CN209691405U - A kind of equipment for nuclear fuel rod Surface testing - Google Patents
A kind of equipment for nuclear fuel rod Surface testing Download PDFInfo
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- CN209691405U CN209691405U CN201920409646.3U CN201920409646U CN209691405U CN 209691405 U CN209691405 U CN 209691405U CN 201920409646 U CN201920409646 U CN 201920409646U CN 209691405 U CN209691405 U CN 209691405U
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- nuclear fuel
- fuel rod
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- clamping
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model discloses a kind of equipment for nuclear fuel rod Surface testing, belong to technical field of automation equipment.The equipment includes detection device, feeding device, blanking device and control device, it can be realized the automatic charging of bar by the way that feeding device is arranged, by setting detection device can to by glyphomancy symbol identification mechanism identification after the surface tiny flaw of bar and the tiny flaw of end weld accurately detected, it can be realized the automatic blanking of bar by the way that blanking device is arranged, and the bar being verified is delivered to by qualified area and unqualified area according to the testing result of detection device, so that bar of the operator to unqualified area is rechecked.Not only integration degree is high for whole equipment, high degree of automation, detection efficiency are high, required operator is few, and the tiny flaw for capableing of tiny flaw and end of welding bead to billet surface is detected automatically, be conducive to improve detection accuracy, guarantee the safety in utilization of bar.
Description
Technical field
The utility model relates to technical field of automation equipment more particularly to a kind of setting for nuclear fuel rod Surface testing
It is standby.
Background technique
Nuclear fuel rod is first of safety curtain of nuclear reactor, to preventing nuclear leakage from playing a crucial role.Core
Fuel rod clad surface and the exceeded breakage that may cause nuclear fuel rod of face of weld defect, directly influence nuclear power plant reactor
Safe operation.
At present to the surface inspecting method of fuel rod be usually manually visualize check, discovery defect again be measured microscopically hurt
Deep, low efficiency is easy to miss inspection.Other than using detection is manually visualized, ultrasound and eddy detection technology are also used to detect nuclear fuel rod
Defect, but it is usually to detect involucrum internal flaw.X-ray can also be used for detection nuclear fuel rod defect, be usually to examine
Survey weld seam internal porosity, fusion penetration etc..The detection sensitivity of these technologies can not find the tiny flaw of fuel rod surface, such as whirlpool
Stream minimum can find the defect of 30um, and be influenced by direction, and to nuclear fuel pencil cladding surface and face of weld 20um or so
Critical defective can not also be detected automatically.In addition, the equipment in the prior art for being detected to nuclear fuel rod is automatic
Change degree is lower, can not automatic charging and blanking, integrated level is lower, and detection efficiency is lower, the larger workload of testing staff.
Therefore, it needs to propose that one kind can not only examine nuclear fuel pencil cladding surface and face of weld tiny flaw
It surveys, and high degree of automation, can be realized the nuclear fuel rod detection device of automatic charging and blanking.
Utility model content
The purpose of this utility model is to provide a kind of equipment for nuclear fuel rod Surface testing, this is used for nuclear fuel rod
The automation degree of equipment of Surface testing is higher, integrated level is high, detection efficiency and precision are high, is able to detect tiny flaw.
For this purpose, the utility model uses following technical scheme:
A kind of equipment for nuclear fuel rod Surface testing, including rack further include being arranged in the rack:
Detection device, the detection device include spectral detection mechanism, the linear sweep mechanism of laser and survey character recognition machine
Structure, the spectral detection mechanism are used to detect the defect on bar end weld surface, and the linear sweep mechanism of laser is for examining
The defect of the billet surface is surveyed, the glyphomancy symbol identification mechanism is for identifying the mark on the bar；
Feeding device, the feeding device is located at the input terminal of the detection device, for the bar to be delivered to institute
It states in detection device；
Blanking device, the blanking device are located at the output end of the detection device, and the blanking device can be according to institute
The bar is delivered to qualified area or unqualified area by the testing result for stating detection device；
Control device, the control device and the detection device, the feeding device and blanking device communication connect
It connects.
Preferably, the detection device further include:
Blowing mechanism, the blowing mechanism are located in the detection device, and are located in the transmission path of the bar, institute
Stating blowing mechanism includes purging air generator and scavenging conduit, the air inlet of the gas outlet for purging air generator and the scavenging conduit
Mouth is connected to, and is provided with blow valve port on the scavenging conduit.
Preferably, the detection device further include:
Chuck mechanism, the chuck mechanism include along the bar spaced first chuck assembly of transmission direction and
Allow the bar to pass through logical is provided on second chuck assembly, first chuck assembly and second chuck assembly
Hole.
Preferably, first chuck assembly includes the first chuck and the first driving mechanism, the first chuck setting
In the rack, the first clamping seat is provided on first chuck, the through-hole setting is on the first clamping seat, institute
The first driving mechanism and the first clamping seat transmission connection are stated, for driving the first clamping seat rotation；
Second chuck assembly includes the second chuck and the second driving mechanism, and second chuck is arranged in the rack
On, the second clamping seat is provided on second chuck, the through-hole setting is on the second clamping seat, second driving
Mechanism and the second clamping seat transmission connection, for driving the second clamping seat rotation；
Described first, which is clamped seat and the second clamping seat, is provided with collet along the circumferential direction of the through-hole.
Preferably, the feeding device includes:
First material guide mechanism of several spacing side by side setting, the conveying outside the input terminal of first material guide mechanism is corresponding
Line is tiltedly installed with the first guide face, institute on first material guide mechanism to receive the bar that the pipeline conveying comes
Stating bar can roll on first guide face；
First clamping device, first clamping device are located at the output end of first material guide mechanism, first folder
Hold mechanism be configured to receive by first material guide mechanism convey Lai the bar and the bar is delivered to institute
It states in detection device, first clamping device and the control device communication connection.
Preferably, the feeding device further include:
First guide wheel mechanism, first guide wheel mechanism include the first wheel stand and the first guide wheel, the setting of the first wheel stand
In the rack, first guide wheel is rotatably connected on first wheel stand, is set on the outer peripheral surface of first guide wheel
It is equipped with the guide groove for accommodating the bar.
Preferably, being provided with the first baffle block on first guide face, the first baffle block is led described first
Charge level is divided into multiple accommodating spaces, and the side of the first baffle block is provided with the first rod pushing mechanism, first rod pushing mechanism
For pushing the bar to move between the adjacent accommodating space.
Preferably, the blanking device includes the second clamping device, second clamping device includes the second clamping bottom
Seat and the second clamping manipulator, second Holding seat are arranged in the rack, and the second clamping manipulator setting exists
On second Holding seat, and it is slidably connected with second Holding seat.
Preferably, the blanking device further include:
Second material guide mechanism and third material guide mechanism, second material guide mechanism and the third material guide mechanism are located at
The two sides of second clamping device, to receive the bar from second clamping device, second material guide mechanism
It is configured as exporting the underproof bar to unqualified area, the third material guide mechanism is configured as will be described in qualification
Bar is exported to qualified area.
The utility model has the beneficial effects that
The utility model provides a kind of equipment for nuclear fuel rod Surface testing, this is used for nuclear fuel rod Surface testing
Equipment include detection device, feeding device, blanking device and control device, can be realized bar by the way that feeding device is arranged
Automatic charging, by setting detection device can to by glyphomancy symbol identification mechanism identification after billet surface tiny flaw with
And the tiny flaw of end weld is detected, and can be realized the automatic blanking of bar by the way that blanking device is arranged, and according to inspection
The bar being verified is delivered to qualified area and unqualified area by the testing result for surveying device, so that operator is to unqualified area
Bar rechecked.Not only integration degree is high, high degree of automation, inspection for the entire equipment for nuclear fuel rod Surface testing
Survey that high-efficient, required operator is few, and the tiny flaw for capableing of tiny flaw and end of welding bead to billet surface carries out
Automatic detection is conducive to improve detection accuracy, guarantees the safety in utilization of bar.
Detailed description of the invention
Fig. 1 is the structural schematic diagram of the equipment provided by the utility model for nuclear fuel rod Surface testing；
Fig. 2 is the structural schematic diagram of feeding device provided by the utility model；
Fig. 3 is the side view of feeding device provided by the utility model；
Fig. 4 is that feeding device provided by the utility model hides the structural schematic diagram after the first rack；
Fig. 5 is the structural schematic diagram of the first guide wheel mechanism and the second allocation mechanism provided by the utility model；
Fig. 6 is the structural schematic diagram of detection device provided by the utility model；
Fig. 7 is the side view of detection device provided by the utility model；
Fig. 8 is the top view of detection device provided by the utility model；
Fig. 9 is the structural schematic diagram of chuck mechanism provided by the utility model；
Figure 10 is the structural schematic diagram of the linear sweep mechanism of laser provided by the utility model；
Figure 11 is the structural schematic diagram of spectral detection mechanism provided by the utility model；
Figure 12 is the structural schematic diagram of glyphomancy symbol identification mechanism provided by the utility model；
Figure 13 is the structural schematic diagram of guiding mechanism provided by the utility model；
Figure 14 is the structural schematic diagram of blanking device provided by the utility model；
Figure 15 is that blanking device provided by the utility model hides the structural schematic diagram after third rack；
Figure 16 is the side view of blanking device provided by the utility model；
Figure 17 is that the mechanism of the provided third allocation mechanism of the utility model, the second guide wheel mechanism and the 4th allocation mechanism shows
It is intended to.
In figure:
100, rack；200, feeding device；300, detection device；400, blanking device；
1, the first rack；2, the first allocation mechanism；201, first base；202, the first cylinder；203, the first switch-plate；
3, the first material guide mechanism；301, the first guide pedestal；302, the first stock guide；303, the first baffle block；
4, the second allocation mechanism；401, second base；402, the second cylinder；403, the second switch-plate；
5, the first clamping device；
6, the first guide wheel mechanism；601, the first wheel stand；602, the first guide wheel；
7, the first rod pushing mechanism；701, the first rod pushing jug；702, the first push rod block；
8, baffle；
9, the second rack；10, blowing mechanism；1001, air generator is purged；1002, scavenging conduit；
11, chuck mechanism；1101, the first chuck assembly；11011, the first chuck；11012, motor；11013, belt passes
Moving part；11014, the first clamping seat；1102, the second chuck assembly；
12, glyphomancy symbol identification mechanism；1201, glyphomancy symbol rack；1202, detection components；
13, spectral detection mechanism；1301, Spectral Confocal camera；1302, mobile mould group；
14, the linear sweep mechanism of laser；1401, laser camera；
15, guiding mechanism；1501, guide holder；1502, pilot hole；
16, third rack；
17, the second clamping device；1701, the second Holding seat；1702, the second clamping manipulator；1703, directive slide track；
18, the second guide wheel mechanism；1801, the second wheel stand；1802, the second guide wheel；
19, third allocation mechanism；1901, third pedestal；1902, the first material toggling motor；1903, first rotating shaft；1904,
Three switch-plates；20, the 4th allocation mechanism；
21, the second material guide mechanism；2101, the second guide pedestal；2102, the second stock guide；2103, the second baffle block；
22, third material guide mechanism；23, the second rod pushing mechanism.
Specific embodiment
The technical solution of the utility model is clearly and completely described below in conjunction with attached drawing, it is clear that described
Embodiment is the utility model a part of the embodiment, instead of all the embodiments.Based on the embodiments of the present invention, originally
Field those of ordinary skill every other embodiment obtained without making creative work belongs to practical
Novel protected range.
It is in the description of the present invention, it should be noted that term " center ", "upper", "lower", "left", "right", " perpendicular
Directly ", the orientation or positional relationship of the instructions such as "horizontal", "inner", "outside" is to be based on the orientation or positional relationship shown in the drawings, and is only
For ease of description the utility model and simplify description, rather than the device or element of indication or suggestion meaning must have it is specific
Orientation, be constructed and operated in a specific orientation, therefore should not be understood as limiting the present invention.In addition, term " the
One ", " second ", be used for descriptive purposes only and cannot be understood as indicating or suggesting relative importance.Wherein, term " first
Set " and " second position " be two different positions.
In the description of the present invention, it should be noted that unless otherwise clearly defined and limited, term " is pacified
Dress ", " connected ", " connection " shall be understood in a broad sense, for example, it may be being fixedly connected, may be a detachable connection；It can be machine
Tool connection, is also possible to be electrically connected；It can be directly connected, two members can also be can be indirectly connected through an intermediary
Connection inside part.For the ordinary skill in the art, it can understand that above-mentioned term is practical new at this with concrete condition
Concrete meaning in type.
A kind of equipment for nuclear fuel rod Surface testing is present embodiments provided, this is used for nuclear fuel rod Surface testing
Equipment can scuffing to billet surface, pit, island shape wound, leprosy scar the defects of and bar on the tiny flaw of weld seam examine
It surveys.In the present embodiment, bar refers to that cylindrical nuclear fuel rod, nuclear fuel rod include the bar main body of coaxial arrangement and set
Set the end plug in bar main body two sides.End plug is connected by the way of welding with bar main body, in the company of end plug and bar main body
There is circular weld at the place of connecing.Certainly in other embodiments, it also can use the equipment detection for nuclear fuel rod Surface testing
The barred body of other purposes, does not enumerate herein.
As shown in Figure 1, the equipment for being used for nuclear fuel rod Surface testing includes rack 100 and is arranged in rack 100
Feeding device 200, detection device 300 and blanking device 400.Rack 100 is the frame structure formed using sheet metal component assembly, tool
There are the advantages such as stability of strutting system is high and manufacturing cost is low.It, can be in frame structure in order to improve the structural strength of rack 100
The structures such as upper setting reinforcing rib.Rack 100 can be structure as a whole, or separate structure, in the present embodiment, in order to just
In manufacture and installation frame 100, rack 100 is set separate structure by selection.Specifically, which includes being arranged side by side
The first rack 1, the second rack 9 and third rack 16, feeding device 200 be arranged in the first rack 1, detection device 300 is set
It sets in the second rack 9, blanking device 400 is arranged in third rack 16.Detection device 300 is located at feeding device 200 under
Expect between device 400, feeding device 200 is connected to the input terminal of detection device 300, blanking device 400 and detection device 300
Output end connection, feeding device 200 can be realized automatic charging, nuclear fuel rod are transmitted in detection device 300 by root, detect
Device 300 can the defect in the bar main body to nuclear fuel rod detect, and can be between bar main body and end plug
Weld seam is detected, and is detected the nuclear fuel rod finished and is entered in blanking device 400 from detection device 300,400 basis of blanking device
Qualified nuclear fuel rod and underproof nuclear fuel rod are transmitted to different zones and stored by testing result.
Feeding device does not need artificially to carry in entire feeding process, can be effectively prevented from the abnormal collision of bar
And carrying is conducive to the yields for improving bar to reduce the impaired probability of bar.Specifically, as shown in Figures 2 to 4,
Feeding device 200 includes the first allocation mechanism 2, the first material guide mechanism 3, the second allocation mechanism 4 and the first clamping device 5.Wherein,
The input terminal of the first material guide mechanism 3 is arranged in first allocation mechanism 2, can be by nuclear fuel rod by pipeline (not shown)
It is allocated on the first material guide mechanism 3.Pipeline is mainly used for transmitting nuclear fuel rod, realizes automatic charging, in the present embodiment, conveying
Line can be belt mechanism or manipulator etc., be not particularly limited herein, as long as nuclear fuel rod can be transmitted to first group
Expect at mechanism 2.
First allocation mechanism 2 includes first base 201, the first cylinder 202 and the first switch-plate 203, and first base 201 is hung down
Straight to be arranged in the first rack 1, in the present embodiment, first base 201 is L-type, the transverse slat of first base 201 and the first rack
1 is fixedly connected by screw, and the riser of first base 201 is vertically arranged with the first rack 1.First cylinder 202 is fixedly mounted on
The riser side of first base 201, and the cylinder rod of the first cylinder 202 is arranged vertically upwards, the cylinder rod of the first cylinder 202
Top is fixedly connected with the first switch-plate 203.Under the driving of the first cylinder 202, the first switch-plate 203 can be along the vertical direction
It moves up and down, to keep the first switch-plate 203 concordant with the first material guide mechanism 3, and nuclear fuel rod disposed thereon is allocated to
On one material guide mechanism 3.In order to be rolled to nuclear fuel rod automatically on the first material guide mechanism 3, it is arranged at the top of the first switch-plate 203
There is inclined first material toggling face, the first material toggling face is higher than the first material toggling face far from one end of the first material guide mechanism 3 and leads close to first
Expect one end of mechanism 3.The higher one end of first switch-plate 203 can provoke nuclear fuel rod from pipeline, in the work of gravity
Under, nuclear fuel rod can face the lower side roll of the first switch-plate 203 along the first material toggling, to be rolled to and the first material toggling
On the first material guide mechanism 3 that the lower one end of plate 203 abuts.
First material guide mechanism 3 includes the first guide pedestal 301 and the first stock guide 302, and the first guide pedestal 301 is vertically set
It sets in the first rack 1, the top of the first guide pedestal 301 is arranged in the first stock guide 302, and sets on the first stock guide 302
Be equipped with the first guide face, the inclined direction in the first guide face is identical as the inclined direction in the first material toggling face, the first stock guide 302 compared with
High one end is arranged with the lower one end face of the first switch-plate 203.The tilt angle in the first guide face preferably 1-10 ° it
Between, such as can be 1 °, 3 °, 5 °, 8 ° or 10 °.Further, the first stock guide 302 and the first guide pedestal 301 are detachable
Connection, to adjust the tilt angle in the first guide face according to demand.It is led when nuclear fuel rod is allocated to first by the first allocation mechanism 2
When expecting in mechanism 3, nuclear fuel rod can be rolled along the first guide face by the higher one end of the first stock guide 302 under gravity
To lower one end.
Since the length of nuclear fuel rod is longer, in order to reduce the cost of manufacture and installation difficulty of the first material guide mechanism 3, at this
In embodiment, the first guide pedestal 301 is arranged to be formed using the lesser sub- pedestal interval of multiple width for selection, the first stock guide
302 are arranged to be formed using the lesser sub- stock guide interval of multiple width, and the quantity of the quantity of sub- pedestal and sub- stock guide is equal, often
A sub- stock guide is provided at the top of one sub- pedestal.Sub- pedestal is integrally U-shaped comprising crossbeam and is vertically set on crossbeam
The vertical beam at both ends, crossbeam are fixedly connected with the first rack 1, and vertical beam is vertically arranged, and the top of two vertical beams respectively with sub- guide
The both ends of plate are detachably connected.
Group stock guide stroke is longer, when being provided with more nuclear fuel rods, in order to which sub- stock guide stroke is segmented, with
More nuclear fuel rods being located on sub- stock guide are provided separately, so as to realize transmitting by root and examining by root for nuclear fuel rod
It surveys, is arranged at intervals with multiple first baffle blocks 303 along guide direction on sub- stock guide, multiple first baffle blocks 303 lead son
Flitch is divided into multiple accommodating spaces, and a nuclear fuel rod is preferably provided in each accommodating space, to avoid more nuclear fuel rods
Between abnormal collision, reduce nuclear fuel rod between friction, to guarantee the complete of nuclear fuel rod inner silica uranium pellet
Whole property, improves the quality of nuclear fuel rod.In order to realize transmission of the nuclear fuel rod between adjacent accommodating space, set in sub- stock guide
The side for setting the first baffle block 303 is provided with the first rod pushing mechanism 7.First rod pushing mechanism 7 includes the first rod pushing jug 701 and the
The side of sub- pedestal is arranged in one push bar block 702, the first rod pushing jug 701, and the cylinder rod of the first rod pushing jug 701 is straight up
Setting, and be fixedly connected with the first push rod block 702.First push rod block 702 includes first connecting portion and first pushes away finger portion, and first connects
Socket part is rectangular block, and first pushes away finger portion as wedge block.In order to avoid acceleration is excessive with first during scrolling for nuclear fuel rod
Sharp impacts occur for baffle block 303, and protective element made of polyurethane material etc. can also be arranged on the first baffle block 303.
Other than protective element, naturally it is also possible to be reduced using speed of the decelerations such as hydraulic bjuffer mechanism to nuclear fuel rod.When
So in other embodiments, if the stroke of stock guide is shorter or stock guide on a nuclear fuel rod is only set every time, can also
It is not provided with the first baffle block 303 and protective element.
When nuclear fuel rod is stopped by the first baffle block 303, the first most significant end for pushing away finger portion is located just at nuclear fuel rod
Underface, when needing to shift nuclear fuel rod to next accommodating space, the cylinder rod of the first rod pushing jug 701 is moved up, the
The first of one push bar block 702 pushes away finger portion and jacks up nuclear fuel rod, and nuclear fuel rod is moved along the lozenges of wedge block under the effect of gravity
It is dynamic, so that crossing the first baffle block 303 reaches next accommodating space.The quantity of first rod pushing mechanism 7 can be one with no restrictions
It is a, two or more, preferably first rod pushing mechanism 7 is provided in the side of each sub- pedestal, to improve core
The stability that fuel rod shifts in adjacent accommodating space.Further, in order to avoid the first rod pushing mechanism 7 pushes away nuclear fuel rod
Partially, it is additionally provided with baffle 8 along the two sides of nuclear fuel rod length direction in the first material guide mechanism 3, baffle 8 can be by fuel rod or so
Alignment, consequently facilitating feeding.One of baffle 8 in two baffles 8 is fixed, another baffle 8 can transverse shifting,
To adapt to the adjustment of width between the two.
At the first baffle block 303 that nuclear fuel rod reaches the last one accommodating space, positioned at the defeated of the first material guide mechanism 3
Nuclear fuel rod can be allocated at the first clamping device 5 by the second allocation mechanism 4 of outlet.As shown in figure 5, the second allocation mechanism 4
Including second base 401, the second cylinder 402 and the second switch-plate 403, second base 401 is vertically set in the first rack 1,
The top of second base 401 is arranged in second cylinder 402, and the cylinder rod of the second cylinder 402 is arranged along the vertical direction, and with second
Switch-plate 403 connects, and is provided with the second material toggling face on the second switch-plate 403, the second switch-plate 403 and the first switch-plate 203
Structure is identical, and details are not described herein.
First clamping device 5 includes the first Holding seat and the first clamping manipulator, and the first Holding seat is arranged first
The output end of material guide mechanism 3, the first clamping manipulator are arranged on the first Holding seat, and slide and connect with the first Holding seat
It connects.Specifically, it is provided with sliding rail on the first Holding seat, the bottom of the first clamping manipulator is provided with sliding block, and sliding block can be
It is slided on sliding rail.The first mechanical paw is provided at the top of first clamping manipulator, the first mechanical paw can clamp nuclear fuel
Stick.When the first clamping manipulator is slided along sliding rail, nuclear fuel rod can be moved along the direction close to detection device 300, thus
Nuclear fuel rod is transmitted in detection device 300.In order to avoid the first clamping manipulator damages nuclear fuel rod, in the first manipulator
Cushion is provided on pawl, cushion can be using pad made of rubber.
Further, in order to improve the transmission precision of nuclear fuel rod, as shown in figure 5, first clamping device 5 further includes
One guide wheel mechanism 6, the first guide wheel mechanism 6 include the first wheel stand 601 and the first guide wheel 602, and the bottom end of the first wheel stand 601 is hung down
Straight to be arranged in the first rack 1, the top of the first wheel stand 601 is provided with rotation slot, and the first guide wheel 602 is rotated by shaft to be connected
It connects inside rotation slot, the guide groove for accommodating nuclear fuel rod is provided on the outer peripheral surface of the first guide wheel 602.In the present embodiment
In, in order to improve guiding accuracy, the quantity of the first guide wheel mechanism 6 is multiple, length of multiple first guide wheel mechanisms 6 along nuclear fuel rod
Spend the setting of direction interval.The part of multiple first guide wheel mechanisms 6 can be set on the first Holding seat, and with the first clamping machine
The synchronization of tool hand is moved along sliding rail.Also the protective element carried out by materials such as polyurethane can be set in the guide groove of first guide wheel 602,
To avoid and nuclear fuel rod friction damage nuclear fuel rod.
As shown in Figure 6 to 8, detection device 300 includes chuck mechanism 11, glyphomancy symbol identification mechanism 12, spectral detection machine
The linear sweep mechanism 14 of structure 13, laser and blowing mechanism 10, chuck mechanism 11, glyphomancy symbol identification mechanism 12, spectral detection mechanism
13, the linear sweep mechanism 14 of laser and blowing mechanism 10 are arranged in the second rack 9, and set-up mode preferably uses connector can
Dismantling connection, connector can select the structures such as screw, rivet.In order to reduce the vibration of the other factors bring such as workshop, the
Be provided with marble platform pedestal in two racks 9, and by chuck mechanism 11, glyphomancy symbol identification mechanism 12, spectral detection mechanism 13,
The linear sweep mechanism 14 of laser and blowing mechanism 10 are arranged on marble platform pedestal.
Wherein, blowing mechanism 10 is set to the second rack 9 close to the side of the first rack 1, and is located at the biography of nuclear fuel rod
On defeated path.Blowing mechanism 10 includes purging air generator 1001 and scavenging conduit 1002, purges the gas outlet of air generator 1001
It is connected to the air inlet of scavenging conduit 1002, the shape of scavenging conduit 1002 is not specifically limited, and can be "-" type, U-shaped or L
Type etc..Blow valve port is provided on scavenging conduit 1002, the shape and quantity of blow valve port are not specifically limited, preferably several.Purging
Air generator 1001 can generate purge stream, and purge stream is transmitted in scavenging conduit 1002, and is blown out out of blow valve port
To the transmission path of nuclear fuel rod, when nuclear fuel rod passes through the lower section of blow valve port, purge stream can will be on nuclear fuel rod
Dust and foreign matter blow off.Further, in the present embodiment, purging air generator 1001 is preferred selects ion wind generator,
To generate ion wind, ion wind can not only purge the foreign matter on nuclear fuel rod, additionally it is possible to eliminate nuclear fuel rod surface
Electrostatic, purging quality are higher.
Chuck mechanism 11 includes along spaced first chuck assembly 1101 of nuclear fuel rod transmission direction and the second chuck
Component 1102, the first chuck assembly 1101 are arranged close to feeding device 200, and the second chuck assembly 1102 is close to blanking device 400
Setting.As shown in figure 9, the first chuck assembly 1101 includes the first chuck 11011 and the first driving mechanism, the first chuck 11011
It is vertically set in the second rack 9, the accommodating chamber for accommodating the first clamping seat 11014, the first card is provided on the first chuck 11011
Joint chair 11014 is provided with the through-hole for allowing nuclear fuel rod in the width direction, is provided with collet, collet on the first clamping seat 11014
Nuclear fuel rod can be clamped, in the present embodiment, collet is suitable for nuclear fuel rod of the diameter in particular range, it is of course possible to logical
Various sizes of nuclear fuel rod can be clamped by crossing the hardware such as replacement collet.First driving mechanism includes motor 11012 and skin
V belt translation part 11013, belt drive 11013 include that belt and two belt pulleys, one of belt pulley are set in motor
On 11012 motor shaft, for the setting of another belt pulley on the first clamping seat 11014, which can be with the first clamping seat
11014 integrated moldings can also be to be fixedly connected again after split settings, and belt is set on two belt pulleys.Motor 11012 can
It drives belt drive 11013 to rotate, so that the first clamping seat 11014 be driven to rotate, and then drives nuclear fuel rod rotation.It is examining
During survey, at 0-120 revs/min, specific rotation speed is specifically set the rotation speed of nuclear fuel rod as the case may be.When
So in other embodiments, the first driving mechanism can also be using other mechanisms, as long as the first clamping seat 11014 can be driven
Rotation.
Second chuck assembly 1102 includes the second chuck and the second driving mechanism, is provided with the second clamping on the second chuck
Seat, the structure of the second chuck is identical with the structure of the first chuck 11011, the structure of the second clamping seat and the first clamping seat 11014
Structure it is identical, details are not described herein.The structure of second driving mechanism and the first driving mechanism may be the same or different,
As long as the second clamping seat can be driven to rotate, so that nuclear fuel rod be driven to rotate.
The linear sweep mechanism 14 of laser is arranged between the first chuck 11011 and the second chuck, for nuclear fuel rod table
The defect information that the tiny flaws such as scuffing, stomata, pit, island shape wound, the leprosy scar in face are detected, and will test passes to whole
The control device of a equipment for nuclear fuel rod Surface testing.Specifically, as shown in Figure 10, the linear sweep mechanism 14 of laser wraps
Laser camera 1401 and image processing modules are included, laser camera 1401 can obtain the image information on nuclear fuel rod surface, and will
The image information passes to image processing modules, and image processing modules can be handled image information, to obtain core combustion
Nuclear fuel rod is divided into qualified product and not so that the later period classifies to nuclear fuel rod by the concrete condition of each defect in charge bar surface
Qualified product.Specific judgment criteria includes following several: the scratch depth on the first, nuclear fuel rod surface is defined as X1mm；The second,
The scuffing on nuclear fuel rod surface is defined as the circumferential width that scratches and accumulates Y1Mm, longitudinal width that scratches accumulate Y2mm；Third, fuel rod
Surface crater is defined as X containing the depth scratched, island shape is hurt2mm.In the present embodiment, X1、X2、Y1And Y2Occurrence do not limit
It is fixed, the specific setting as the case may be in practical work process.When any one defect situation detected is higher than above-mentioned correspondence
It when index, can be judged as substandard product, when the defect detected all meets These parameters, can be judged as qualified production
Product.
In order to carry out high speed, comprehensive detection to nuclear fuel rod, in the present embodiment, selection uses multiple laser phases
Machine 1401 is arranged side by side, to improve the scan area of single.The quantity of laser camera 1401 is not specifically limited, such as can be with
For one, two, three, four or more are selected using four laser cameras 1401 along nuclear fuel in the present embodiment
The transmission direction of stick is arranged side by side.Nuclear fuel rod is located at the top of four laser cameras 1401, when nuclear fuel rod rotation, four
Laser camera 1401 can carry out comprehensive 360 ° of detections without dead angle to the nuclear fuel rod being positioned above.Due to nuclear fuel rod
Length it is longer, four laser cameras 1401 still cannot achieve one-time detection and finish, it is contemplated that the cost of detection device 300 with
And volume, in the present embodiment, selection carries out repeatedly detection paragraph by paragraph, the length and four that nuclear fuel rod detects every time to nuclear fuel rod
The whole detection equal length of a laser camera 1401 side by side.In entire detection process, detect a nuclear fuel rod only need it is several
Minute, compared to artificial detection, detection efficiency is higher.Further, it in order to improve the mobile stability of nuclear fuel rod, avoids
The problem of deviating in moving process, the detection device 300 further include guiding mechanism 15, as shown in figure 13, guiding mechanism 15
Between two chuck assemblies, guiding mechanism 15 includes guide holder 1501, and one end of guide holder 1501 is arranged in the second rack 9
On, the other end is provided with pilot hole 1502, and nuclear fuel rod can be passed through and be moved out of pilot hole 1502.The number of guiding mechanism 15
Measure preferably several, multiple guiding mechanisms 15 are arranged in the transmission path of nuclear fuel rod, and are arranged along specific spacing interval.
Spectral detection mechanism 13 is located at the side of the linear sweep mechanism 14 of laser, for the end plug and bar to nuclear fuel rod
Weld seam between main body is detected, and the weld information that will test passes to entire setting for nuclear fuel rod Surface testing
Standby control device.Specifically, as shown in figure 11, spectral detection mechanism 13 includes Spectral Confocal camera 1301, Spectral Confocal phase
Machine 1301 can be scanned commissure, and obtain the quality information of weld seam.Since nuclear fuel rod includes two end plugs,
It is provided with twice weld seam on a nuclear fuel rod, for the ease of detecting twice weld seam, which further includes moving
Dynamic model group 1302, mobile mould group 1302 include sliding cylinder, slide track seat and the slip base being arranged in the second rack 9, slide gas
The cylinder rod of cylinder is connect with slip base, and slip base is fixedly connected with Spectral Confocal camera 1301, the length direction of slide track seat with
The transmission direction of nuclear fuel rod is parallel, and the sliding slot for being slidably connected with slide track seat is provided on slip base.In sliding cylinder
Under driving, Spectral Confocal camera 1301 can be moved along slide track seat, to detect to twice weld seam.
Glyphomancy symbol identification mechanism 12 is located at the other side of the linear sweep mechanism 14 of laser, for identified on nuclear fuel rod into
Row identifies, and the identification information of acquisition is passed to the control device of entire detection device.Mark on nuclear fuel rod is by character
String composition, is the identity information of nuclear fuel rod, and glyphomancy symbol identification mechanism 12 can identify the identity information of nuclear fuel rod, thus
The defect information and identity information that spectral detection mechanism 13 and the linear sweep mechanism 14 of laser are obtained correspond, so as to the later period
Staff rechecks underproof nuclear fuel rod.Specifically, as shown in figure 12, glyphomancy symbol identification mechanism 12 includes glyphomancy
Accord with rack 1201, light source and detection components 1202.Glyphomancy symbol rack 1201 is L-type structure, is vertically set on the second rack 9
On.Light source setting can be illuminated around nuclear fuel rod in glyphomancy symbol rack 1201.Detection components 1202 can identify that core fires
Mark on charge bar, in the present embodiment, detection components 1202 can be camera.
The course of work of entire detection device 300 are as follows: enter the nuclear fuel of detection device 300 by 10 pairs of blowing mechanism first
Stick is purged, to remove the foreign matter on its surface；Then nuclear fuel rod stops movement after continuing to move to target length, at this time core
Fuel rod is rotated under the clamping action of chuck mechanism 11, and in rotary course, glyphomancy symbol identification mechanism 12 is to nuclear fuel
Mark on stick is identified that the linear sweep mechanism 14 of laser obtains the defect information on nuclear fuel rod circumferential surface, spectrum
The weld seam of nuclear fuel rod end detects in testing agency 13, and by the identification information of acquisition, defect information and weld information
Pass to the control device of entire detection device；Finally, driving nuclear fuel rod continues to move after one section of nuclear fuel rod detection
It is dynamic, next section of nuclear fuel rod is detected.Detection device in compared to the prior art, which can be to core
The tiny flaw of 20um or so is detected on fuel rod surface and face of weld, and detection accuracy is higher.
After nuclear fuel rod detection, nuclear fuel rod enters blanking device 400.Blanking device is in entire blanking process
In, it does not need artificially to carry, the abnormal collision of bar and carrying can be effectively prevented from, to reduce impaired general of bar
Rate is conducive to the yields for improving bar.Specifically, as shown in Figure 14 to Figure 16, blanking device 400 includes the second clamping device
17, the second clamping device 17 is used to clamp the nuclear fuel rod into blanking device 400.Specifically, the second clamping device 17 includes
Second Holding seat 1701 and the second clamping manipulator 1702, the second Holding seat 1701 are arranged in third rack 16, and second
The setting of clamping manipulator 1702 is slidably connected on the second Holding seat 1701, and with the second Holding seat 1701.Specifically,
Directive slide track 1703 is provided on two Holding seats 1701, the bottom of the second clamping manipulator 1702 is provided with sliding block, sliding block energy
It is enough to be slided on directive slide track 1703.The top of second clamping manipulator 1702 is provided with the second mechanical paw, the second manipulator
Pawl can clamp nuclear fuel rod.When the second clamping manipulator 1702 is slided along directive slide track 1703, nuclear fuel rod can be along remote
Direction from detection device 300 is mobile, so that nuclear fuel rod is transmitted to inside blanking device 400.In order to avoid the second clamping
Manipulator 1702 damages nuclear fuel rod, and cushion is provided on the second mechanical paw, and cushion can be using made of rubber
Pad.
Further, in order to improve the transmission precision of nuclear fuel rod, which further includes the second guide wheel machine
Structure 18, the second guide wheel mechanism 18 include the second wheel stand 1801 and the second guide wheel 1802, and the bottom end of the second wheel stand 1801 is vertical
It is arranged in third rack 16, the top of the second wheel stand 1801 is provided with rotation slot, and the second guide wheel 1802 is rotated by shaft
It is connected to inside rotation slot, the guide groove for accommodating nuclear fuel rod is provided on the outer peripheral surface of the second guide wheel 1802.In this implementation
In example, in order to improve guiding accuracy, the quantity of the second guide wheel mechanism 18 be it is multiple, multiple second guide wheel mechanisms 18 are along nuclear fuel rod
Length direction interval setting.The part of multiple second guide wheel mechanisms 18 can be set on the second Holding seat 1701, and with
The synchronization of second clamping manipulator 1702 is moved along directive slide track 1703.It also can be set in the guide groove of second guide wheel 1802 by poly- ammonia
The protective element that the materials such as ester carry out, to avoid and nuclear fuel rod friction damage nuclear fuel rod.In 17 He of the second clamping device
Under the action of second guide wheel mechanism 18, nuclear fuel rod can integrally enter in blanking device 400.
For the ease of carrying out separating storage to qualified nuclear fuel rod and underproof nuclear fuel rod, in the second rack 9
There are two allocation mechanism and two material guide mechanisms for setting.Two allocation mechanisms are respectively third allocation mechanism 19 and the 4th kickoff
The two sides of nuclear fuel rod are arranged in structure 20, third allocation mechanism 19 and the 4th allocation mechanism 20.Specifically, as shown in figure 17,
Three allocation mechanisms 19 include third pedestal 1901, the first material toggling motor 1902, first rotating shaft 1903 and third switch-plate 1904, the
Three pedestals 1901 are vertically set in third rack 16.In the present embodiment, third pedestal 1901 and third switch-plate 1904
Quantity be it is multiple, multiple third pedestals 1901 along nuclear fuel rod length direction interval be arranged, one end of third pedestal 1901
It is fixedly connected by screw, first rotating shaft hole is provided on the other end.First rotating shaft 1903 sequentially passes through multiple first rotating shaft holes
Setting, the motor axis connection of one end of first rotating shaft 1903 and the first material toggling motor 1902, specifically connection type, can choose
It is directly connected to, also can choose and connected using belt component, in the present embodiment, selection is connected using belt component.Multiple
Three switch-plates 1904 are arranged at intervals in first rotating shaft 1903, under the driving of the first material toggling motor 1902, first rotating shaft 1903
It can rotate, so as to drive third switch-plate 1904 to rotate around first rotating shaft 1903, in third switch-plate 1904
In rotation process, the one end of third switch-plate 1904 far from first rotating shaft 1903 can be from the lower section of nuclear fuel rod by nuclear fuel rod
It lifts, and is allocated on corresponding material guide mechanism.
The structure of 4th allocation mechanism 20 is identical as the structure of third switch-plate 1904, and the two is symmetrically set about nuclear fuel rod
It sets.4th allocation mechanism 20 includes the 4th pedestal, the second material toggling motor, the second shaft and the 4th switch-plate, and the 4th pedestal is vertical
It is arranged in third rack 16.In the present embodiment, the quantity of the 4th pedestal and the 4th switch-plate is multiple, multiple 4th bottoms
Seat is arranged along the length direction interval of nuclear fuel rod, and one end of the 4th pedestal is fixedly connected by screw, is provided on the other end
Second shaft hole.Second shaft sequentially passes through multiple second shaft hole settings, one end of the second shaft and the second material toggling motor
Motor axis connection, specifically connection type, can choose and be directly connected to, and also can choose and is connected using belt component, in this reality
It applies in example, selection is connected using belt component.Multiple 4th switch-plates are arranged at intervals in the second shaft, in the second material toggling motor
Driving under, the second shaft can rotate, so as to drive the 4th switch-plate to rotate around the second shaft, in the 4th material toggling
In the rotation process of plate, the 4th one end of switch-plate far from the second shaft can be dialled from the lower section of nuclear fuel rod by nuclear fuel rod
It rises, and is allocated on corresponding material guide mechanism.
Two material guide mechanisms are respectively the second material guide mechanism 21 and third material guide mechanism 22, the second material guide mechanism 21 and third
Material guide mechanism 22 is located at the two sides of the second clamping device 17 and the second guide wheel mechanism 18.That is, the second material guide mechanism
21 and third material guide mechanism 22 be located at the two sides of nuclear fuel rod, the second material guide mechanism 21 is for exporting underproof nuclear fuel rod
To unqualified area, third material guide mechanism 22 is used to export qualified nuclear fuel rod to qualified area.
Second material guide mechanism 21 is identical with the structure of third material guide mechanism 22, and the second material guide mechanism 21 includes the second guide bottom
Seat 2101 and the second stock guide 2102, the second guide pedestal 2101 are vertically set in third rack 16, the second stock guide 2102
The top of second guide pedestal 2101 is set, and is provided with the second guide face on the second stock guide 2102, the second guide face
Tilt angle preferably between 1.0-10.0 °, such as can for 1.0 °, 2.5 °, 3.4 °, 4.2 °, 5.6 °, 6.3 °, 7.7 °,
8.9 °, 9.0 ° or 10.0 °.
Third material guide mechanism 22 includes third guide pedestal and third stock guide, and third guide pedestal is vertically set on third
In rack 16, the top of third guide pedestal is arranged in third stock guide, sets on the third stock guide of third material guide mechanism 22
It is equipped with third guide face, the inclined direction in third guide face and the second guide face is on the contrary, to make the second stock guide 2102 and the
Three stock guides arrangement triangular shape.The tilt angle in third guide face is preferably between 1.0-10.0 °, such as can be
1.0 °, 2.4 °, 3.5 °, 4.6 °, 5.2 °, 6.7 °, 7.3 °, 8.8 °, 9.4 ° or 10.0 ° etc..Third guide face and the second guide
The tilt angle in face can be controlled separately, and be not particularly limited herein.Since qualified nuclear fuel rod is more, it is underproof compared with
It is few, the length of third stock guide is preferably set greater than to the length of the second stock guide 2102, to accommodate more nuclear fuels
Stick.Since the height of third guide pedestal and the second guide pedestal 2101 is equal, in the present embodiment, third guide face
It is different with the tilt angle in the second guide face.
Further, the second stock guide 2102 is detachably connected with the second guide pedestal 2101, to adjust according to demand
The tilt angle in the second guide face.Since the length of nuclear fuel rod is longer, in order to reduce the cost of manufacture of the second material guide mechanism 21
And installation difficulty, it is lesser that second guide pedestal 2101 can be likewise provided as multiple width as shown in the first material guide mechanism 3
Narrow pedestal and narrow stock guide, narrow stock guide are located above narrow pedestal, and multiple narrow pedestal interval settings are to have biggish support
Area.Narrow pedestal is identical as the structure of sub- pedestal, and details are not described herein.
When narrow stock guide stroke is longer, when being provided with more nuclear fuel rods, in order to which the stroke of narrow stock guide is segmented,
It is provided separately with more nuclear fuel rods being located on narrow stock guide, so as to realize rechecking and receiving by root for nuclear fuel rod
It receives, and reduces and be located at the pressure that is subject to of bottom nuclear fuel rod, be arranged at intervals with multiple the along guide direction on narrow stock guide
Narrow stock guide is divided into multiple accommodating spaces by two baffle blocks 2103, multiple second baffle blocks 2103, can in each accommodating space
One or more nuclear fuel rods, preferably one are arranged, to avoid abnormal collision between more nuclear fuel rods, core is reduced
Friction between fuel rod improves the quality of nuclear fuel rod to guarantee the integrality of nuclear fuel rod inner silica uranium pellet.
In order to realize transmission of the nuclear fuel rod between adjacent accommodating space, set in the side that the second baffle block 2103 is arranged in narrow stock guide
It is equipped with the second rod pushing mechanism 23.Second rod pushing mechanism 23 is identical with the structure of the first rod pushing mechanism 7, and the second rod pushing mechanism 23 includes
The side of narrow pedestal, the cylinder rod of the second rod pushing jug is arranged in second rod pushing jug and the second push rod block, the second rod pushing jug
It is arranged vertically upwards, and is fixedly connected with the second push rod block.Second push rod block includes second connecting portion and second pushes away finger portion, and second
Interconnecting piece is rectangular block, and second pushes away finger portion as wedge block.In order to avoid acceleration is excessive with the during scrolling for nuclear fuel rod
Sharp impacts occur for two baffle blocks 2103, and protective element made of polyurethane material etc. can also be arranged on the second baffle block 2103
Part.Other than protective element, naturally it is also possible to be reduced using speed of the decelerations such as hydraulic bjuffer mechanism to nuclear fuel rod.
Certainly in other embodiments, if the stroke of narrow stock guide is shorter or narrow stock guide on a nuclear fuel is only set every time
Stick can also be not provided with the second baffle block 2103 and protective element.
When nuclear fuel rod is stopped by the second baffle block 2103, the second rod pushing mechanism 23 be located just at nuclear fuel rod just under
Side, when needing to shift nuclear fuel rod to next accommodating space, the cylinder rod of the first rod pushing jug 701 of the second rod pushing mechanism 23
It moves up, the first of the first push rod block 702 of the second rod pushing mechanism 23 pushes away finger portion and jack up nuclear fuel rod, and nuclear fuel rod is in weight
The lozenges that power acts on the first push rod of lower edge block 702 is mobile, so that crossing the second baffle block 2103 reaches next accommodating space.The
The quantity of two rod pushing mechanisms 23 with no restrictions, can for one, two or more, it is preferably equal in the side of each narrow pedestal
It is provided with second rod pushing mechanism 23, to improve the stability that nuclear fuel rod shifts in adjacent accommodating space.
When nuclear fuel rod is located at the second baffle block 2103 in the last one accommodating space, staff can be to core
Fuel rod is rechecked and is stored, and safety is higher.It rechecks, by control device and can also beat for the ease of staff
Printing apparatus connection, to print defect stick inventory, which can enumerate stick number including nuclear fuel rod, defect
The information such as position, defect type, flaw size, so as to staff's ratio against defect stick inventory microscope to nuclear fuel rod into
Row reinspection is determined and is put together after problematic nuclear fuel rod is tied up using rubber band to recovering mechanism recycling after the completion of rechecking.
The entire equipment detection accuracy for nuclear fuel rod Surface testing is higher, can reach in length, the detection accuracy of width direction
Not less than 0.01mm, can reach in the detection accuracy of depth direction not less than 0.005mm, detecting repeatability can reach not low
In 0.002mm, the degree of automation and detection effect of detection are largely improved, is advantageously implemented fast and efficiently
Detection.
The present embodiment additionally provides a kind of detection method of above-mentioned equipment for nuclear fuel rod Surface testing, the detection side
Method specifically comprises the following steps:
Bar is transmitted in detection device 300 using feeding device 200；
The mark on the bar is identified using glyphomancy symbol identification mechanism 12, utilizes the spectrum of detection device 300
The defect on bar end weld surface detects in testing agency 13, and using the linear sweep mechanism of laser 14 to billet surface
Defect detected；
Bar is transmitted to blanking device 400, and according to the testing result of detection device 300, qualified bar is transmitted
To qualified area, underproof bar is transmitted to unqualified area.
Specifically, when detecting face of weld defect using spectral detection mechanism 13, first with the axial line of nuclear fuel rod
It for rotary shaft, controls nuclear fuel rod and at least rotates a circle, obtain the 3D point cloud data of the tested single cylinder segment of face of weld；So
The 3D point cloud data for splicing at least two cylinder segments afterwards obtain the complete 3D point cloud data of tested face of weld；Finally it is based on
Depth information in complete 3D point cloud data carries out gray processing to complete 3D point cloud data, generates gray level image, and be based on gray scale
The sum of the grayscale values of each point presets defect condition and carries out defects detection to gray level image in image.
It is first rotation with nuclear fuel rod axial line when detecting bar surface defect using the linear sweep mechanism 14 of laser
Axis controls nuclear fuel rod rotation on the direction of axial line, for each group of cylinder segment to be measured of nuclear fuel rod, controls laser
The 3D point cloud data on the acquisition of linear scan mechanism 14 group cylinder segment surface to be measured；It is then based on every group of cylindrical zone segment table to be measured
Depth information in the 3D point cloud data in face carries out gray processing, to obtain the gray level image on every group of cylinder segment surface to be measured, base
Sum of the grayscale values in the gray level image on every group of cylinder segment surface to be measured presets defect condition, determines every group of cylinder segment to be measured
The defect on surface；Location information finally based on each group cylinder segment surface defect to be measured splices each group cylindrical zone segment table to be measured
The defect in face obtains the complete defect information of periphery to be measured.
Further, detection method further include: before detection device 300 detects bar, utilize blowing mechanism
10 pairs of billet surfaces purge.
Further, detection method further include: when detection device 300 detects bar, known using glyphomancy symbol
Other mechanism 12 identifies the mark on bar.
Obviously, the above embodiments of the present invention is used for the purpose of clearly illustrating examples for clearly illustrating the present invention, and
It is not limitations of the embodiments of the present invention.For those of ordinary skill in the art, in above description
On the basis of can also make other variations or changes in different ways.There is no need and unable to give all embodiments
Exhaustion.Any modifications, equivalent replacements, and improvements made within the spirit and principle of the present invention etc., should be included in
Within the protection scope of the utility model claims.
Claims (9)
1. a kind of equipment for nuclear fuel rod Surface testing, including rack (100), which is characterized in that further include being arranged in institute
It states on rack (100):
Detection device (300), the detection device (300) include spectral detection mechanism (13), the linear sweep mechanism of laser (14)
Identification mechanism (12) are accorded with glyphomancy, the spectral detection mechanism (13) is used to detect the defect on bar end weld surface, described
The linear sweep mechanism of laser (14) is used to detect the defect of the billet surface, and glyphomancy symbol identification mechanism (12) is used for institute
The mark stated on bar is identified；
Feeding device (200), the feeding device (200) are located at the input terminal of the detection device (300), are used for the stick
Material is delivered in the detection device (300)；
Blanking device (400), the blanking device (400) are located at the output end of the detection device (300), the blanking device
(400) bar can be delivered to qualified area or unqualified area according to the testing result of the detection device (300)；
Control device, the control device and the detection device (300), the feeding device (200) and the blanking device
(400) communication connection.
2. the equipment according to claim 1 for nuclear fuel rod Surface testing, which is characterized in that the detection device
(300) further include:
Blowing mechanism (10), the blowing mechanism (10) are located in the detection device (300), and are located at the transmission of the bar
On path, the blowing mechanism (10) includes purging air generator (1001) and scavenging conduit (1002), the purging air generator
(1001) gas outlet is connected to the air inlet of the scavenging conduit (1002), is provided with blow valve port on the scavenging conduit (1002).
3. the equipment according to claim 1 for nuclear fuel rod Surface testing, which is characterized in that the detection device
(300) further include:
Chuck mechanism (11), the chuck mechanism (11) include the spaced first chuck group of transmission direction along the bar
Part (1101) and the second chuck assembly (1102), on first chuck assembly (1101) and second chuck assembly (1102)
It is provided with the through-hole for allowing the bar to pass through.
4. the equipment according to claim 3 for nuclear fuel rod Surface testing, which is characterized in that
First chuck assembly (1101) includes the first chuck (11011) and the first driving mechanism, first chuck
(11011) it is arranged on the rack (100), the first clamping seat (11014), institute is provided on first chuck (11011)
Through-hole setting is stated in first clamping seat (11014), first driving mechanism and first clamping seat (11014) pass
Dynamic connection, for driving the first clamping seat (11014) rotation；
Second chuck assembly (1102) includes the second chuck and the second driving mechanism, and second chuck is arranged in the machine
On frame (100), the second clamping seat is provided on second chuck, the through-hole setting is described on the second clamping seat
Second driving mechanism and the second clamping seat transmission connection, for driving the second clamping seat rotation；
Described first, which is clamped seat (11014) and the second clamping seat, is provided with collet along the circumferential direction of the through-hole.
5. the equipment according to claim 1 for nuclear fuel rod Surface testing, which is characterized in that the feeding device
(200) include:
The first material guide mechanism (3) of several spacing side by side setting, it is defeated outside the input terminal of first material guide mechanism (3) is corresponding
Line sending is tiltedly installed with the first guide on first material guide mechanism (3) to receive the bar that the pipeline conveying comes
Face, the bar can roll on first guide face；
First clamping device (5), first clamping device (5) are located at the output end of first material guide mechanism (3), and described
One clamping device (5) be configured to receive by first material guide mechanism (3) convey Lai the bar and by the stick
Material is delivered in the detection device (300), first clamping device (5) and the control device communication connection.
6. the equipment according to claim 5 for nuclear fuel rod Surface testing, which is characterized in that the feeding device
(200) further include:
First guide wheel mechanism (6), first guide wheel mechanism (6) include the first wheel stand (601) and the first guide wheel (602), the
One wheel stand (601) is arranged on the rack (100), and first guide wheel (602) is rotatably connected on first wheel stand
(601) on, the guide groove for accommodating the bar is provided on the outer peripheral surface of first guide wheel (602).
7. the equipment according to claim 5 for nuclear fuel rod Surface testing, which is characterized in that
It is provided with the first baffle block (303) on first guide face, the first baffle block (303) is by first guide face
It is divided into multiple accommodating spaces, the side of the first baffle block (303) is provided with the first rod pushing mechanism (7), first push rod
Mechanism (7) is for pushing the bar to move between the adjacent accommodating space.
8. the equipment according to claim 1 for nuclear fuel rod Surface testing, which is characterized in that
The blanking device (400) includes the second clamping device (17), and second clamping device (17) includes the second clamping bottom
Seat (1701) and the second clamping manipulator (1702), second Holding seat (1701) are arranged on the rack (100), institute
State the second clamping manipulator (1702) be arranged on second Holding seat (1701), and with second Holding seat
(1701) it is slidably connected.
9. the equipment according to claim 8 for nuclear fuel rod Surface testing, which is characterized in that the blanking device
(400) further include:
Second material guide mechanism (21) and third material guide mechanism (22), second material guide mechanism (21) and the third material guide mechanism
(22) two sides of second clamping device (17) are located at, to receive the stick for coming from second clamping device (17)
Material, second material guide mechanism (21) are configured as exporting the underproof bar to unqualified area, the third guide
Mechanism (22) is configured as exporting the qualified bar to qualified area.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920409646.3U CN209691405U (en) | 2019-03-28 | 2019-03-28 | A kind of equipment for nuclear fuel rod Surface testing |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920409646.3U CN209691405U (en) | 2019-03-28 | 2019-03-28 | A kind of equipment for nuclear fuel rod Surface testing |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109961860A (en) * | 2019-03-28 | 2019-07-02 | 中核建中核燃料元件有限公司 | A kind of equipment 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 |
|---|---|---|---|---|
| CN109961860A (en) * | 2019-03-28 | 2019-07-02 | 中核建中核燃料元件有限公司 | A kind of equipment and its detection method for nuclear fuel rod Surface testing |
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