Nuclear power plant valve rod extraction and installation detection device

Abstract

The utility model discloses a nuclear power plant valve rod extraction and installation detection device, comprising a rack which is provided with a first moving wheel, and the upper surface of the rack is provided with a guide rail and a transition slide rail; the rack is further provided with a first supporting assembly and a second supporting assembly. The first supporting assembly comprises a first support and a first roller. The second supporting assembly comprises a second support and a second roller, and the first roller and the second roller are used for supporting the valve body; a first supporting seat is arranged on the rack; the supporting frame is provided with a second moving wheel and a sliding strip, a second supporting seat is arranged on the supporting frame, and the nuclear power plant valve rod and the second supporting seat are relatively fixed; the driving mechanism is used for being connected with the supporting frame so as to drive the supporting frame to be close to or away from the rack. By means of the device, valve body transferring and nuclear power plant valve rod pulling and installing can be achieved, the staying time of workers in a high-dose area can be effectively shortened, therefore, the irradiation dose of the workers is reduced, and the safety risk of the workers can be greatly reduced while the nuclear power plant valve overhauling efficiency is improved.

Description

TECHNICAL FIELD

[0001] The utility model relates to nuclear power technology field especially relates to a nuclear power plant valve rod draws detection device. BACKGROUND

[0002] In nuclear power plant, for the valve of high dose area of nuclear power plant especially large gate valve, need to carry out regular calibration and overhaul during overhaul, usually first remove valve cover, whole hoist after then carry out overhaul, overhaul process completely relies on manual operation. Since the whole weight of upper valve cover part of large gate valve is big, it is time-consuming and laborious in carrying process, manual operation is difficult in the process of overhaul such as drawing and installing valve rod, and has certain safety risk, high dose area operation and contact with radioactive valve component etc. can cause personnel to receive high radiation dose. SUMMARY

[0003] The utility model solves the technical problem, and provides a nuclear power plant valve rod draws detection device.

[0004] The utility model adopts the technical scheme in the technical problem of solving its technical problem: construct a nuclear power plant valve rod draws detection device, including:

[0005] Frame, the frame is equipped with a plurality of first mobile wheel, the upper surface of frame is equipped with two guide rails and movable installation on the transition slide rail of guide rail, two The guide rail is parallel interval setting and all along the length direction of frame extension setting;The frame is equipped with first support assembly and second support assembly still, both are interval setting along the length direction of frame, first support assembly includes two first support that are opposite setting, first roller is equipped on every first support;Second support assembly includes two second supports that are opposite setting, and second roller is equipped on every second support, first roller and second roller are used for supporting the valve body of nuclear power plant valve;The frame is equipped with support still, first support seat is equipped on support, first limit hole is equipped on first support seat;

[0006] Support frame, the support frame is interval setting with the frame, the support frame is equipped with a plurality of second mobile wheel, the support frame is equipped with the slide bar of movable connection with the transition slide rail, second support seat is equipped on the support frame, second limit hole is equipped on second support seat, second limit hole is coaxial setting with first limit hole, first limit hole and second limit hole are used for the nuclear power plant valve rod to be equipped in it The nuclear power plant valve rod is opposite fixed with second support seat;

[0007] Driving mechanism, the driving mechanism is used for with the support frame is connected, to drive the support frame is close to or away from the frame.

[0008] In some embodiments, the first support seat is provided with a plurality of first through holes spaced in the circumferential direction, the first through holes are in communication with the first limiting holes, and the nuclear power plant valve rod extraction detection device further comprises a plurality of limiting rods, the limiting rods are arranged in the first through holes, and the end of the limiting rod is provided with a roller abutting on the groove on the surface of the nuclear power plant valve rod.

[0009] In some embodiments, the second support seat is provided with a plurality of second through holes spaced in the circumferential direction, the second through holes are in communication with the second limiting holes, and the nuclear power plant valve rod extraction detection device further comprises a plurality of limiting members, the limiting members are arranged in the second through holes, and the end of the limiting member is used for abutting on the groove on the surface of the nuclear power plant valve rod.

[0010] In some embodiments, a bearing for the nuclear power plant valve rod is arranged in the second limiting hole.

[0011] In some embodiments, the driving mechanism comprises a first driving motor and a lead screw, the support frame is provided with a lead screw seat, the first driving motor is installed in the rack, the first driving motor is connected with the lead screw, and one end of the lead screw is connected with the lead screw seat.

[0012] In some embodiments, the nuclear power plant valve rod extraction detection device further comprises a plurality of laser range finders, and the plurality of laser range finders are installed on the slide through a fixing plate in the length direction of the slide.

[0013] In some embodiments, the number of the laser range finders is at least three.

[0014] In some embodiments, the central shaft of the first roller is provided with a first gear, the rack is further provided with a second driving motor, the output end of the second driving motor is provided with a second gear, and the first gear and the second gear are engaged with each other.

[0015] In some embodiments, the outer surface of the first roller and / or the second roller is provided with a pattern.

[0016] In some embodiments, the first moving wheel and the second moving wheel both comprise universal wheels.

[0017] The nuclear power plant valve rod extraction detection device can realize the transfer of the valve body of the nuclear power plant valve, especially the large gate valve, and the extraction of the nuclear power plant valve rod, can effectively shorten the time of the staff staying in the high-dose area, thereby reducing the radiation dose of the staff, and can improve the maintenance efficiency of the nuclear power plant valve, especially the large gate valve of the nuclear power plant, while greatly reducing the safety risk of the staff. BRIEF DESCRIPTION OF DRAWINGS

[0018] To more clearly illustrate the technical solution of this utility model, the present utility model will be further described below in conjunction with the accompanying drawings and embodiments. It should be understood that the following drawings only show some embodiments of this utility model and should not be considered as a limitation of the scope. For those skilled in the art, other related drawings can be obtained from these drawings without creative effort. In the drawings:

[0019] Figure 1 This is a schematic diagram illustrating the application of the nuclear power plant valve stem extraction and testing device in some embodiments of this utility model;

[0020] Figure 2 This is one of the partial structural schematic diagrams of the nuclear power plant valve stem extraction and testing device in some embodiments of this utility model;

[0021] Figure 3 This is the second partial structural schematic diagram of the nuclear power plant valve stem extraction and testing device in some embodiments of this utility model;

[0022] Figure 4 This is a schematic diagram of the structure of the first support base in some embodiments of this utility model;

[0023] Figure 5 This is a schematic diagram of the structure of the second support base in some embodiments of this utility model. Detailed Implementation

[0024] To provide a clearer understanding of the technical features, objectives, and effects of this utility model, the specific embodiments of this utility model are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the orientations or positional relationships indicated by terms such as "front," "rear," "upper," "lower," "left," "right," "longitudinal," "horizontal," "vertical," "horizontal," "top," "bottom," "inner," "outer," "head," and "tail" are based on the orientations or positional relationships shown in the accompanying drawings, and are constructed and operated in a specific orientation. They are only for the convenience of describing this technical solution and do not indicate that the device or component referred to must have a specific orientation; therefore, they should not be construed as limitations on this utility model.

[0025] It should also be noted that, unless otherwise explicitly specified and limited, terms such as "installation," "connection," "joining," "fixing," and "setting" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components. When an component is referred to as being "on" or "below" another component, the component can be located "directly" or "indirectly" on the other component, or there may be one or more intermediary components. The terms "first," "second," "third," etc., are only for the convenience of describing this technical solution and should not be construed as indicating or implying relative importance or implicitly specifying the number of indicated technical features. Therefore, features defined with "first," "second," "third," etc., may explicitly or implicitly include one or more of that feature. For those skilled in the art, the specific meaning of the above terms in this utility model can be understood according to the specific circumstances.

[0026] In the following description, specific details such as particular system structures and techniques are set forth for illustrative purposes and not for limitation, in order to provide a thorough understanding of the embodiments of the present invention. However, those skilled in the art will understand that the present invention can be implemented in other embodiments without these specific details. In other instances, detailed descriptions of well-known systems, apparatuses, circuits, and methods are omitted so as not to obscure the description of the present invention with unnecessary detail.

[0027] See Figures 1 to 5 This utility model discloses a valve stem extraction and inspection device for nuclear power plants, which can be used for the transfer of nuclear power plant valves, including but not limited to large gate valves. The valve stem extraction and inspection device can also be used for the extraction and installation of nuclear power plant valve stems 200 to facilitate the inspection of the nuclear power plant valve stems 200, which can be the valve stems of large gate valves.

[0028] In some embodiments, the nuclear power plant valve stem removal and testing device includes: a frame 10, a support frame 20, and a drive mechanism 30.

[0029] The frame 10 is generally cuboid in shape, and can be either a cube or a cuboid. The frame 10 may be equipped with several first moving wheels 11. The upper surface of the frame 10 is provided with two guide rails 12 and a transition slide rail 13 movably mounted on the guide rails 12. The guide rails 12 and the transition slide rail 13 can be connected by a slider. The two guide rails 12 are arranged parallel and spaced apart, both extending along the length of the frame 10. The frame 10 also provides a first support assembly 14 and a second support assembly 15, both spaced apart along the length of the frame 10. Component 14 includes two first supports 141 arranged opposite to each other, each of which is provided with a first roller 142; the second support component 15 includes two second supports 151 arranged opposite to each other, and each of which is provided with a second roller 152, the first roller 142 and the second roller 152 are used to support the valve body 100 of the nuclear power plant valve; the frame 10 is also provided with a bracket 16, which may be arranged near the first support component 14, and the bracket 16 is provided with a first support seat 17, the first support seat 17 being provided with a first limiting hole 171.

[0030] The support frame 20 is spaced apart from the frame 10, and the support frame 20 is close to the bracket 16. The support frame 20 is provided with a plurality of second moving wheels 21. The support frame 20 is provided with a slide bar 22 that is movably connected to the transition slide rail 13. The support frame 20 is provided with a second support seat 23. The second support seat 23 is provided with a second limiting hole 231. The second limiting hole 231 is coaxially arranged with the first limiting hole 171. The first limiting hole 171 and the second limiting hole 231 are used for the nuclear power plant valve stem 200 to pass through, and the nuclear power plant valve stem 200 is fixed relative to the second support seat 23.

[0031] The drive mechanism 30 is used to connect with the support frame 20 to drive the support frame 20 closer to or further away from the frame 10. In some embodiments, the drive mechanism 30 includes a first drive motor and a lead screw 31. The support frame 20 is provided with a lead screw seat 32. The first drive motor is installed inside the frame 10 and connected to the lead screw 31. One end of the lead screw 31 is connected to the lead screw seat 32. The lead screw 31 may be, but is not limited to, a ball screw. Understandably, the drive mechanism 30 may be a lead screw drive mechanism. Of course, in some embodiments, the drive mechanism 30 may also include a hydraulic cylinder or a pneumatic cylinder. If a hydraulic cylinder is selected, it may be installed inside the frame 10, and the telescopic rod of the hydraulic cylinder may be connected to the support frame 20. Alternatively, if a pneumatic cylinder is selected, it may be installed inside the frame 10, and the telescopic rod of the pneumatic cylinder may be connected to the support frame 20. Of course, the drive mechanism 30 may also use other drive devices, which are not specifically limited here.

[0032] In some embodiments, the first support base 17 is provided with a plurality of first through holes 172 spaced apart along the circumferential direction. The first through holes 172 are connected to the first limiting holes 171. The nuclear power plant valve stem extraction and testing device also includes a plurality of limiting rods 40. The limiting rods 40 pass through the first through holes 172, and the ends of the limiting rods 40 are provided with rollers 41 (e.g., rollers 41) that abut against the grooves 201 on the surface of the nuclear power plant valve stem 200. Figure 2 (As shown). The roller 41 is inserted into the groove 201 to limit the radial displacement of the nuclear power plant valve stem 200 during the installation and removal of the valve stem 200, so that it is always coaxial with the valve body 100. After the limiting rod 40 is installed, it can be fixed laterally with a set screw.

[0033] In some embodiments, the second support base 23 is provided with a plurality of second through holes 232 spaced apart along the circumferential direction. The second through holes 232 are connected to the second limiting holes 231. The nuclear power plant valve stem extraction and testing device further includes a plurality of limiting members 50. The limiting members 50 pass through the second through holes 232, and the ends of the limiting members 50 are used to abut against the grooves 201 on the surface of the nuclear power plant valve stem 200. The limiting members 50 include, but are not limited to, fastening screws.

[0034] In some embodiments, the second limiting hole 231 is provided with a bearing 24 for the nuclear power plant valve stem 200 to pass through.

[0035] In some embodiments, the nuclear power plant valve stem removal and testing device further includes a plurality of laser rangefinders 60, which are mounted at intervals on the slide bar 22 along the length direction of the slide bar 22 via a fixing plate 61. The plurality of laser rangefinders 60 may be installed at equal intervals. The laser rangefinders 60 are mounted on the fixing plate 61 with their laser emission ports aligned with the nuclear power plant valve stem 200, and the line connecting their centers is parallel to the axis of the nuclear power plant valve stem 200.

[0036] Preferably, the number of laser rangefinders 60 is at least three.

[0037] In some embodiments, the central shaft of the first roller 142 is provided with a first gear, and the frame 10 is also provided with a second drive motor. The output end of the second drive motor is provided with a second gear. The first gear and the second gear mesh with each other, and the second drive motor can drive the first roller 142 to rotate, thereby driving the valve body 100 to rotate. Of course, the first roller 142 can also adopt other drive structures, which are not specifically limited here.

[0038] In some embodiments, the outer surfaces of the first roller 142 and / or the second roller 152 are textured to increase the friction between the first roller 142 and / or the second roller 152 and the valve body 100. Under the action of the friction between the first roller 142 and / or the second roller 152 and the valve body 100, the valve body 100 rotates, thereby driving the nuclear power plant valve stem 200 to rotate.

[0039] In some embodiments, both the first caster wheel 11 and the second caster wheel 21 include swivel wheels, and the swivel wheels are equipped with brakes to facilitate parking in a suitable position.

[0040] The application of the nuclear power plant valve stem extraction and testing device is as follows: The valve body 100 is placed on the first support assembly 14 and the second support assembly 15 of the frame 10, and then the valve body 100 is transported to a low-radiation area for operation. During the extraction and testing of the nuclear power plant valve stem 200, the limiting rod 40 on the first support seat 17 and the limiting member 50 on the second support seat 23 are first installed. Then, the drive mechanism 30 is activated. Under the drive of the drive mechanism 30, the support frame 20 is moved closer to or away from the frame 10. During this process, the nuclear power plant valve stem 200 is extracted or reinstalled. When the nuclear power plant valve stem 200 is extracted, i.e., when the support frame 20 is pulled out, the surface of the nuclear power plant valve stem 200 can be manually inspected for defects such as wear, scratches, and corrosion. In addition, the straightness of the nuclear power plant valve stem 200 can be measured. First, the limiting rod 40 on the first support seat 17 and the limiting piece 50 on the second support seat 23 are removed. The first roller 142 rotates to drive the valve body 100 to rotate, which in turn drives the nuclear power plant valve stem 200 to rotate. During this process, the laser rangefinder 60 simultaneously measures the height of each point on several cross sections of the nuclear power plant valve stem 200 when it is irradiated by the laser. Data collected by the laser rangefinder 60 at several different times are collected to calculate the straightness. Compared with traditional manual operation, measurement and calculation, it saves manpower and can measure the straightness of the nuclear power plant valve stem 200 more accurately and efficiently.

[0041] This nuclear power plant valve stem extraction and testing device can realize the transfer of valve body 100 of nuclear power plant valves, especially large gate valves, and the extraction and installation of valve stem 200. It can effectively shorten the time that workers stay in high-dose areas, thereby reducing the radiation dose to personnel. It can greatly reduce personnel safety risks while improving the maintenance efficiency of nuclear power plant valves, especially large gate valves.

[0042] It is understood that the above embodiments only illustrate preferred embodiments of the present utility model, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present utility model patent. It should be noted that for those skilled in the art, the above technical features can be freely combined, and several modifications and improvements can be made without departing from the concept of the present utility model, all of which fall within the protection scope of the present utility model. Therefore, all equivalent transformations and modifications made within the scope of the claims of the present utility model should fall within the coverage of the claims of the present utility model.

Claims

1. A valve stem extraction and testing device for nuclear power plants, characterized in that, include: The frame includes several first moving wheels. The upper surface of the frame has two guide rails and a transition slide rail movably mounted on the guide rails. The two guide rails are parallel and spaced apart, both extending along the length of the frame. The frame also includes a first support assembly and a second support assembly, both spaced apart along the length of the frame. The first support assembly includes two opposing first supports, each with a first roller. The second support assembly includes two opposing second supports, each with a second roller. The first and second rollers support the valve body of a nuclear power plant valve. The frame also includes a bracket with a first support seat, which has a first limiting hole. A support frame is provided, which is spaced apart from the machine frame. The support frame is provided with a plurality of second moving wheels and a slide bar that is movably connected to the transition slide rail. The support frame is provided with a second support seat, which is provided with a second limiting hole. The second limiting hole is coaxially arranged with a first limiting hole. The first limiting hole and the second limiting hole are used for the nuclear power plant valve stem to pass through them, and the nuclear power plant valve stem is fixed relative to the second support seat. A drive mechanism is provided for connection with the support frame to drive the support frame closer to or away from the frame.

2. The nuclear power plant valve stem extraction and testing device according to claim 1, characterized in that, The first support base is provided with a plurality of first through holes spaced apart along the circumferential direction. The first through holes are connected to the first limiting holes. The nuclear power plant valve stem extraction and testing device also includes a plurality of limiting rods. The limiting rods pass through the first through holes, and the ends of the limiting rods are provided with rollers that abut against the grooves on the surface of the nuclear power plant valve stem.

3. The nuclear power plant valve stem extraction and testing device according to claim 1, characterized in that, The second support base is provided with a plurality of second through holes spaced apart along the circumferential direction. The second through holes are connected to the second limiting holes. The nuclear power plant valve stem extraction and testing device also includes a plurality of limiting members. The limiting members pass through the second through holes, and the ends of the limiting members are used to abut against the grooves on the surface of the nuclear power plant valve stem.

4. The nuclear power plant valve stem extraction and testing device according to claim 1, characterized in that, The second limiting hole is provided with a bearing for the nuclear power plant valve stem to pass through.

5. The nuclear power plant valve stem extraction and testing device according to claim 1, characterized in that, The driving mechanism includes a first driving motor and a lead screw. A lead screw seat is provided on the support frame. The first driving motor is installed in the frame and connected to the lead screw. One end of the lead screw is connected to the lead screw seat.

6. The nuclear power plant valve stem extraction and testing device according to claim 1, characterized in that, The nuclear power plant valve stem extraction and testing device also includes several laser rangefinders, which are installed at intervals on the slide bar along the length of the slide bar via a fixing plate.

7. The nuclear power plant valve stem extraction and testing device according to claim 6, characterized in that, The number of laser rangefinders is at least three.

8. The nuclear power plant valve stem extraction and testing device according to claim 1, characterized in that, The central shaft of the first roller is provided with a first gear, and the frame is also provided with a second drive motor. The output end of the second drive motor is provided with a second gear, and the first gear and the second gear mesh with each other.

9. The nuclear power plant valve stem extraction and testing device according to any one of claims 1 to 8, characterized in that, The outer surface of the first roller and / or the second roller is textured.

10. The nuclear power plant valve stem extraction and testing device according to any one of claims 1 to 8, characterized in that, Both the first and second movable wheels include omnidirectional wheels.

Images