CN209764753U - Device for detecting surface of nuclear fuel rod - Google Patents
Device for detecting surface of nuclear fuel rod Download PDFInfo
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- CN209764753U CN209764753U CN201920410473.7U CN201920410473U CN209764753U CN 209764753 U CN209764753 U CN 209764753U CN 201920410473 U CN201920410473 U CN 201920410473U CN 209764753 U CN209764753 U CN 209764753U
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Abstract
the utility model discloses a device for nuclear fuel rod surface detects belongs to automation equipment technical field. The utility model provides a device for nuclear fuel rod surface detection includes the second frame, chuck mechanism, spectrum detection mechanism, laser linear scanning mechanism and controlling means, can centre gripping bar and drive the bar rotation through setting up chuck mechanism, and can carry out 360 detections to the small defect on bar surface and the small defect of tip welding seam simultaneously through setting up spectrum detection mechanism and laser linear scanning mechanism, compare in prior art the bar go on detecting one by one, reduced the required time of detection to very big degree. The device for detecting the surface of the nuclear fuel rod is high in automation degree, integration and detection efficiency, can automatically detect the small defects on the surface of the rod and the small defects at the end parts of welding seams, is favorable for improving the detection precision, and ensures the use safety of the rod.
Description
Technical Field
the utility model relates to an automation equipment technical field especially relates to a device for nuclear fuel rod surface detects.
Background
nuclear fuel rods are the first safety barrier of a nuclear reactor and play a crucial role in preventing nuclear leaks. The defects on the surface of the cladding of the nuclear fuel rod and the surface of the welding seam exceed the standard, which can cause the damage of the nuclear fuel rod and directly influence the safe operation of the reactor of the nuclear power station.
At present, the surface inspection method of the fuel rod is usually manual visual inspection, defects are found, the damage depth is measured by using a microscope, the efficiency is low, and the omission inspection is easy. In addition to manual visual inspection, ultrasonic and eddy current inspection techniques are also used to detect nuclear fuel rod defects, but typically detect cladding internal defects. X-ray radiation may also be used to detect nuclear fuel rod defects, which are typically internal porosity, penetration, etc. of welds. The detection sensitivity of these techniques is such that it is not possible to detect minute defects on the surface of the fuel rod, such as defects of 30um at minimum eddy currents, and is directionally dependent, and it is not possible to automatically detect critical defects on the surface of the nuclear fuel rod cladding and on the weld surface of around 20 um.
Therefore, it is desirable to provide a detection device capable of detecting micro defects on the cladding surface and the weld surface of the nuclear fuel rod.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to provide a device method for nuclear fuel rod surface detects, this a device for nuclear fuel rod surface detects not only degree of automation is higher, the integrated level is high, detection efficiency is high, and can realize the detection for the small defect of nuclear fuel rod.
to achieve the purpose, the utility model adopts the following technical proposal:
An apparatus for nuclear fuel rod surface inspection, comprising a second frame, further comprising:
The chuck mechanism is arranged on the second rack and used for clamping a bar stock and driving the bar stock to rotate;
the spectrum detection mechanism is arranged on the second rack, is positioned on one side of the chuck mechanism and is used for detecting the defects on the surface of the welding seam at the end part of the bar;
The laser linear scanning mechanism is arranged on the second rack and used for detecting the defects on the surface of the bar;
and the control device is in communication connection with the chuck mechanism, the spectrum detection mechanism and the laser linear scanning mechanism.
Preferably, the apparatus for nuclear fuel rod surface inspection further includes:
the purging mechanism is arranged on the second rack and located on the transmission path of the bar, the purging mechanism comprises a purging wind generator and a purging pipe, a gas outlet of the purging wind generator is communicated with a gas inlet of the purging pipe, and a purging opening is formed in the purging pipe.
Preferably, the purge wind generator is an ion wind generator.
preferably, the chuck mechanism comprises a first chuck component and a second chuck component which are arranged at intervals along the length direction of the bar stock, and through holes allowing the bar stock to pass through are formed in the first chuck component and the second chuck component.
Preferably, the first chuck assembly comprises a first chuck and a first driving mechanism, the first chuck is arranged on the second rack, a first clamping seat is arranged on the first chuck, the through hole is formed in the first clamping seat, and the first driving mechanism is in transmission connection with the first clamping seat and is used for driving the first clamping seat to rotate;
the second chuck assembly comprises a second chuck and a second driving mechanism, the second chuck is arranged on the second rack, a second clamping seat is arranged on the second chuck, the through hole is formed in the second clamping seat, and the second driving mechanism is in transmission connection with the second clamping seat and used for driving the second clamping seat to rotate;
the first clamping seat and the second clamping seat are provided with clamping heads along the circumferential direction of the through hole.
Preferably, the apparatus for nuclear fuel rod surface inspection further includes:
The guide mechanism is arranged on the second rack and positioned between the first chuck component and the second chuck component, and a guide hole allowing the bar stock to pass through is formed in the guide mechanism.
preferably, the apparatus for nuclear fuel rod surface inspection further includes:
And the character measuring and recognizing mechanism is arranged on the second rack and is used for recognizing the mark on the bar stock.
preferably, the character measuring and recognizing mechanism comprises a character measuring rack, a light source and a detecting component, the character measuring rack is arranged on the second rack, the light source and the detecting component are arranged on the character measuring rack, and the detecting component is used for acquiring the mark on the bar stock.
preferably, the spectrum detection mechanism comprises a spectrum confocal camera and a moving module, the spectrum confocal camera is arranged on the moving module, and the moving module can drive the spectrum confocal camera to slide.
preferably, the laser linear scanning mechanism comprises a laser camera and an image processing component, the laser camera is electrically connected with the image processing component, and the laser camera can acquire image information of the surface of the bar stock and transmit the image information to the image processing component.
The utility model has the advantages that:
The utility model provides a device for nuclear fuel rod surface detection, this device for nuclear fuel rod surface detection includes the second frame, chuck mechanism, spectrum detection mechanism, laser linear scanning mechanism and controlling means, can centre gripping bar and drive the bar rotation through setting up chuck mechanism, and can carry out 360 detection to the small defect on bar surface and the small defect of tip welding seam simultaneously through setting up spectrum detection mechanism and laser linear scanning mechanism, the bar goes on detects one by one in prior art, the required time of detection has been reduced to very big degree. The device for detecting the surface of the nuclear fuel rod is high in automation degree, integration and detection efficiency, can automatically detect the small defects on the surface of the rod and the small defects at the end parts of welding seams, is favorable for improving the detection precision, and ensures the use safety of the rod.
drawings
Fig. 1 is a schematic structural diagram of a bar stock detection device provided by the present invention;
fig. 2 is a schematic structural diagram of the feeding device provided by the present invention;
fig. 3 is a side view of the feeding device provided by the present invention;
Fig. 4 is a schematic structural view of the feeding device provided by the present invention after the first frame is hidden;
Fig. 5 is a schematic structural diagram of a first guide wheel mechanism and a second material shifting mechanism provided by the present invention;
FIG. 6 is a schematic structural view of an apparatus for nuclear fuel rod surface inspection provided by the present invention;
FIG. 7 is a side view of an apparatus for nuclear fuel rod surface inspection provided by the present invention;
FIG. 8 is a top view of an apparatus for nuclear fuel rod surface inspection provided by the present invention;
Fig. 9 is a schematic structural view of a chuck mechanism provided by the present invention;
Fig. 10 is a schematic structural diagram of a laser linear scanning mechanism provided by the present invention;
fig. 11 is a schematic structural diagram of a spectrum detection mechanism provided by the present invention;
fig. 12 is a schematic structural diagram of a character measurement identification mechanism provided by the present invention;
Fig. 13 is a schematic structural view of a guide mechanism provided in the present invention;
fig. 14 is a schematic structural view of the blanking device provided by the present invention;
Fig. 15 is a schematic structural view of the blanking device provided by the present invention after the third frame is hidden;
Fig. 16 is a side view of the blanking device provided by the present invention;
Fig. 17 is a schematic mechanism diagram of a third material shifting mechanism, a second guide wheel mechanism and a fourth material shifting mechanism provided by the present invention.
In the figure:
100. a frame; 200. a feeding device; 300. a device for nuclear fuel rod surface inspection; 400. a blanking device;
1. a first frame; 2. a first material shifting mechanism; 201. a first base; 202. a first cylinder; 203. a first kickoff plate;
3. A first material guide mechanism; 301. a first material guide base; 302. a first material guide plate; 303. a first stopper;
4. a second material shifting mechanism; 401. a second base; 402. a second cylinder; 403. a second kickoff plate;
5. A first clamping mechanism;
6. A first guide wheel mechanism; 601. a first guide wheel seat; 602. a first guide wheel;
7. A first push bar mechanism; 701. a first push rod cylinder; 702. a first push rod block;
8. a baffle plate;
9. A second frame; 10. a purging mechanism; 1001. a blowing wind generator; 1002. a purge tube;
11. A chuck mechanism; 1101. a first chuck assembly; 11011. a first chuck; 11012. a motor; 11013. a belt drive member; 11014. a first clamping seat; 1102. a second chuck assembly;
12. A character measurement identifier mechanism; 1201. a character testing frame; 1202. a detection component;
13. A spectrum detection mechanism; 1301. a spectral confocal camera; 1302. a moving module;
14. A laser linear scanning mechanism; 1401. a laser camera;
15. A guide mechanism; 1501. a guide seat; 1502. a guide hole;
16. A third frame;
17. A second clamping mechanism; 1701. a second clamping base; 1702. a second clamping manipulator; 1703. a guide slide rail;
18. A second guide wheel mechanism; 1801. a second guide wheel seat; 1802. a second guide wheel;
19. A third material shifting mechanism; 1901. a third base; 1902. a first material shifting motor; 1903. a first rotating shaft; 1904. a third kickoff plate; 20. a fourth material shifting mechanism;
21. A second material guide mechanism; 2101. a second material guiding base; 2102. a second material guide plate; 2103. a second stopper;
22. a third material guiding mechanism; 23. and the second rod pushing mechanism.
Detailed Description
the technical solution of the present invention will be described clearly and completely with reference to the accompanying drawings, and obviously, the described embodiments are some, but not all embodiments of the present invention. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative work belong to the protection scope of the present invention.
In the description of the present invention, it should be noted that the terms "center", "upper", "lower", "left", "right", "vertical", "horizontal", "inner", "outer", and the like indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are only for convenience of description and simplification of description, but do not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention. Furthermore, the terms "first," "second," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance. Wherein the terms "first position" and "second position" are two different positions.
In the description of the present invention, it is to be noted that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are to be construed broadly, e.g., as meaning either a fixed connection or a removable connection; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meaning of the above terms in the present invention can be understood in specific cases to those skilled in the art.
the embodiment provides a bar stock check out test set, and this bar stock check out test set can detect the small defect of welding seam on scratch, pit, island shape on bar stock surface hinder, scab etc. and the bar stock. In this embodiment, the rod material is a cylindrical nuclear fuel rod, and the nuclear fuel rod includes a rod material main body and end plugs, which are coaxially disposed, and are disposed at two sides of the rod material main body. The end plug and the bar main body are connected in a welding mode, and an annular welding seam is arranged at the connection position of the end plug and the bar main body. Of course, in other embodiments, the bar stock detection device may be used to detect bar stock for other purposes, which is not illustrated here.
as shown in fig. 1, the bar stock detecting apparatus includes a frame 100, and a feeding device 200, a device 300 for nuclear fuel rod surface detection, and a discharging device 400 provided on the frame 100. The frame 100 is a frame structure formed by assembling sheet metal parts, and has the advantages of high support stability, low manufacturing cost and the like. In order to improve the structural strength of the frame 100, a structure such as a reinforcing rib may be provided on the frame structure. The frame 100 may be an integral structure or a separate structure, and in this embodiment, the frame 100 is selected to be a separate structure for the convenience of manufacturing and installing the frame 100. Specifically, the rack 100 includes a first rack 1, a second rack 9, and a third rack 16 arranged side by side, a loading device 200 is provided on the first rack 1, a device 300 for nuclear fuel rod surface inspection is provided on the second rack 9, and a discharging device 400 is provided on the third rack 16. The device 300 for nuclear fuel rod surface detection is located between the feeding device 200 and the discharging device 400, the feeding device 200 is communicated with an input end of the device 300 for nuclear fuel rod surface detection, the discharging device 400 is communicated with an output end of the device 300 for nuclear fuel rod surface detection, automatic feeding can be achieved by the feeding device 200, nuclear fuel rods are transmitted into the device 300 for nuclear fuel rod surface detection one by one, the device 300 for nuclear fuel rod surface detection can detect defects on a rod main body of a nuclear fuel rod, welding seams between the rod main body and an end plug can be detected, the detected nuclear fuel rods enter the discharging device 400 from the device 300 for nuclear fuel rod surface detection, and the discharging device 400 transmits qualified nuclear fuel rods and unqualified nuclear fuel rods to different regions for storage according to detection results.
the feeding device does not need artificial transportation in the whole feeding process, and can effectively avoid abnormal collision and transportation of the bars, thereby reducing the probability of bar damage and being beneficial to improving the yield of the bars. Specifically, as shown in fig. 2 to 4, the feeding device 200 includes a first material shifting mechanism 2, a first material guiding mechanism 3, a second material shifting mechanism 4, and a first clamping mechanism 5. The first material shifting mechanism 2 is disposed at an input end of the first material guiding mechanism 3, and can shift the nuclear fuel rod from a conveying line (not shown) to the first material guiding mechanism 3. The transfer chain mainly used transmits nuclear fuel rod, realizes automatic feeding, and in this embodiment, the transfer chain can be for belt mechanism or manipulator etc. do not do specific restriction here, as long as can transmit nuclear fuel rod to first 2 departments of dialling material mechanism can.
the first material shifting mechanism 2 comprises a first base 201, a first cylinder 202 and a first material shifting plate 203, wherein the first base 201 is vertically arranged on the first frame 1, in this embodiment, the first base 201 is L-shaped, a transverse plate of the first base 201 is fixedly connected with the first frame 1 through screws, and a vertical plate of the first base 201 is vertically arranged with the first frame 1. The first cylinder 202 is fixedly mounted on the side of the vertical plate of the first base 201, the cylinder rod of the first cylinder 202 is vertically arranged upwards, and the top end of the cylinder rod of the first cylinder 202 is fixedly connected with the first material shifting plate 203. Under the driving of the first cylinder 202, the first material shifting plate 203 can move up and down along the vertical direction, so that the first material shifting plate 203 is flush with the first material guiding mechanism 3, and the nuclear fuel rods on the first material shifting plate are shifted to the first material guiding mechanism 3. In order to enable the nuclear fuel rod to automatically roll onto the first material guiding mechanism 3, an inclined first material stirring surface is arranged at the top of the first material stirring plate 203, and one end, far away from the first material guiding mechanism 3, of the first material stirring surface is higher than one end, close to the first material guiding mechanism 3, of the first material stirring surface. The higher one end of first switch plate 203 can be picked up nuclear fuel rod from the transfer chain, and under the effect of gravity, nuclear fuel rod can roll towards the lower one side of first switch plate 203 along first switch plate to roll to on the first guide mechanism 3 with the lower one end butt of first switch plate 203.
The first material guiding mechanism 3 comprises a first material guiding base 301 and a first material guiding plate 302, the first material guiding base 301 is vertically arranged on the first rack 1, the first material guiding plate 302 is arranged at the top of the first material guiding base 301, a first material guiding surface is arranged on the first material guiding plate 302, the inclined direction of the first material guiding surface is the same as the inclined direction of the first material stirring surface, and the higher end of the first material guiding plate 302 is opposite to the lower end of the first material stirring plate 203. The angle of inclination of the first guide surface is preferably between 1 and 10 °, and may be, for example, 1 °, 3 °, 5 °, 8 °, or 10 °. Further, the first material guiding plate 302 is detachably connected to the first material guiding base 301, so as to adjust the inclination angle of the first material guiding surface according to the requirement. When the first material shifting mechanism 2 shifts the nuclear fuel rod to the first material guiding mechanism 3, the nuclear fuel rod can roll from the higher end to the lower end of the first material guiding plate 302 along the first material guiding surface under the action of gravity.
Because the length of the nuclear fuel rod is long, in order to reduce the manufacturing cost and the installation difficulty of the first material guiding mechanism 3, in this embodiment, the first material guiding base 301 is formed by arranging a plurality of sub bases with smaller widths at intervals, the first material guiding plate 302 is formed by arranging a plurality of sub material guiding plates with smaller widths at intervals, the number of the sub bases is equal to that of the sub material guiding plates, and one sub material guiding plate is arranged at the top of each sub base. The sub-base is integrally U-shaped and comprises a cross beam and vertical beams vertically arranged at two ends of the cross beam, the cross beam is fixedly connected with the first frame 1, the vertical beams are vertically arranged, and the tops of the two vertical beams are detachably connected with two ends of the sub-material guide plate respectively.
when the sub-guide plate stroke is longer, when being provided with many nuclear fuel rods on it, in order to segment the sub-guide plate stroke, in order to set up many nuclear fuel rods separately that will be located on the sub-guide plate, so that can realize the transmission of nuclear fuel rod one by one and detect one by one, be provided with a plurality of first spacer blocks 303 along the guide direction interval on the sub-guide plate, a plurality of first spacer blocks 303 are cut apart into a plurality of accommodation spaces with the sub-guide plate, preferably set up a nuclear fuel rod in each accommodation space, in order to avoid unusual collision between the many nuclear fuel rods, reduce the friction between the nuclear fuel rod, thereby guarantee the integrality of the inside uranium dioxide pellet of nuclear fuel rod, improve the quality of nuclear fuel rod. In order to realize the transmission of the nuclear fuel rods between the adjacent accommodating spaces, a first rod pushing mechanism 7 is arranged on the side of the sub guide plate where the first stopper 303 is arranged. The first push rod mechanism 7 comprises a first push rod cylinder 701 and a first push rod block 702, the first push rod cylinder 701 is arranged on the side portion of the sub-base, and a cylinder rod of the first push rod cylinder 701 is vertically arranged upwards and is fixedly connected with the first push rod block 702. The first push rod block 702 includes a first connecting portion and a first push finger portion, the first connecting portion is a rectangular block, and the first push finger portion is a wedge-shaped block. In order to prevent the nuclear fuel rod from violently colliding with the first stopper 303 due to an excessive acceleration during rolling, a protective element made of a polyurethane material or the like may be further provided on the first stopper 303. In addition to the guard elements, it is of course possible to reduce the speed of the nuclear fuel rod by using a speed reduction mechanism such as a hydraulic shock absorber. Of course, in other embodiments, the first spacer 303 and the guard member may not be provided if the stroke of the guide plate is short or only one nuclear fuel rod is provided on the guide plate at a time.
When the nuclear fuel rod is blocked by the first spacer 303, the highest end of the first push finger part is just located under the nuclear fuel rod, when the nuclear fuel rod needs to be transferred to the next accommodating space, the cylinder rod of the first push rod cylinder 701 moves upwards, the first push finger part of the first push rod 702 jacks up the nuclear fuel rod, and the nuclear fuel rod moves along the wedge-shaped surface of the wedge-shaped block under the action of gravity, so that the nuclear fuel rod passes through the first spacer 303 and reaches the next accommodating space. The number of the first rod pushing mechanisms 7 is not limited, and may be one, two or more, and preferably, one first rod pushing mechanism 7 is disposed on a side portion of each sub-base, so as to improve the stability of the nuclear fuel rod in the adjacent accommodating space. Further, in order to avoid the first rod pushing mechanism 7 to push the nuclear fuel rod to be deviated, the baffle plates 8 are further arranged on the two sides of the first material guide mechanism 3 along the length direction of the nuclear fuel rod, and the baffle plates 8 can align the fuel rod left and right, so that the feeding is facilitated. One of the two flaps 8 is stationary 8 and the other flap 8 is laterally movable to accommodate adjustment of the width therebetween.
when the nuclear fuel rod reaches the first spacer 303 of the last accommodating space, the second material shifting mechanism 4 at the output end of the first material guide mechanism 3 can shift the nuclear fuel rod to the first clamping mechanism 5. As shown in fig. 5, the second material shifting mechanism 4 includes a second base 401, a second cylinder 402 and a second material shifting plate 403, the second base 401 is vertically disposed on the first frame 1, the second cylinder 402 is disposed on the top of the second base 401, a cylinder rod of the second cylinder 402 is disposed along a vertical direction and is connected to the second material shifting plate 403, a second material shifting surface is disposed on the second material shifting plate 403, and the second material shifting plate 403 is identical to the first material shifting plate 203 in structure, which is not described herein again.
the first clamping mechanism 5 comprises a first clamping base and a first clamping mechanical arm, the first clamping base is arranged at the output end of the first material guiding mechanism 3, and the first clamping mechanical arm is arranged on the first clamping base and is connected with the first clamping base in a sliding mode. Specifically, a sliding rail is arranged on the first clamping base, a sliding block is arranged at the bottom of the first clamping manipulator, and the sliding block can slide on the sliding rail. The top of first centre gripping manipulator is provided with first mechanical gripper claw, and first mechanical gripper claw can the centre gripping nuclear fuel rod. When the first clamping robot slides along the rail, the nuclear fuel rod can be moved in a direction close to the device for nuclear fuel rod surface inspection 300, thereby transferring the nuclear fuel rod into the device for nuclear fuel rod surface inspection 300. In order to prevent the first clamping manipulator from damaging the nuclear fuel rod, a buffer pad is arranged on the first manipulator claw, and the buffer pad can be a pad body made of rubber.
Further, in order to improve the transmission precision of the nuclear fuel rod, as shown in fig. 5, the first clamping mechanism 5 further includes a first guide wheel mechanism 6, the first guide wheel mechanism 6 includes a first guide wheel seat 601 and a first guide wheel 602, a bottom end of the first guide wheel seat 601 is vertically disposed on the first frame 1, a top end of the first guide wheel seat 601 is provided with a rotation groove, the first guide wheel 602 is rotatably connected inside the rotation groove through a rotation shaft, and an outer peripheral surface of the first guide wheel 602 is provided with a guide groove for accommodating the nuclear fuel rod. In the present embodiment, in order to improve the guiding accuracy, the number of the first guide wheel mechanisms 6 is plural, and the plural first guide wheel mechanisms 6 are provided at intervals in the longitudinal direction of the nuclear fuel rod. Portions of the plurality of first guide wheel mechanisms 6 may be disposed on the first clamping base and move along the slide rails in synchronization with the first clamping robot. A protective member made of urethane or the like may be provided in the guide groove of the first guide wheel 602 to prevent the nuclear fuel rod from being damaged by friction with the nuclear fuel rod.
As shown in fig. 6 to 8, the device 300 for detecting the surface of the nuclear fuel rod includes a chuck mechanism 11, a character measurement recognition mechanism 12, a spectrum detection mechanism 13, a laser linear scanning mechanism 14, and a purging mechanism 10, wherein the chuck mechanism 11, the character measurement recognition mechanism 12, the spectrum detection mechanism 13, the laser linear scanning mechanism 14, and the purging mechanism 10 are all disposed on the second frame 9, and are preferably detachably connected by a connecting member, which may be a screw, a rivet, or the like. In order to reduce the vibration caused by workshop and other factors, a marble platform base is arranged on the second frame 9, and the chuck mechanism 11, the character measuring recognition mechanism 12, the spectrum detection mechanism 13, the laser linear scanning mechanism 14 and the blowing mechanism 10 are arranged on the marble platform base.
Wherein, the purging mechanism 10 is arranged at one side of the second frame 9 close to the first frame 1 and is positioned on the transmission path of the nuclear fuel rod. The purging mechanism 10 includes a purging wind generator 1001 and a purging pipe 1002, a gas outlet of the purging wind generator 1001 is communicated with a gas inlet of the purging pipe 1002, and the shape of the purging pipe 1002 is not particularly limited, and may be a straight shape, a U shape, an L shape, or the like. The purge pipe 1002 is provided with purge ports, and the shape and number of the purge ports are not particularly limited, and are preferably plural. The purge wind generator 1001 can generate a purge gas flow and transmit the purge gas flow into the purge tube 1002 and blow out from inside the purge port onto a transmission path of the nuclear fuel rod, and the purge gas flow can blow off dust and foreign substances on the nuclear fuel rod when the nuclear fuel rod passes below the purge port. Further, in this embodiment, the purge wind generator 1001 preferably selects an ion wind generator, so as to generate ion wind, and the ion wind not only can purge foreign matters on the nuclear fuel rod, but also can eliminate static electricity on the surface of the nuclear fuel rod, and has high purge quality.
the chuck mechanism 11 includes a first chuck assembly 1101 and a second chuck assembly 1102 which are spaced apart in a nuclear fuel rod transfer direction, the first chuck assembly 1101 being disposed adjacent to the loading device 200, and the second chuck assembly 1102 being disposed adjacent to the unloading device 400. As shown in fig. 9, the first chuck assembly 1101 includes a first chuck 11011 and a first driving mechanism, the first chuck 11011 is vertically disposed on the second frame 9, an accommodating cavity for accommodating the first clamping seat 11014 is disposed on the first chuck 11011, a through hole for allowing a nuclear fuel rod is disposed in the first clamping seat 11014 along a width direction, and a collet is disposed on the first clamping seat 11014, and the collet can clamp the nuclear fuel rod. The first driving mechanism comprises a motor 11012 and a belt transmission part 11013, the belt transmission part 11013 comprises a belt and two belt pulleys, one belt pulley is sleeved on a motor shaft of the motor 11012, the other belt pulley is arranged on a first clamping seat 11014, the belt pulley can be integrally formed with the first clamping seat 11014 or can be fixedly connected after being arranged in a split mode, and the belt is sleeved on the two belt pulleys. The motor 11012 can drive the belt transmission member 11013 to rotate, thereby driving the first clamping seat 11014 to rotate, and further driving the nuclear fuel rod to rotate. During the test, the rotation speed of the nuclear fuel rod is 0-120 r/min, and the specific rotation speed is specifically set according to specific conditions. Of course, in other embodiments, the first driving mechanism may also be other mechanisms as long as the first clamping seat 11014 can be driven to rotate.
The second chuck assembly 1102 includes a second chuck and a second driving mechanism, the second chuck is provided with a second clamping seat, the structure of the second chuck is the same as that of the first chuck 11011, and the structure of the second clamping seat is the same as that of the first clamping seat 11014, which will not be described herein again. The structure of the second driving mechanism and the structure of the first driving mechanism can be the same or different, and the second clamping seat can be driven to rotate so as to drive the nuclear fuel rod to rotate.
the laser linear scanning mechanism 14 is arranged between the first chuck 11011 and the second chuck, and is used for detecting micro defects such as scratch, air hole, pit, island shape wound, scab and the like on the surface of the nuclear fuel rod, and detecting the micro defectsThe detected defect information is transmitted to the control device of the whole bar stock detection equipment. Specifically, as shown in fig. 10, the laser linear scanning mechanism 14 includes a laser camera 1401 and an image processing unit, the laser camera 1401 can acquire image information of the surface of the nuclear fuel rod and transmit the image information to the image processing unit, and the image processing unit can process the image information to obtain details of each defect on the surface of the nuclear fuel rod, so that the nuclear fuel rod can be classified at a later stage and divided into a qualified product and a non-qualified product. Specific judgment criteria include the following: first, the scratch depth of the surface of the nuclear fuel rod is defined as X1mm; second, the scratch on the surface of the nuclear fuel rod is defined as the circumferential scratch width cumulative Y1mm, longitudinal scratch width accumulation Y2mm; thirdly, the depth of the surface pits of the fuel rod containing scratches and island-shaped scratches is defined as X2mm. In this embodiment, X1、X2、Y1And Y2The specific value of (a) is not limited, and is specifically set according to specific conditions in the actual working process. And when any detected defect condition is higher than the corresponding index, judging that the product is unqualified, and when all detected defects meet the index, judging that the product is qualified.
in order to perform high-speed and comprehensive detection of the nuclear fuel rod, in the embodiment, a plurality of laser cameras 1401 are arranged side by side, so that the single scanning area is increased. The number of the laser cameras 1401 is not particularly limited, and may be, for example, one, two, three, four, or more, and in the present embodiment, four laser cameras 1401 are selectively provided side by side in the transport direction of the nuclear fuel rod. The nuclear fuel rod is positioned above the four laser cameras 1401, and when the nuclear fuel rod rotates, the four laser cameras 1401 can detect the nuclear fuel rod positioned above the nuclear fuel rod in an all-around 360-degree blind-corner-free manner. Because the length of the nuclear fuel rod is long, the four laser cameras 1401 still cannot finish detection at one time, and considering the cost and the volume of the device 300 for detecting the surface of the nuclear fuel rod, in the embodiment, the nuclear fuel rod is selected to be detected for multiple times section by section, and the length of each detection of the nuclear fuel rod is equal to the whole detection length of the four laser cameras 1401 side by side. In the whole detection process, only a few minutes are needed for detecting one nuclear fuel rod, and compared with manual detection, the detection efficiency is higher. Further, in order to improve the moving stability of the nuclear fuel rod and avoid the problem of displacement during the moving process, the device 300 for nuclear fuel rod surface inspection further includes a guide mechanism 15, as shown in fig. 13, the guide mechanism 15 is located between two chuck assemblies, the guide mechanism 15 includes a guide seat 1501, one end of the guide seat 1501 is disposed on the second frame 9, and the other end is provided with a guide hole 1502, and the nuclear fuel rod can pass through the guide hole 1502 and move. The number of the guide means 15 is preferably plural, and the plural guide means 15 are provided on the transfer path of the nuclear fuel rod and are spaced apart along a certain interval.
The spectrum detection mechanism 13 is positioned at one side of the laser linear scanning mechanism 14 and is used for detecting the welding seam between the end plug of the nuclear fuel rod and the rod main body and transmitting the detected welding seam information to the control device of the whole rod detection equipment. Specifically, as shown in fig. 11, the spectrum detection mechanism 13 includes a spectrum confocal camera 1301, and the spectrum confocal camera 1301 can scan the weld joint and acquire the quality information of the weld joint. Because the nuclear fuel rod includes two end plugs, consequently be provided with twice welding seam on a nuclear fuel rod, for the convenience of detecting twice welding seam, this spectrum detection mechanism 13 is still including removing module 1302, remove module 1302 including setting up the cylinder that slides in second frame 9, slide rail seat and the seat that slides, the cylinder pole and the seat that slides of the cylinder that slides are connected, and the seat that slides and spectrum confocal camera 1301 fixed connection, the length direction of slide rail seat is parallel with the transmission direction of nuclear fuel rod, be provided with the spout that is used for with slide rail seat sliding connection on the seat that slides. Driven by the sliding cylinder, the spectral confocal camera 1301 can move along the slide rail seat, so that two welding seams can be detected.
the character measuring and identifying mechanism 12 is located on the other side of the laser linear scanning mechanism 14 and is used for identifying the mark on the nuclear fuel rod and transmitting the obtained mark information to the control device of the whole detection device. The mark on the nuclear fuel rod is composed of character strings, which are the identity information of the nuclear fuel rod, and the detection character recognition mechanism 12 can recognize the identity information of the nuclear fuel rod, so that the defect information obtained by the spectrum detection mechanism 13 and the laser linear scanning mechanism 14 corresponds to the identity information one by one, and later workers can perform recheck on unqualified nuclear fuel rods. Specifically, as shown in fig. 12, the character measurement recognition mechanism 12 includes a character measurement housing 1201, a light source and a detection assembly 1202. The character-measuring frame 1201 is an L-shaped structure, and is vertically disposed on the second frame 9. The light source is disposed on the character-measuring machine frame 1201 and can illuminate the periphery of the nuclear fuel rod. The detection assembly 1202 is capable of recognizing a marker on the nuclear fuel rod, and in this embodiment, the detection assembly 1202 may be a camera.
The operation of the entire device 300 for nuclear fuel rod surface inspection is: the nuclear fuel rod entering the device for nuclear fuel rod surface inspection 300 is first purged by the purge mechanism 10 to remove foreign substances on the surface thereof; then the nuclear fuel rod continues to move for a target length and stops moving, at the moment, the nuclear fuel rod rotates under the clamping action of the chuck mechanism 11, in the rotating process, the detection character recognition mechanism 12 recognizes the mark on the nuclear fuel rod, the laser linear scanning mechanism 14 obtains the defect information on the circumferential surface of the nuclear fuel rod, the spectrum detection mechanism 13 detects the welding line at the end part of the nuclear fuel rod, and transmits the obtained mark information, the defect information and the welding line information to the control device of the whole detection device; and finally, after the detection of one section of the nuclear fuel rod is finished, driving the nuclear fuel rod to move continuously, and detecting the next section of the nuclear fuel rod. Compared with the device for detecting the surface of the nuclear fuel rod in the prior art, the device 300 for detecting the surface of the nuclear fuel rod can detect the micro defects of about 20um on the surface of the nuclear fuel rod and the surface of the welding seam, and has high detection precision.
The present embodiment also provides a testing method for the above device for nuclear fuel rod surface testing, which includes the steps of;
Clamping the bar stock by using a chuck mechanism 11 and driving the bar stock to rotate;
Acquiring complete 3D point cloud data of the surface of the welding seam by using a spectrum detection mechanism 13, and determining the surface defect of the welding seam based on depth information in the complete 3D point cloud data;
and acquiring 3D point cloud data of the cylindrical section to be detected on the surface of the bar by using the laser linear scanning mechanism 14, and determining the surface defect of the bar based on depth information in the 3D point cloud data.
Specifically, when the spectrum detection mechanism 13 is used for detecting the weld surface defects, firstly, the axis line of a nuclear fuel rod is taken as a rotating shaft, the nuclear fuel rod is controlled to rotate at least one circle, and 3D point cloud data of a single cylindrical section on the surface of a detected weld is acquired; then splicing the 3D point cloud data of at least two cylindrical sections to obtain complete 3D point cloud data of the surface of the detected weld joint; and finally, graying the complete 3D point cloud data based on the depth information in the complete 3D point cloud data to generate a gray image, and detecting the defects of the gray image based on the gray value of each point in the gray image and a preset defect condition.
When the laser linear scanning mechanism 14 is used for detecting the surface defects of the bar stock, firstly, the nuclear fuel rod is controlled to rotate in the direction of the axis by taking the axis of the nuclear fuel rod as a rotating shaft, and the laser linear scanning mechanism 14 is controlled to obtain 3D point cloud data of the surface of each group of cylindrical sections to be detected of the nuclear fuel rod; graying is carried out on the basis of depth information in the 3D point cloud data of the surface of each group of cylindrical sections to be detected to obtain a gray image of the surface of each group of cylindrical sections to be detected, and the defects of the surface of each group of cylindrical sections to be detected are determined on the basis of gray values in the gray image of the surface of each group of cylindrical sections to be detected and preset defect conditions; and finally, splicing the defects on the surface of each group of cylindrical sections to be detected based on the position information of the defects on the surface of each group of cylindrical sections to be detected to obtain complete defect information of the surface of the cylindrical section to be detected.
After the nuclear fuel rod is detected, the nuclear fuel rod enters the blanking device 400. The blanking device does not need manual carrying in the whole blanking process, and can effectively avoid abnormal collision and carrying of the bar, thereby reducing the probability of bar damage and being beneficial to improving the yield of the bar. Specifically, as shown in fig. 14 to 16, the blanking device 400 includes a second clamping mechanism 17, and the second clamping mechanism 17 is used for clamping the nuclear fuel rod entering the blanking device 400. Specifically, the second gripper mechanism 17 includes a second gripper base 1701 and a second gripper robot 1702, the second gripper base 1701 being provided on the third frame 16, the second gripper robot 1702 being provided on the second gripper base 1701 and being slidably connected to the second gripper base 1701. Specifically, a guide slide rail 1703 is provided on the second clamp base 1701, and a slider is provided at the bottom of the second clamp robot 1702, the slider being capable of sliding on the guide slide rail 1703. The top of the second clamping robot 1702 is provided with a second gripper robot capable of clamping a nuclear fuel rod. When the second clamping robot 1702 slides along the guide rail 1703, the nuclear fuel rod can be moved in a direction away from the device for nuclear fuel rod surface inspection 300, thereby transferring the nuclear fuel rod to the inside of the unloading device 400. In order to prevent the second clamping robot 1702 from damaging the nuclear fuel rod, a buffer pad may be disposed on the second gripper jaw, and the buffer pad may be a pad made of rubber.
Further, in order to improve the transmission accuracy of the nuclear fuel rod, the second clamping mechanism 17 further includes a second guide wheel mechanism 18, the second guide wheel mechanism 18 includes a second guide wheel seat 1801 and a second guide wheel 1802, a bottom end of the second guide wheel seat 1801 is vertically disposed on the third frame 16, a top end of the second guide wheel seat 1801 is provided with a rotation groove, the second guide wheel 1802 is rotatably connected inside the rotation groove through a rotation shaft, and an outer circumferential surface of the second guide wheel 1802 is provided with a guide groove for receiving the nuclear fuel rod. In the present embodiment, in order to improve the guiding accuracy, the number of the second guide wheel mechanisms 18 is plural, and the plural second guide wheel mechanisms 18 are provided at intervals in the longitudinal direction of the nuclear fuel rod. Portions of the plurality of second guide wheel mechanisms 18 may be disposed on the second clamp base 1701 and moved along the guide slide 1703 in synchronization with the second clamp robot 1702. A protective member made of urethane or the like may be provided in the guide groove of the second guide wheel 1802 so as to prevent the nuclear fuel rod from being damaged by friction with the nuclear fuel rod. Under the action of the second clamping mechanism 17 and the second guide wheel mechanism 18, the nuclear fuel rod can integrally enter the blanking device 400.
In order to facilitate the separate storage of qualified nuclear fuel rods and unqualified nuclear fuel rods, two material shifting mechanisms and two material guiding mechanisms are arranged on the second rack 9. The two material shifting mechanisms are respectively a third material shifting mechanism 19 and a fourth material shifting mechanism 20, and the third material shifting mechanism 19 and the fourth material shifting mechanism 20 are arranged on two sides of the nuclear fuel rod. Specifically, as shown in fig. 17, the third material-shifting mechanism 19 includes a third base 1901, a first material-shifting motor 1902, a first rotating shaft 1903, and a third material-shifting plate 1904, and the third base 1901 is vertically disposed on the third frame 16. In this embodiment, the number of the third bases 1901 and the number of the third material-shifting plates 1904 are plural, the plural third bases 1901 are arranged at intervals along the length direction of the nuclear fuel rod, one end of the third bases 1901 is fixedly connected by a screw, and the other end is provided with a first rotating shaft hole. First pivot 1903 passes a plurality of first pivot holes in proper order and sets up, and the one end of first pivot 1903 is connected with the motor shaft of first material motor 1902, and concretely the connected mode can select the lug connection, also can select to adopt belt module to connect, in this embodiment, selects to adopt belt module to connect. A plurality of third switch plates 1904 are arranged on the first rotating shaft 1903 at intervals, under the driving of the first switch motor 1902, the first rotating shaft 1903 can rotate, so that the third switch plates 1904 can be driven to rotate around the first rotating shaft 1903, and in the rotating process of the third switch plates 1904, one end, far away from the first rotating shaft 1903, of each third switch plate 1904 can be used for pulling up a nuclear fuel rod from the lower part of the nuclear fuel rod and pulling the nuclear fuel rod to a corresponding guide mechanism.
the fourth material ejecting mechanism 20 has the same structure as the third material ejecting plate 1904, and is symmetrically disposed with respect to the nuclear fuel rod. The fourth material shifting mechanism 20 includes a fourth base, a second material shifting motor, a second rotating shaft, and a fourth material shifting plate, and the fourth base is vertically disposed on the third frame 16. In this embodiment, the number of the fourth bases and the number of the fourth material shifting plates are both multiple, the multiple fourth bases are arranged at intervals along the length direction of the nuclear fuel rod, one end of each fourth base is fixedly connected through a screw, and the other end of each fourth base is provided with a second rotating shaft hole. The second pivot passes a plurality of second pivot holes in proper order and sets up, and the one end of second pivot is connected with the motor shaft of second group material motor, and concretely connected mode can select the lug connection, also can select to adopt belt subassembly to connect, in this embodiment, selects to adopt belt subassembly to connect. A plurality of fourth switch plates are arranged on the second rotating shaft at intervals, the second rotating shaft can rotate under the driving of a second switch plate motor, so that the fourth switch plates can be driven to rotate around the second rotating shaft, and in the rotating process of the fourth switch plates, one ends, far away from the second rotating shaft, of the fourth switch plates can be used for shifting up the nuclear fuel rods from the lower portions of the nuclear fuel rods and shifting the nuclear fuel rods to the corresponding guide mechanisms.
The two material guiding mechanisms are respectively a second material guiding mechanism 21 and a third material guiding mechanism 22, and the second material guiding mechanism 21 and the third material guiding mechanism 22 are respectively located at two sides of the second clamping mechanism 17 and the second guide wheel mechanism 18. That is, the second guide mechanism 21 and the third guide mechanism 22 are located at both sides of the nuclear fuel rod, the second guide mechanism 21 is used for guiding out the failed nuclear fuel rod to the failure area, and the third guide mechanism 22 is used for guiding out the qualified nuclear fuel rod to the failure area.
The second guide mechanism 21 and the third guide mechanism 22 have the same structure, the second guide mechanism 21 includes a second guide base 2101 and a second guide plate 2102, the second guide base 2101 is vertically disposed on the third frame 16, the second guide plate 2102 is disposed on the top of the second guide base 2101, and a second guide surface is disposed on the second guide plate 2102, and the inclination angle of the second guide surface is preferably between 1.0-10.0 °, and may be, for example, 1.0 °, 2.5 °, 3.4 °, 4.2 °, 5.6 °, 6.3 °, 7.7 °, 8.9 °, 9.0 ° or 10.0 °.
The third material guiding mechanism 22 includes a third material guiding base and a third material guiding plate, the third material guiding base is vertically disposed on the third frame 16, the third material guiding plate is disposed on the top of the third material guiding base, a third material guiding surface is disposed on the third material guiding plate of the third material guiding mechanism 22, and the third material guiding surface and the second material guiding surface have opposite inclination directions, so that the second material guiding plate 2102 and the third material guiding plate are arranged in a triangular shape. The angle of inclination of the third guiding surface is preferably between 1.0-10.0 °, and may be, for example, 1.0 °, 2.4 °, 3.5 °, 4.6 °, 5.2 °, 6.7 °, 7.3 °, 8.8 °, 9.4 °, or 10.0 °. The inclination angles of the third material guiding surface and the second material guiding surface can be controlled respectively, and are not limited specifically herein. Since there are more qualified nuclear fuel rods and less unqualified nuclear fuel rods, it is preferable to set the length of the third guide plate to be greater than that of the second guide plate 2102 in order to accommodate more nuclear fuel rods. Since the heights of the third material guiding base and the second material guiding base 2101 are equal, the inclination angles of the third material guiding surface and the second material guiding surface are different in this embodiment.
Further, a second material guiding plate 2102 is detachably connected with the second material guiding base 2101 so as to adjust the inclination angle of the second material guiding surface according to requirements. Because the nuclear fuel rod is long, in order to reduce the manufacturing cost and the installation difficulty of the second material guiding mechanism 21, as shown in the first material guiding mechanism 3, the second material guiding base 2101 may be also configured as a plurality of narrow bases and narrow material guiding plates with small widths, the narrow material guiding plates are located above the narrow bases, and the plurality of narrow bases are spaced apart from each other to have a large supporting area. The narrow base and the sub-base have the same structure, and are not described in detail herein.
When the narrow stock guide stroke is longer, when being provided with many nuclear fuel rods on it, in order to segment the stroke of narrow stock guide, with a plurality of nuclear fuel rods that will be located on the narrow stock guide separately set up, so that can realize that nuclear fuel rods recheck and accomodate one by one, and reduce the pressure that is located bottommost layer nuclear fuel rod and receives, be provided with a plurality of second spacer blocks 2103 along the guide direction interval on the narrow stock guide, a plurality of second spacer blocks 2103 divide into a plurality of accommodation spaces with the narrow stock guide, can set up one or many nuclear fuel rods in each accommodation space, it is preferred one, in order to avoid unusual collision between a plurality of nuclear fuel rods, reduce the friction between the nuclear fuel rod, thereby guarantee the integrality of the inside uranium dioxide pellet of nuclear fuel rod, improve the quality of nuclear fuel rod. In order to realize the transmission of the nuclear fuel rods between the adjacent accommodating spaces, a second rod pushing mechanism 23 is arranged at the side of the narrow guide plate where the second barrier block 2103 is arranged. The second push rod mechanism 23 is identical to the first push rod mechanism 7 in structure, the second push rod mechanism 23 comprises a second push rod cylinder and a second push rod block, the second push rod cylinder is arranged on the side portion of the narrow base, and a cylinder rod of the second push rod cylinder is vertically arranged upwards and fixedly connected with the second push rod block. The second push rod block comprises a second connecting portion and a second push finger portion, the second connecting portion is a rectangular block, and the second push finger portion is a wedge-shaped block. In order to prevent the nuclear fuel rod from violently colliding with the second barrier block 2103 due to the fact that the nuclear fuel rod is accelerated too much in the rolling process, a protective element made of polyurethane materials and the like can be arranged on the second barrier block 2103. In addition to the guard elements, it is of course possible to reduce the speed of the nuclear fuel rod by using a speed reduction mechanism such as a hydraulic shock absorber. Of course, in other embodiments, the second barrier blocks 2103 and the shielding elements may not be provided if the stroke of the narrow guide plate is short, or only one nuclear fuel rod is provided on the narrow guide plate at a time.
When the nuclear fuel rod is blocked by the second barrier block 2103, the second rod pushing mechanism 23 is located just under the nuclear fuel rod, when the nuclear fuel rod needs to be transferred to the next accommodating space, the cylinder rod of the first rod pushing cylinder 701 of the second rod pushing mechanism 23 moves upwards, the first pushing portion of the first rod pushing block 702 of the second rod pushing mechanism 23 pushes up the nuclear fuel rod, and the nuclear fuel rod moves along the wedge-shaped surface of the first rod pushing block 702 under the action of gravity, so that the nuclear fuel rod passes through the second barrier block 2103 and reaches the next accommodating space. The number of the second rod pushing mechanisms 23 is not limited, and may be one, two or more, and preferably, one second rod pushing mechanism 23 is provided at a side portion of each narrow base, so as to improve the stability of the nuclear fuel rod in the adjacent accommodating space.
When nuclear fuel rod was located the second in last accommodation space and separates shelves piece 2103 department, the staff can carry out reinspection and accomodate nuclear fuel rod, and the security is higher. In order to facilitate the recheck of the workers, the control device can be connected with the printing equipment so as to print out a defective rod list, the defective rod list can list information including the rod number, the defect position, the defect type, the defect size and the like of the nuclear fuel rods, so that the workers can recheck the nuclear fuel rods by using a microscope according to the defective rod list, and after the recheck is completed, the nuclear fuel rods with problems are determined to be bundled by using rubber bands and then are put into a recycling mechanism to be recycled. The whole bar detecting equipment has high detecting precision, the detecting precision in the length direction and the width direction can be not less than 0.01mm, the detecting precision in the depth direction can be not less than 0.005mm, the detecting repeatability can be not less than 0.002mm, the automation degree and the detecting effect of the detection are improved to a great extent, and the detection of the whole bar detecting equipment is fast and efficient.
It is obvious that the above embodiments of the present invention are only examples for clearly illustrating the present invention, and are not intended to limit the embodiments of the present invention. Other variations and modifications will be apparent to persons skilled in the art in light of the above description. And are neither required nor exhaustive of all embodiments. Any modification, equivalent replacement, and improvement made within the spirit and principle of the present invention should be included in the protection scope of the claims of the present invention.
Claims (10)
1. Device for nuclear fuel rod surface inspection, comprising a second frame (9), characterized in that it further comprises:
the chuck mechanism (11) is arranged on the second rack (9) and used for clamping the bar stock and driving the bar stock to rotate;
the spectrum detection mechanism (13) is arranged on the second rack (9), is positioned on one side of the chuck mechanism (11) and is used for detecting the defects on the surface of the weld joint at the end part of the bar stock;
The laser linear scanning mechanism (14), the laser linear scanning mechanism (14) is arranged on the second rack (9) and is used for detecting the defects of the surface of the bar stock;
and the control device is in communication connection with the chuck mechanism (11), the spectrum detection mechanism (13) and the laser linear scanning mechanism (14).
2. the device for nuclear fuel rod surface inspection (300) of claim 1 further comprising:
The purging mechanism (10) is arranged on the second rack (9) and located on the transmission path of the bar, the purging mechanism (10) comprises a purging wind generator (1001) and a purging pipe (1002), a gas outlet of the purging wind generator (1001) is communicated with a gas inlet of the purging pipe (1002), and a purging opening is formed in the purging pipe (1002).
3. The device for nuclear fuel rod surface inspection of claim 2,
The blowing wind generator (1001) is an ion wind generator.
4. The device for nuclear fuel rod surface inspection of claim 1, wherein,
the chuck mechanism (11) comprises a first chuck assembly (1101) and a second chuck assembly (1102) which are arranged at intervals along the length direction of the bar stock, and through holes allowing the bar stock to pass through are formed in the first chuck assembly (1101) and the second chuck assembly (1102).
5. the device for nuclear fuel rod surface inspection of claim 4, wherein,
The first chuck assembly (1101) comprises a first chuck (11011) and a first driving mechanism, the first chuck (11011) is arranged on the second rack (9), a first clamping seat (11014) is arranged on the first chuck (11011), the through hole is formed in the first clamping seat (11014), and the first driving mechanism is in transmission connection with the first clamping seat (11014) and is used for driving the first clamping seat (11014) to rotate;
The second chuck assembly (1102) comprises a second chuck and a second driving mechanism, the second chuck is arranged on the second rack (9), a second clamping seat is arranged on the second chuck, the through hole is formed in the second clamping seat, and the second driving mechanism is in transmission connection with the second clamping seat and is used for driving the second clamping seat to rotate;
The first clamping seat (11014) and the second clamping seat are provided with clamping heads along the circumferential direction of the through hole.
6. the device for nuclear fuel rod surface inspection (300) of claim 4 further comprising:
a guide mechanism (15), wherein the guide mechanism (15) is arranged on the second frame (9) and is positioned between the first chuck assembly (1101) and the second chuck assembly (1102), and a guide hole (1502) allowing the bar stock to pass through is arranged on the guide mechanism (15).
7. the device for nuclear fuel rod surface inspection (300) of claim 1 further comprising:
and the character detection recognition mechanism (12) is arranged on the second rack (9) and is used for recognizing the mark on the bar stock.
8. The device for nuclear fuel rod surface inspection of claim 7, wherein,
The character measuring recognition mechanism (12) comprises a character measuring rack (1201), a light source and a detection assembly (1202), the character measuring rack (1201) is arranged on the second rack (9), the light source and the detection assembly (1202) are arranged on the character measuring rack (1201), and the detection assembly (1202) is used for acquiring the mark on the bar stock.
9. The device for nuclear fuel rod surface inspection of claim 1, wherein,
The spectrum detection mechanism (13) comprises a spectrum confocal camera (1301) and a moving module (1302), wherein the spectrum confocal camera (1301) is arranged on the moving module (1302), and the moving module (1302) can drive the spectrum confocal camera (1301) to slide.
10. The device for nuclear fuel rod surface inspection of claim 1, wherein,
The laser linear scanning mechanism (14) comprises a laser camera (1401) and an image processing component, wherein the laser camera (1401) is electrically connected with the image processing component, and the laser camera (1401) can acquire image information of the surface of the bar stock and transmit the image information to the image processing component.
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| CN201920410473.7U CN209764753U (en) | 2019-03-28 | 2019-03-28 | Device for detecting surface of nuclear fuel rod |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN109827972A (en) * | 2019-03-28 | 2019-05-31 | 中核建中核燃料元件有限公司 | A kind of device and its detection method for nuclear fuel rod Surface testing |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109827972A (en) * | 2019-03-28 | 2019-05-31 | 中核建中核燃料元件有限公司 | A kind of device and its detection method for nuclear fuel rod Surface testing |
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