of the nuclear power plant valve is lifted or lowered, observe whether its movement is flexible and smooth, and whether there is any jamming or abnormal sound. Read the maximum output of the torque sensor 30 and compare it with the torque threshold for opening or closing the nuclear power plant valve. If the result is less than, it means that the valve is in normal condition. If the result is greater than, it means that the valve has problems such as jamming and needs further inspection and treatment.

[0043] The nuclear power plant valve stem lifting test device of the present application is small in size, light in weight, easy to install, and simple to operate. It can match the valve stem threads of nuclear power plant valves of different specifications by replacing the nut 70, thereby making the device more widely applicable.

[0044] For large gate valves, the nuclear power plant valve stem lifting test device of the present application can quickly perform lifting tests on the valves with one person operating independently, reducing labor costs, shortening the maintenance cycle, and reducing the time operators stay in the high-dose area of ​​the nuclear island, thereby greatly reducing safety risks.

[0045] In the description of this specification, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present invention. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described can be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art can combine and combine different embodiments or examples described in this specification and features of different embodiments or examples without contradiction.

[0046] It can be understood that the above embodiments only express the preferred implementation methods of the present invention, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the present invention. It should be pointed out that for ordinary technicians in this field, without departing from the concept of the present invention, the above technical features can be freely combined, and several deformations and improvements can be made, all of which fall within the scope of protection of the present invention. Therefore, all equivalent changes and modifications made to the scope of the claims of the present invention should fall within the scope of coverage of the claims of the present invention.

Claims

1. A valve stem lifting test device for a nuclear power plant, characterized in that: The invention comprises a housing (10), an electric wrench (20) and a torque sensor (30); a driving gear (40), a transmission gear (50) and a driven gear (60) which are meshed with each other in sequence are provided in the housing (10); a driving connection hole (41) is provided at an axial end of the driving gear (40); the electric wrench (20) is connected to the torque sensor (30), and the torque sensor (30) is connected to the driving connection hole (41); The housing (10) is provided with through holes penetrating the upper and lower surfaces thereof; the driven gear (60) is in an annular columnar shape; the inner cavity of the driven gear (60) is provided with a nut (70) threadedly connected to the valve stem of the nuclear power plant valve; the inner cavity of the nut (70) is communicated with the through hole.

2. The valve stem lifting test device for a nuclear power plant according to claim 1, characterized in that: The bottom of the housing (10) is also provided with a mounting plate (80) for connecting to a valve cover of a nuclear power plant valve.

3. The valve stem lifting test device for a nuclear power plant according to claim 2, characterized in that: The mounting plate (80) is provided with a long waist-shaped hole (81).

4. The valve stem lifting test device for a nuclear power plant according to claim 1, characterized in that: The driving connection hole (41) is a square hole.

5. The valve stem lifting test device for a nuclear power plant according to claim 1, characterized in that: There are two transmission gears (50), and both of the two transmission gears (50) are engaged with the driving gear (40) and the driven gear (60).

6. The valve stem lifting test device for a nuclear power plant according to claim 5, characterized in that: The line connecting the axis of the driving gear (40) and the axis of the driven gear (60) is a first line; the line connecting the axes of the two transmission gears (50) is a second line; the first line and the second line are arranged perpendicularly.

7. The valve stem lifting test device for a nuclear power plant according to claim 1, characterized in that: The inner cavity of the driven gear (60) is provided with a plurality of convex portions (61), the plurality of convex portions (61) are arranged at intervals along the circumferential direction of the inner cavity of the driven gear (60), each of the convex portions (61) is provided with a plurality of rectangular teeth (62), the plurality of rectangular teeth (62) are arranged at intervals along the circumferential direction of the inner cavity of the driven gear (60), and a groove (63) is defined between adjacent rectangular teeth (62); The nut (70) is annular and cylindrical. An inner wall surface of the nut (70) is provided with an internal thread (71). The outer peripheral side surface of the nut (70) is provided with a plurality of convex teeth (72) at intervals. The plurality of convex teeth (72) are arranged at intervals along the circumferential direction of the outer peripheral side surface of the nut (70). The convex teeth (72) and the groove (63) are mutually engaged.

8. The valve stem lifting test device for a nuclear power plant according to claim 7, characterized in that: A limiting groove (64) is formed between adjacent protrusions (61); The lower side of the nut (70) is provided with a plurality of mounting grooves (73), and the plurality of mounting grooves (73) are arranged at intervals along the axis of the nut (70); the circumferential side wall of the nut (70) is also provided with a limiting hole (74), and the limiting hole (74) is used to connect the mounting groove (73) and the limiting groove (64); The nuclear power plant valve stem lifting test device also includes a plurality of bearings (90) and a plurality of screws (91), wherein the bearings (90) are installed in the installation grooves (73), the screws (91) are passed through the limiting holes (74) to connect the bearings (90), and the nuts of the screws (91) are located in the limiting grooves (64).

9. The valve stem lifting test device for a nuclear power plant according to claim 1, characterized in that: A portion of the bearing (90) protrudes from the lower surface of the nut (70).

10. The valve stem lifting test device for a nuclear power plant according to claim 1, characterized in that: The housing (10) comprises a shell and a cover plate that are detachably connected.

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