CN107388978A - The thread measurement system and detection method of the main screw of nuclear power plant reactor container - Google Patents
The thread measurement system and detection method of the main screw of nuclear power plant reactor container Download PDFInfo
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- CN107388978A CN107388978A CN201710580483.0A CN201710580483A CN107388978A CN 107388978 A CN107388978 A CN 107388978A CN 201710580483 A CN201710580483 A CN 201710580483A CN 107388978 A CN107388978 A CN 107388978A
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- thread
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- thread measurement
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01B—MEASURING LENGTH, THICKNESS OR SIMILAR LINEAR DIMENSIONS; MEASURING ANGLES; MEASURING AREAS; MEASURING IRREGULARITIES OF SURFACES OR CONTOURS
- G01B11/00—Measuring arrangements characterised by the use of optical techniques
- G01B11/08—Measuring arrangements characterised by the use of optical techniques for measuring diameters
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
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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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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- General Physics & Mathematics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses the thread measurement system of the main screw of nuclear power plant reactor container and detection method, including host computer unit, for carrying out man-machine interaction；And disposed thread parameter algorithm, the screw thread data received are calculated；Main control unit, it is connected with host computer cell signal, the signal of laser range sensor is carried out to be processed and transmitted to host computer unit；And the user instruction sent according to host computer unit, vertically movable mechanism, rotating mechanism are controlled；Thread measurement module, it is connected with main control unit signal, including two symmetrical laser range sensors；Vertically movable mechanism, for controlling the vertical motion of thread measurement module；Rotating mechanism, for controlling horizontally rotating for thread measurement module.The present invention realizes the purpose accurately detected to the main screw of reactor vessel to solve the problems, such as that the inconvenience of the main screw of reactor vessel in the prior art accurately detects, causes kingbolt that bite phenomenon easily occurs.
Description
Technical field
The present invention relates to nuclear power field, and in particular to the thread measurement system of the main screw of nuclear power plant reactor container and detection
Method.
Background technology
External screw thread process technology：Since twentieth century end, the screw thread process technology of external industrially developed country
There occurs the leap of essence, the crudy of screw thread to be obviously improved.Some external enterprises utilize advanced
Processing, e measurement technology, strict control screw thread parameters, and the mismachining tolerance of screw thread is controlled in product in process
Within the 60% of predetermined tolerance.
The situation of China's screw product：China has been the important big trading nation in the whole world, Chinese threaded fastener export volume
The first in the world is occupied, Chinese threaded fitting also there are large quantities of outlets every year.Although Chinese exports amount is big, the matter of Chinese screw thread
Amount is not horizontal high, is referred to as coarse screw thread big producer by other.The horizontal state with mid-twentieth century of Chinese screw thread process at present
It is on close level outside.These all highly impact the credit rating of China's engineering goods and the profit of foreign exchange earning.Chinese screw thread
Product from scalar type to mass type transformation be screw thread process enterprise inevitable choice.
Compare China and the gap of the pipe screw thread product of external industrially developed country, maximum gap is exactly crudy.
Want to improve screw processing quality it is necessary to ensure the control of screw thread parameters mismachining tolerance in product predetermined tolerance, and to the greatest extent may be used
Error can be made smaller.This requires us except to there is advanced process technology, also to possess advanced thread single parameter and survey
Measuring appratus and method.
The installation of nuclear power plant reactor container kingbolt and dismounting be new heap loading procedure or power station overhaul during one
Important step, but it is no matter domestic or external, and the kingbolt bite phenomenon of reactor vessel still happens occasionally.Kingbolt occurs
After serious bite, more difficulty is taken out, a series of problems can be caused to reactor later stage work, can be damaged when serious on container
Main screw, in some instances it may even be possible to schedule delays, cause heavy economic losses.Show that kingbolt is matched somebody with somebody with main screw according to correlation experience feedback
It is to cause kingbolt to install one of an important factor for bite occurs that it is smaller, which to close gap,.It is but special due to nuclear power plant reactor container
Property, screw hole dimensions are larger, and use environment is complicated, and the factor such as irremovable influences, and current each power station only makes before kingbolt is installed
Detection means is by the macroscopic defect of vision-based detection screw thread, has no the hand for detecting the critical datas such as main screw central diameter
Section, can not also optimize and grasp the fit clearance of kingbolt and main screw, make bite risk in kingbolt assembling process be present.And
The existing manual measurement instrument of in the market, measuring principle are to advise the correction that compares using corresponding thread standard, are passed using displacement
Displacement is converted to electric signal and shown again by analog-to-digital conversion with digital display meter by sensor.Also occur other in the prior art
The thread detecting device of form, but such device is mostly measured by mechanical structure such as guide rail, measuring arm, swing rod etc., should
In the measurement apparatus of class mechanical type, central diameter show value does not have one-to-one relationship with measuring point depth, it is impossible to reacts screw thread one week respectively
The central diameter value at place, can not also record the inner diameter values of each point in screw global extent, therefore can not be to the big footpath of screw, central diameter, small
Footpath is calculated, and measuring point depth is by the length limitation of equipment guide rail etc. itself, it is impossible to accomplishes to cover the measurement of gamut.
The content of the invention
It is an object of the invention to provide the thread measurement system of the main screw of nuclear power plant reactor container and detection method, with
The main screw inconvenience for solving reactor vessel in the prior art accurately detects, causes kingbolt that asking for bite phenomenon easily occurs
Topic, realizes the purpose accurately detected to the main screw of reactor vessel.
The present invention is achieved through the following technical solutions：
The thread measurement system of the main screw of nuclear power plant reactor container, it is characterised in that including：
Host computer unit, for carrying out man-machine interaction；And disposed thread parameter algorithm, the screw thread data received are carried out
Calculate；
Main control unit, it is connected with host computer cell signal, the signal of laser range sensor is processed and transmitted to
Host computer unit；And the user instruction sent according to host computer unit, vertically movable mechanism, rotating mechanism are controlled；
Thread measurement module, it is connected with main control unit signal, including two symmetrical laser range sensors；
Vertically movable mechanism, for controlling the vertical motion of thread measurement module；
Rotating mechanism, for controlling horizontally rotating for thread measurement module.
Main screw inconvenience for reactor vessel in the prior art accurately detects, causes kingbolt that bite easily occurs to show
As the problem of, present invention firstly provides a kind of thread measurement system of the main screw of nuclear power plant reactor container, including host computer list
Member, main control unit, thread measurement module, vertically movable mechanism, rotating mechanism, wherein host computer unit are used to carry out man-machine friendship
Mutually, user carries out instruction transmission according to host computer unit, is sent user instruction to main control unit by host computer unit；Host computer
Unit can also carry out calculating processing to the data received.Main control unit receives the user instruction that host computer unit is sent,
And according to user instruction, corresponding mechanism is controlled, such as vertically movable mechanism, rotating mechanism are acted, meanwhile, main control unit is also
The data that can be detected to thread measurement module are handled, and are easy to the transmission to host computer unit.Thread measurement module with
Main control unit signal connects, for the measurement data of two laser range sensors of master unit transmissions.Two laser rangings
Sensor is symmetrically distributed in thread measurement module, by two symmetrical laser range sensors, to main screw inwall
Distance with respect to both direction measures.Vertically movable mechanism is controlled by main control unit, for controlling thread measurement module
It is vertically movable；Rotating mechanism is controlled by main control unit, for controlling horizontally rotating for thread measurement module.The system uses process
In, thread measurement module is placed in an initial condition at the top of the main screw of reactor pressure vessel to be detected, by host computer
Unit sets and moved up and down, and the design parameter horizontally rotated, starts working afterwards.In the course of work, thread measurement module is first
Under the driving of vertically movable mechanism, moved inside main screw while sensed by two laser rangings from top to bottom
Device gathers the screw thread data inside main screw, and data are transmitted to host computer unit after main control unit is handled and is calculated and is shown
Show.Behind thread measurement block motion to bottom, drive it to rotate specified angle by rotating mechanism, driven afterwards by vertically movable mechanism
Move it to be moved from bottom to top, the number of threads inside main screw is gathered also by two laser range sensors in motion process
According to data are transmitted to host computer unit after main control unit is handled and is calculated and is shown.After reaching top, it can complete to survey
Amount, also can again rotational angle, repeat the above steps, to obtain more measurement parameters so that testing result is more accurate.This inspection
Examining system is set particular for the particularity of main screw in nuclear power plant reactor pressure vessel compared to prior art, can
One week central diameter value everywhere of screw thread is reacted, is able to record the inner diameter values of each point in screw global extent, therefore can directly pass through
Each point inner diameter values are calculated the big footpath of screw, central diameter, path, and therefore, the present invention is realized to the main screw of reactor vessel
The purpose accurately detected.
Further, image capture module, image capture module and main control unit are also included in the thread measurement module
Signal connects, and is carried out the signal of image capture module by main control unit to be processed and transmitted to host computer unit.Adopted by image
Collect module to carrying out real-time IMAQ inside the main screw of reactor pressure vessel, in order to which staff intuitively observes master
Screw internal whorl situation, enabling carry out observation detection, further checking detection data, raising accuracy of detection.
Further, picture recognition module is set in host computer unit, to image capture module acquired image information
In typical defect be identified.For the internal thread of main screw, common typical defect such as tool marks, twisted, flat button, double
Top clip etc., all shown with substantially stationary image, therefore by picture recognition module, the figure gathered to image capture module
As information is identified one by one, typical defect is quickly identified with this, without passing through internal diameter analysis and artificial observation, you can
The typical defect of main screw internal whorl is efficiently automatically detected, greatly improves the automaticity and effect of thread measurement
Rate.
Preferably, trigger module is also included in the thread measurement module, for controlling laser range sensor with certain
Time interval triggering sampling.It is to trigger the cycle by setting, interval sampling can be carried out as needed so that of the invention
Using more flexibly, it can cross and be detected suitable for the internal thread under more parameters.
Preferably, the disposed thread parameter algorithm of host computer unit includes pitch diameter of thread algorithm, big footpath algorithm, path calculation
One or more in method, bottom footpath algorithm.Existing thread parameter algorithm just includes to central diameter, big footpath, path, bottom footpath etc.
Calculate, therefore the thread parameter algorithm that this programme is set in host computer unit can include one or more therein, with this
Detection data, the detection range of the raising present invention needed for obtaining as needed.
The thread measurement method of the main screw of nuclear power plant reactor container, comprises the following steps：
(a) thread measurement module is made to be located at the top of screw；
(b) screw bottom is moved downwardly to by vertically movable mechanism driving thread measurement module；
(c) rotated by rotating mechanism driving thread measurement module；
(d) moved up to by vertically movable mechanism driving thread measurement module at the top of screw；
Wherein, in step (b), (d) in the upper and lower motion process of thread measurement module, screw thread is symmetrically distributed in by two
Laser range sensor measurement on detection module and is transmitted to main control unit screw internal data, main control unit through data at
Transmitted after reason to host computer unit, thread parameter calculating is carried out by host computer unit.
Vertically movable mechanism can be existing any drive mechanism with linear movement direction in the present invention, such as electric
Dynamic push rod, reciprocating motor etc..Rotating mechanism can be realized by existing any rotating device such as stepper motor, not limit herein.
Further, in step (b), (d) in the upper and lower motion process of thread measurement module, also by image capture module
Gather the view data inside screw and transmit to main control unit, main control unit is transmitted after data processing to host computer unit.
Further, host computer unit carries out typical defect identification to acquired image data.
Preferably, in step (b), (d) in the upper and lower motion process of thread measurement module, laser range sensor is with one
Fixed time interval is sampled.
The thread parameter that preferably, host computer unit is carried out is calculated as pitch diameter of thread calculating, big footpath calculates, path calculates,
One or more in the calculating of bottom footpath.
The present invention compared with prior art, has the following advantages and advantages：
1st, the thread measurement system and detection method of the main screw of nuclear power plant reactor container of the present invention, thread measurement module exist
During up and down motion, the screw thread data inside main screw are gathered by two laser range sensors, by data through master control list
Transmitted after member processing to host computer unit and calculated and shown.This detecting system is compared to prior art, particular for nuclear power
The particularity of main screw in reactor pressure vessel of standing and set, the central diameter value that screw thread can be reacted one week everywhere, be able to record
The inner diameter values of each point in screw global extent, therefore directly the big footpath of screw, central diameter, path can be entered by each point inner diameter values
Row calculates, and therefore, the present invention realizes the purpose accurately detected to the main screw of reactor vessel.
2nd, the thread measurement system and detection method of the main screw of nuclear power plant reactor container of the present invention, passes through IMAQ mould
Block is to carrying out real-time IMAQ inside the main screw of reactor pressure vessel, in order to which staff intuitively observes main screw
Internal whorl situation, enabling carry out observation detection, further checking detection data, raising accuracy of detection.
3rd, the thread measurement system and detection method of the main screw of nuclear power plant reactor container of the present invention, passes through image recognition mould
Block, image capture module acquired image information is identified one by one, typical defect quickly identified with this, without
Pass through internal diameter analysis and artificial observation, you can efficiently automatically detect the typical defect of main screw internal whorl, greatly carry
The high automaticity and efficiency of thread measurement.
Brief description of the drawings
Accompanying drawing described herein is used for providing further understanding the embodiment of the present invention, forms one of the application
Point, do not form the restriction to the embodiment of the present invention.In the accompanying drawings：
Fig. 1 is the connection diagram of the specific embodiment of the invention 1；
Fig. 2 is the schematic flow sheet of the specific embodiment of the invention 2.
Embodiment
For the object, technical solutions and advantages of the present invention are more clearly understood, with reference to embodiment and accompanying drawing, to this
Invention is described in further detail, and exemplary embodiment of the invention and its explanation are only used for explaining the present invention, do not make
For limitation of the invention.
Embodiment 1：
The thread measurement system of the main screw of nuclear power plant reactor container as shown in Figure 1, including：Host computer unit, is used for
Carry out man-machine interaction；And disposed thread parameter algorithm, the screw thread data received are calculated；Main control unit, with host computer
Cell signal is connected, and the signal of laser range sensor is carried out to be processed and transmitted to host computer unit；And according to host computer list
The user instruction that member is sent, is controlled to vertically movable mechanism, rotating mechanism；Thread measurement module, believe with main control unit
Number connection, including two symmetrical laser range sensors；Vertically movable mechanism, for controlling the perpendicular of thread measurement module
Straight motion；Rotating mechanism, for controlling horizontally rotating for thread measurement module.Also adopted in the thread measurement module including image
Collect module, image capture module is connected with main control unit signal, the signal of image capture module is handled by main control unit
And transmit to host computer unit.Picture recognition module is set in host computer unit, image capture module acquired image is believed
Typical defect in breath is identified.Also include trigger module in the thread measurement module, for controlling laser ranging to sense
Device triggers sampling at a certain time interval.The disposed thread parameter algorithm of host computer unit includes pitch diameter of thread algorithm, big footpath
Algorithm.In the present embodiment course of work, thread measurement module is first under the driving of vertically movable mechanism, from top to bottom in main spiral shell
Moved inside hole while gather the screw thread data inside main screw by two laser range sensors, by data through master
Transmitted after control cell processing to host computer unit and calculated and shown.Behind thread measurement block motion to bottom, by whirler
Structure drives it to rotate specified angle, drives it to be moved from bottom to top by vertically movable mechanism afterwards, also leads in motion process
The screw thread data crossed inside two main screws of laser range sensors collection, data are transmitted to upper after main control unit is handled
Machine unit is calculated and shown.After reaching top, can complete to measure, also can again rotational angle, repeat the above steps, to obtain
Take more measurement parameters so that testing result is more accurate.This detecting system is anti-particular for nuclear power station compared to prior art
Answer the particularity of main screw in core pressure vessel and set, the central diameter value that screw thread can be reacted one week everywhere, be able to record screw
The inner diameter values of each point in global extent, therefore directly the big footpath of screw, central diameter can be calculated by each point inner diameter values.Together
When, additionally it is possible to by picture recognition module, image capture module acquired image information is identified one by one, with this to allusion quotation
Type defect is quickly identified, without passing through internal diameter analysis and artificial observation, you can efficiently automatically detect inside main screw
The typical defect of screw thread, greatly improve the automaticity and efficiency of thread measurement.
Embodiment 2：
The thread measurement method of the main screw of nuclear power plant reactor container as shown in Figure 2, comprises the following steps：(a) spiral shell is made
Line detection module is located at the top of screw；(b) screw bottom is moved downwardly to by vertically movable mechanism driving thread measurement module；
(c) rotated by rotating mechanism driving thread measurement module；(d) transported upwards by vertically movable mechanism driving thread measurement module
Move to screw；Wherein, it is symmetrically distributed in step (b), (d) in the upper and lower motion process of thread measurement module by two
Laser range sensor in thread measurement module measures screw internal data and transmitted to main control unit, and main control unit is through number
According to being transmitted after processing to host computer unit, thread parameter calculating is carried out by host computer unit.Thread measurement mould in step (b), (d)
In the upper and lower motion process of block, also by the view data inside image capture module collection screw and transmit to main control unit,
Main control unit is transmitted after data processing to host computer unit.Host computer unit carries out typical defect to acquired image data
Identification.In step (b), (d) in the upper and lower motion process of thread measurement module, laser range sensor is between the regular hour
Every being sampled.The thread parameter that host computer unit is carried out, which calculates, includes pitch diameter of thread calculating, big footpath calculates, path calculates, bottom
During footpath calculates.
Above-described embodiment, the purpose of the present invention, technical scheme and beneficial effect are carried out further
Describe in detail, should be understood that the embodiment that the foregoing is only the present invention, be not intended to limit the present invention
Protection domain, within the spirit and principles of the invention, any modification, equivalent substitution and improvements done etc., all should include
Within protection scope of the present invention.
Claims (10)
1. the thread measurement system of the main screw of nuclear power plant reactor container, it is characterised in that including：
Host computer unit, for carrying out man-machine interaction；And disposed thread parameter algorithm, the screw thread data received are counted
Calculate；
Main control unit, it is connected with host computer cell signal, the signal of laser range sensor be processed and transmitted to upper
Machine unit；And the user instruction sent according to host computer unit, vertically movable mechanism, rotating mechanism are controlled；
Thread measurement module, it is connected with main control unit signal, including two symmetrical laser range sensors；
Vertically movable mechanism, for controlling the vertical motion of thread measurement module；
Rotating mechanism, for controlling horizontally rotating for thread measurement module.
2. the thread measurement system of the main screw of nuclear power plant reactor container according to claim 1, it is characterised in that described
Also include image capture module in thread measurement module, image capture module is connected with main control unit signal, will by main control unit
The signal of image capture module carries out being processed and transmitted to host computer unit.
3. the thread measurement system of the main screw of nuclear power plant reactor container according to claim 2, it is characterised in that upper
Picture recognition module is set in machine unit, the typical defect in image capture module acquired image information is identified.
4. the thread measurement system of the main screw of nuclear power plant reactor container according to claim 1, it is characterised in that described
Also include trigger module in thread measurement module, for controlling laser range sensor to trigger sampling at a certain time interval.
5. the thread measurement system of the main screw of nuclear power plant reactor container according to claim 1, it is characterised in that upper
The disposed thread parameter algorithm of machine unit include pitch diameter of thread algorithm, big footpath algorithm, path algorithm, one kind in the algorithm of bottom footpath or
It is a variety of.
6. the thread measurement method of the main screw of nuclear power plant reactor container based on detecting system described in claim 1, its feature
It is, comprises the following steps：
(a) thread measurement module is made to be located at the top of screw；
(b) screw bottom is moved downwardly to by vertically movable mechanism driving thread measurement module；
(c) rotated by rotating mechanism driving thread measurement module；
(d) moved up to by vertically movable mechanism driving thread measurement module at the top of screw；
Wherein, in step (b), (d) in the upper and lower motion process of thread measurement module, thread measurement is symmetrically distributed in by two
Laser range sensor in module measures screw internal data and transmitted to main control unit, and main control unit is after data processing
Transmit to host computer unit, thread parameter calculating is carried out by host computer unit.
7. the thread measurement method of the main screw of nuclear power plant reactor container according to claim 6, it is characterised in that step
(b), in (d) in the upper and lower motion process of thread measurement module, also by the picture number inside image capture module collection screw
According to and transmit to main control unit, main control unit is transmitted after data processing to host computer unit.
8. the thread measurement method of the main screw of nuclear power plant reactor container according to claim 7, it is characterised in that upper
Machine unit carries out typical defect identification to acquired image data.
9. the thread measurement method of the main screw of nuclear power plant reactor container according to claim 6, it is characterised in that step
(b), in (d) in the upper and lower motion process of thread measurement module, laser range sensor is adopted at a certain time interval
Sample.
10. the thread measurement method of the main screw of nuclear power plant reactor container according to claim 6, it is characterised in that on
The thread parameter that position machine unit is carried out be calculated as one kind during the pitch diameter of thread calculates, big footpath calculates, path calculates, bottom footpath calculates or
It is a variety of.
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| CN201710580483.0A CN107388978A (en) | 2017-07-17 | 2017-07-17 | The thread measurement system and detection method of the main screw of nuclear power plant reactor container |
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Cited By (6)
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| CN110849279A (en) * | 2019-11-27 | 2020-02-28 | 陕西理工大学 | Compensation method for measuring pitch diameter of thread by machine vision |
| CN111693253A (en) * | 2020-06-23 | 2020-09-22 | 中国核动力研究设计院 | Pressure vessel owner bolt hole detection device |
| CN111710447A (en) * | 2020-06-23 | 2020-09-25 | 中国核动力研究设计院 | Method and system for detecting main bolt hole of pressure vessel |
| CN112871737A (en) * | 2021-01-12 | 2021-06-01 | 中煤科工集团西安研究院有限公司 | Pipe fitting internal thread detection method based on sensor, pipe fitting screening method and system |
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| CN114353672A (en) * | 2022-01-19 | 2022-04-15 | 中国长江三峡集团有限公司 | Large-diameter pipeline lining fixing bolt inspection system and inspection method |
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| CN110849279A (en) * | 2019-11-27 | 2020-02-28 | 陕西理工大学 | Compensation method for measuring pitch diameter of thread by machine vision |
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| CN111693253A (en) * | 2020-06-23 | 2020-09-22 | 中国核动力研究设计院 | Pressure vessel owner bolt hole detection device |
| CN111710447A (en) * | 2020-06-23 | 2020-09-25 | 中国核动力研究设计院 | Method and system for detecting main bolt hole of pressure vessel |
| CN112871737A (en) * | 2021-01-12 | 2021-06-01 | 中煤科工集团西安研究院有限公司 | Pipe fitting internal thread detection method based on sensor, pipe fitting screening method and system |
| CN112871737B (en) * | 2021-01-12 | 2022-06-28 | 中煤科工集团西安研究院有限公司 | Pipe fitting internal thread detection method based on sensor, pipe fitting screening method and system |
| CN113555139A (en) * | 2021-07-22 | 2021-10-26 | 中广核检测技术有限公司 | Automatic video inspection device for main bolt hole of reactor pressure vessel |
| CN113555139B (en) * | 2021-07-22 | 2024-02-13 | 中广核检测技术有限公司 | Automatic video inspection device for main bolt hole of reactor pressure vessel |
| CN114353672A (en) * | 2022-01-19 | 2022-04-15 | 中国长江三峡集团有限公司 | Large-diameter pipeline lining fixing bolt inspection system and inspection method |
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