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CN105817831B - The screw hole defects detection and restorative procedure of nuclear power station large container and equipment, device - Google Patents

The screw hole defects detection and restorative procedure of nuclear power station large container and equipment, device Download PDF

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Publication number
CN105817831B
CN105817831B CN201610314895.5A CN201610314895A CN105817831B CN 105817831 B CN105817831 B CN 105817831B CN 201610314895 A CN201610314895 A CN 201610314895A CN 105817831 B CN105817831 B CN 105817831B
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China
Prior art keywords
screw thread
defect
equipment
nuclear power
power station
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CN105817831A (en
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刘青松
侯硕
余冰
沈黎
邓志燕
贺韶
彭祥阳
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
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    • BPERFORMING OPERATIONS; TRANSPORTING
    • B23MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23PMETAL-WORKING NOT OTHERWISE PROVIDED FOR; COMBINED OPERATIONS; UNIVERSAL MACHINE TOOLS
    • B23P6/00Restoring or reconditioning objects
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01BMEASURING LENGTH, THICKNESS OR SIMILAR LINEAR DIMENSIONS; MEASURING ANGLES; MEASURING AREAS; MEASURING IRREGULARITIES OF SURFACES OR CONTOURS
    • G01B5/00Measuring arrangements characterised by the use of mechanical techniques
    • G01B5/08Measuring arrangements characterised by the use of mechanical techniques for measuring diameters
    • G01B5/12Measuring arrangements characterised by the use of mechanical techniques for measuring diameters internal diameters
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N21/00Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
    • G01N21/84Systems specially adapted for particular applications

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  • Physics & Mathematics (AREA)
  • General Physics & Mathematics (AREA)
  • Health & Medical Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Analytical Chemistry (AREA)
  • Biochemistry (AREA)
  • General Health & Medical Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Immunology (AREA)
  • Pathology (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a kind of nuclear power station large containers and the screw hole defects detection and restorative procedure of equipment, obtain continuous, positioning formula the inspection data information of any one screw thread hole surface of reactor pressure vessel;Dimensional gaughing is carried out to being judged as that there is no the internal thread of defect or defect in tolerance interval;The step of Local treatment is carried out to the screw thread of existing defects;Whole the step of repairing, is carried out to the screw thread of existing defects.The invention also discloses a kind of nuclear power station large containers and the screw hole defects detection and prosthetic device of equipment.Implement the nuclear power station large container of the present invention and screw hole defects detection and restorative procedure, the device of equipment, the different defects of nuclear power station large container and equipment can be directed to, using different technique;Spiral interpolation miller artistic skill enough expands the range of screw thread reparation;Defects detection and the efficiency repaired are further improved, effectively reduces the raying dosage of worker.

Description

The screw hole defects detection and restorative procedure of nuclear power station large container and equipment, device
Technical field
The present invention relates to nuclear power field more particularly to a kind of nuclear power station large container and equipment screw hole defects detection and repair Multiple method, apparatus.
Background technology
In the prior art, it detects and repairs the defects of screw hole and generally carried out, but by instrument using the technology mode of screw tap processing Device handles the influence of size, is not particularly suited for screw hole defects detection and the reparation of nuclear power station large container and equipment.It is existing For nuclear power station large container and the method for the screw hole defects detection and reparation of equipment, it is primarily present following technological deficiency:
1st, the degree of automation is not high, and repair means are limited.
2nd, screw thread repair coverage is limited, and overhaul efficiency is not high.
Invention content
The technical problems to be solved by the invention are, provide the screw hole defect inspection of a kind of nuclear power station large container and equipment Survey and restorative procedure, device can be directed to the different defects of nuclear power station large container and equipment, using different technique;Spiral Interpolation miller artistic skill enough expands the range of screw thread reparation;Defects detection and the efficiency repaired are further improved, effectively reduces worker Raying dosage.
In order to solve the above-mentioned technical problem, the embodiment provides the spiral shells of a kind of nuclear power station large container and equipment Hole defect detects and restorative procedure, includes the following steps:Obtain the continuous of any one screw thread hole surface of reactor pressure vessel , positioning formula inspection data information, including:There are the first games of any one of tiny burr and Superficial Foreign Body defect for screw thread Portion's defect information and screw thread exist collapse, distort, any one of misrun and thread fracture defect, and the defect is local defect The second local defect information;Any one screw thread hole surface is judged with the presence or absence of defect according to inspection data information, if it is determined that It is yes, then records type, the size and location data information of defect;If being judged as NO, next step is performed;To being judged as not depositing Dimensional gaughing is carried out in the internal thread of defect or defect in tolerance interval, judges whether inspection result is qualified, if it is determined that It is yes, then terminates;If the judgment is No, then the step of being repaired according to the concrete condition of defect to screw thread is performed;To existing The screw thread of defect carries out the step of Local treatment;Whole the step of repairing, is carried out to the screw thread of existing defects.
Wherein, the step of carrying out Local treatment to the screw thread of existing defects includes:Obtain any of reactor pressure vessel When continuous, positioning formula the inspection data information of a screw thread hole surface is First partial defect information, using chasing tool to screw thread Hole is combed;Obtain continuous, positioning formula the inspection data information of any one screw thread hole surface of reactor pressure vessel During for the second local defect information, the thread segment being damaged is cut off using bolt hole milling process.
Wherein, threaded hole comb using chasing tool and be included:Chaser is not by the way of fertile material is removed, knife Tool is close to original thread, along the step of the progress feed of original thread contour line.
Wherein, the step of carrying out whole reparation to the screw thread of existing defects includes:Using the side of spiral interpolation processing screw thread Method repairs screw thread, the method that selection uses the mating three-shaft linkage lathe milling of molding cutter, after equipment installation is in, with screw thread Spiral interpolation is carried out along original thread path centered on hole, can different interpolation radiuses be selected according to actual requirement.
Wherein, the screw thread of existing defects is carried out further including after whole the step of repairing:Whether check screw thread hole surface There are still defect, measured after determining screw thread no significant defect using go-no go gauge the step of.
In order to solve the above technical problems, the invention also discloses another technical solution, a kind of nuclear power station large container and The screw hole defects detection and prosthetic device of equipment, including:To obtain any one screw thread hole surface of reactor pressure vessel Continuously, the video detection instrument of the inspection data information of positioning formula, checks that data information includes:There are tiny burr and tables for screw thread The First partial defect information and screw thread of any one of face foreign matter defect, which exist, to be collapsed, distorts, in the fracture of misrun and thread Any defect, and second local defect information of the defect for local defect;To being judged as that there is no defect or defects Internal thread in tolerance interval carries out the inside micrometer and/or go-no go gauge of dimensional gaughing;To the spiral shell to existing defects Line carries out the chasing tool and/or milling cutter of Local treatment;The spiral interpolation processing integrally repaired to the screw thread to existing defects Instrument;Wherein:Video detection instrument, inside micrometer and/or go-no go gauge, chasing tool and/or milling cutter and spiral interpolation processing instrument are successively It is connected and forms assembly line.
Wherein, video detection instrument is that RV bolts hole are continuous, positions formula closed-circuit television somascope, and RV bolts hole are continuous, positioning Formula closed-circuit television somascope includes the display, logger, camera and the video recorder that are connected with each other.
Wherein, it further includes:Be connected with inside micrometer and/or go-no go gauge to the spiral shell that is cut off of screw thread damage section Pit Milling Machine.
Wherein, spiral interpolation processing instrument includes three-shaft linkage lathe and the molding cutter being arranged on three-shaft linkage lathe.
The screw hole defects detection and restorative procedure of nuclear power station large container and equipment provided by the present invention, device, have Following advantageous effect:
Firstth, video detection instrument, inside micrometer and/or go-no go gauge, chasing tool and/or milling cutter and spiral interpolation processing instrument Composition assembly line is sequentially connected, video detection instrument can obtain the continuous of any one screw thread hole surface of reactor pressure vessel , the inspection data information of positioning formula, it is interior and according to checking that data information judges any one screw thread hole surface with the presence or absence of defect Diameter micrometer and/or go-no go gauge to carry out size inspection to being judged as that there is no the internal thread of defect or defect in tolerance interval It looks into, chasing tool and/or milling cutter are to judging that the internal thread not in tolerance interval is repaired;Spiral interpolation is processed instrument and is lacked to existing Sunken screw thread carries out whole reparation, the different defects of nuclear power station large container and equipment can be directed to, using different technique;Spiral shell Rotation interpolation miller artistic skill enough expands the range of screw thread reparation;Defects detection and the efficiency repaired are further improved, effectively reduces work The raying dosage of people.
Secondth, video detection instrument includes the display, logger, camera and the video recorder that are connected with each other, can will examine The fruit that comes to an end shows, records, takes a picture and records as requested, so as to provide foundation for its maintaining or repair.
Description of the drawings
In order to illustrate more clearly about the embodiment of the present invention or technical scheme of the prior art, to embodiment or will show below There is attached drawing needed in technology description to be briefly described, it should be apparent that, the accompanying drawings in the following description is only this Some embodiments of invention, for those of ordinary skill in the art, without creative efforts, can be with Other attached drawings are obtained according to these attached drawings.
Fig. 1 is nuclear power station large container and the screw hole defects detection of equipment of the present invention and the flow diagram of restorative procedure.
Fig. 2 is nuclear power station large container and the screw hole defects detection of equipment of the present invention and the structure diagram of prosthetic device.
Specific embodiment
Below in conjunction with the attached drawing in the embodiment of the present invention, the technical solution in the embodiment of the present invention is carried out clear, complete Site preparation describes, it is clear that described embodiment is only part of the embodiment of the present invention, instead of all the embodiments.It is based on Embodiment in the present invention, those of ordinary skill in the art are obtained every other without creative efforts Embodiment shall fall within the protection scope of the present invention.
It is nuclear power station large container of the present invention and the screw hole defects detection of equipment and the embodiment of restorative procedure referring to Fig. 1 One.
The screw hole defects detection and restorative procedure of nuclear power station large container and equipment in the present embodiment, including following step Suddenly:
Step S10 obtains continuous, positioning formula the inspection data of any one screw thread hole surface of reactor pressure vessel Information, any one screw thread hole surface according to judging the inspection data information whether there is defect, if the judgment is Yes, then Record type, the size and location data information of defect;If being judged as NO, next step is performed;
When it is implemented, above-mentioned steps can be implemented by video detection instrument, such as:Video detection instrument can be RV bolts Hole is continuous, positioning formula closed-circuit television somascope, is carried out for the entire thread surface of bolt hole each to reactor pressure vessel Continuously, the closed-circuit television (CCTV) of positioning formula checks.When it is implemented, RV bolts hole are continuous, positioning formula closed-circuit television somascope Display, logger, camera and the video recorder of interconnection are further included, testing result information can be carried out as requested Video screen shows, records, takes a picture and records a video, so as to provide foundation for its maintaining or maintenance.It is lacked if existing Type, the size and location fall into, then recorded defect.
Preferably, continuous, positioning formula the inspection data of any one screw thread hole surface of reactor pressure vessel are obtained Information includes:Screw thread there are tiny burr, it is tiny collapse, the First partial of tiny distortion and any one of Superficial Foreign Body defect Defect information and screw thread exist collapse, distort, any one of misrun and thread fracture defect, and the defect is local defect Second local defect information.
Step S20 to carry out dimensional gaughing to being judged as that there is no the internal thread of defect or defect in tolerance interval, sentence Whether disconnected inspection result is qualified, if the judgment is Yes, then terminates;If the judgment is No, then the concrete condition according to defect is performed The step repaired to screw thread
When it is implemented, after RV bolts hole are continuous, positioning formula closed-circuit television somascope checks, if defect is not present in screw thread Or defect is within the acceptable range, perform internal threads dimensional gaughing the step of.Dimensional gaughing is using inside micrometer and leads to No-go gage carries out.If dimensional gaughing is qualified, without screw thread reparation;If off-dimension or screw thread existing defects, need root Screw thread is repaired according to the concrete condition of defect.
Step S30, the step of Local treatment is carried out to the screw threads of existing defects;
When it is implemented, the screw thread to existing defects includes the step of carrying out Local treatment:If it obtains reactor pressure to hold When continuous, positioning formula the inspection data information of any one screw thread hole surface of device is First partial defect information, using comb Knife combs threaded hole;Wherein:Threaded hole comb using chasing tool and is included:Chaser uses and does not remove parent material The mode of material, cutter are close to original thread, along the step of the progress feed of original thread contour line.Screw thread comb after still need to carry out video and The detection of go-no go gauge, to ensure qualification.
If continuous, positioning formula the inspection data information for obtaining any one screw thread hole surface of reactor pressure vessel is During the second local defect information, the thread segment being damaged is cut off using bolt hole milling process.Bolt milling cutter is using part The mode of milling carries out removal procedure to local defect.It needs to assess excision screw thread influence before defect excision, assesses nothing Problem can carry out excision work, still need to carry out video and size detection after screw thread excision, to ensure qualification.
Step S40 carries out whole the step of repairing to the screw thread of existing defects.
When it is implemented, if threaded hole is there are a wide range of major defect, so that can not be handled or be handled using chasing tool, milling cutter It cannot still meet the requirements afterwards, whole reaming entirety repair process at this moment should be carried out to threaded hole.Screw thread is expanded using removal material The method of hole central diameter, while bolt adaptation specification need to be changed to reach pressure vessel available mode.Screw thread reparation is inserted using spiral Add work screw thread technique, i.e. selection uses the mating three-shaft linkage lathe milling process of molding cutter, after equipment installation is in, with Spiral interpolation is carried out along original thread path centered on threaded hole, according to actual requirement, selects different interpolation radiuses.
Preferably, the screw thread of existing defects is carried out further including after whole the step of repairing:Checking screw thread hole surface is It is no there are still defect, measured after determining screw thread no significant defect using go-no go gauge the step of.That is, screw thread reaming After, video check is also needed, is measured after screw thread no significant defect is determined using go-no go gauge, if meeting condition, threaded hole It repairs and completes.If Eligibility requirements cannot be met, continue reaming and repair step, to ensure qualification.
The invention also discloses a kind of nuclear power station large container and the screw hole defects detection and prosthetic device of equipment, including: To obtain the video inspection of continuous, positioning formula the inspection data information of any one screw thread hole surface of reactor pressure vessel Survey instrument 1;To being judged as that there is no the internal diameters thousand that the internal thread of defect or defect in tolerance interval carries out dimensional gaughing Divide ruler and/or go-no go gauge 2;To carry out the chasing tool of Local treatment and/or milling cutter 3 to the screw thread of existing defects;To existing The spiral interpolation processing instrument 4 that the screw thread of defect is integrally repaired;Wherein:Video detection instrument 1, inside micrometer and/or it is logical only Rule 2, chasing tool and/or milling cutter 3 and spiral interpolation processing instrument 4 are sequentially connected composition assembly line.
Preferably, it further includes:What is be connected with inside micrometer and/or go-no go gauge 2 cuts off to damage section to screw thread Threaded hole Milling Machine 5.
Preferably, spiral interpolation processing instrument 4 include three-shaft linkage lathe 41 and be arranged on three-shaft linkage lathe 41 into Type cutter 42.
When it is implemented, video detection instrument 1 is that RV bolts hole are continuous, positions formula closed-circuit television somascope, RV bolts hole connect Continuous, positioning formula closed-circuit television somascope includes the display 11, logger 12, camera 13 and the video recorder that are connected with each other 14.RV bolts hole are continuous, the entire thread surface of each bolt hole to reactor pressure vessel of positioning formula closed-circuit television somascope 1 It carries out continuous, positioning formula closed-circuit television (CCTV) to check, can testing result information be carried out to video screen as requested and shown Show, record, take a picture and record a video, so as to provide foundation for its maintaining or maintenance.If existing defects, then record lacks Sunken type, size and location.
After RV bolts hole are continuous, positioning formula closed-circuit television somascope checks, if there is no defect or defects can for screw thread In the range of receiving, perform internal threads dimensional gaughing the step of.Dimensional gaughing is carried out using inside micrometer and go-no go gauge 2. If dimensional gaughing is qualified, without screw thread reparation;If off-dimension or screw thread existing defects, need the tool according to defect Body situation repairs screw thread.
Further, if continuous, positioning formula the inspection data of any one screw thread hole surface of reactor pressure vessel When information is First partial defect information, threaded hole is combed using chasing tool;Wherein:Threaded hole is combed using chasing tool Reason includes:For chaser by the way of fertile material is not removed, cutter is close to original thread, and feed is carried out along original thread contour line The step of.Screw thread still needs to carry out the detection of video and go-no go gauge after combing, to ensure qualification.
If after continuous, positioning formula the inspection of the screw thread hole surface of reacted core pressure vessel, it is found that it is thin screw thread exists Small burr, it is tiny collapse, tiny distortion and any one of Superficial Foreign Body defect, by threaded hole Milling Machine 5 to bolt hole into Row milling is to cut off the thread segment being damaged.Bolt milling cutter is cut local defect using the mode of local milling Except processing.It needs to assess excision screw thread influence before defect excision, assessment no problem can carry out excision work, screw thread excision After still need to carry out video and size detection, to ensure qualification.If the screw thread hole surface of reacted core pressure vessel is continuous, fixed Position formula inspection after, find screw thread exist collapse, distort, misrun and thread fracture any one of defect when, spiral shell can be used Rotation interpolation processing instrument 4 carries out spiral interpolation processing to repair screw thread.Specifically, selection is using 42 mating three-shaft linkage of molding cutter Lathe 41 carries out milling, and after equipment installation is in, spiral interpolation is carried out along original thread path centered on threaded hole, can basis Actual requirement selects different interpolation radiuses.
Implement the nuclear power station large container of the present invention and the screw hole defects detection and restorative procedure and device of equipment, have such as Lower advantageous effect:
Firstth, video detection instrument, inside micrometer and/or go-no go gauge, chasing tool and/or milling cutter and spiral interpolation processing instrument Composition assembly line is sequentially connected, video detection instrument can obtain the continuous of any one screw thread hole surface of reactor pressure vessel , the inspection data information of positioning formula, it is interior and according to checking that data information judges any one screw thread hole surface with the presence or absence of defect Diameter micrometer and/or go-no go gauge to carry out size inspection to being judged as that there is no the internal thread of defect or defect in tolerance interval It looks into, chasing tool and/or milling cutter are to judging that the internal thread not in tolerance interval is repaired;Spiral interpolation is processed instrument and is lacked to existing Sunken screw thread carries out whole reparation, the different defects of nuclear power station large container and equipment can be directed to, using different technique;Spiral shell Rotation interpolation miller artistic skill enough expands the range of screw thread reparation;Defects detection and the efficiency repaired are further improved, effectively reduces work The raying dosage of people.
Secondth, video detection instrument includes the display, logger, camera and the video recorder that are connected with each other, can will examine The fruit that comes to an end shows, records, takes a picture and records as requested, so as to provide foundation for its maintaining or repair.

Claims (9)

1. the screw hole defects detection and restorative procedure of a kind of nuclear power station large container and equipment, which is characterized in that including following step Suddenly:
Continuous, positioning formula the inspection data information of any one screw thread hole surface of reactor pressure vessel is obtained, including:Spiral shell Line exist there are the First partial defect information and screw thread of any one of tiny burr and Superficial Foreign Body defect collapse, distort, Any one of misrun and thread fracture defect, and second local defect information of the defect for local defect;According to the inspection Look into data information and judge any one described screw thread hole surface with the presence or absence of defect, if the judgment is Yes, then record defect type, Size and location data information;If being judged as NO, next step is performed;
Dimensional gaughing is carried out to being judged as that there is no the internal thread of defect or defect in tolerance interval, judges that inspection result is No qualification if the judgment is Yes, then terminates;If the judgment is No, then it performs and screw thread is repaiied according to the concrete condition of defect Multiple step;
The step of Local treatment is carried out to the screw thread of existing defects;
Whole the step of repairing, is carried out to the screw thread of existing defects.
2. the screw hole defects detection and restorative procedure of nuclear power station large container as described in claim 1 and equipment, feature exist In the step of screw thread to existing defects carries out Local treatment includes:
Continuous, positioning formula the inspection data information of any one the screw thread hole surface for obtaining reactor pressure vessel is the During one local defect information, threaded hole is combed using chasing tool;
Continuous, positioning formula the inspection data information of any one the screw thread hole surface for obtaining reactor pressure vessel is the During two local defect information, the thread segment being damaged is cut off using bolt hole milling process.
3. the screw hole defects detection and restorative procedure of nuclear power station large container as claimed in claim 2 and equipment, feature exist In the use chasing tool, which to threaded hole comb, to be included:Chaser by the way of fertile material is not removed, be close to by cutter Original thread, along the step of the progress feed of original thread contour line.
4. such as claim 1-3 any one of them nuclear power station large containers and the screw hole defects detection and restorative procedure of equipment, Include it is characterized in that, the screw thread to existing defects carries out whole the step of repairing:
Screw thread is repaired using the method for spiral interpolation processing screw thread, selection is using the mating three-shaft linkage lathe milling of molding cutter Method, equipment installation in after, centered on threaded hole along original thread path carry out spiral interpolation, can according to actual requirement, Select different interpolation radiuses.
5. the screw hole defects detection and restorative procedure of nuclear power station large container as claimed in claim 4 and equipment, feature exist In the screw thread to existing defects further included after whole the step of repairing:
Screw thread hole surface is checked whether there are still defect, the step measured after screw thread no significant defect is determined using go-no go gauge Suddenly.
6. the screw hole defects detection and prosthetic device of a kind of nuclear power station large container and equipment, which is characterized in that including:To obtain The video detection instrument of continuous, positioning formula the inspection data information of any one screw thread hole surface of reactor pressure vessel is taken, Check that data information includes:Screw thread there are any one of tiny burr and Superficial Foreign Body defect First partial defect information and Screw thread exist collapse, distort, misrun and thread fracture any one of defect, and the defect for local defect second part lack Fall into information;
To divide the internal diameter thousand for being judged as carrying out dimensional gaughing there is no the internal thread of defect or defect in tolerance interval Ruler and/or go-no go gauge;
To carry out the chasing tool and/or milling cutter of Local treatment to the screw thread of existing defects;
Instrument is processed to the spiral interpolation that the screw thread to existing defects is integrally repaired;Wherein:It is the video detection instrument, described Inside micrometer and/or go-no go gauge, the chasing tool and/or milling cutter and spiral interpolation processing instrument are sequentially connected composition flowing water Line.
7. the screw hole defects detection and prosthetic device of nuclear power station large container as claimed in claim 6 and equipment, feature exist In the video detection instrument is that RV bolts hole are continuous, positions formula closed-circuit television somascope, and the RV bolts hole are continuous, positioning formula Closed-circuit television somascope includes the display, logger, camera and the video recorder that are connected with each other.
8. the screw hole defects detection and prosthetic device of nuclear power station large container as claimed in claim 6 and equipment, feature exist In further including:
Be connected with the inside micrometer and/or the go-no go gauge to the threaded hole milling that is cut off of screw thread damage section Machine.
9. the screw hole defects detection and prosthetic device of nuclear power station large container as claimed in claim 6 and equipment, feature exist In the spiral interpolation processing instrument includes three-shaft linkage lathe and the molding cutter being arranged on the three-shaft linkage lathe.
CN201610314895.5A 2016-05-13 2016-05-13 The screw hole defects detection and restorative procedure of nuclear power station large container and equipment, device Active CN105817831B (en)

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Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108000048B (en) * 2016-11-01 2019-06-21 三门核电有限公司 A kind of online restorative procedure of main screw hole of reactor pressure vessel flange
CN107388978A (en) * 2017-07-17 2017-11-24 成都海光核电技术服务有限公司 The thread measurement system and detection method of the main screw of nuclear power plant reactor container
CN112045364A (en) * 2020-08-25 2020-12-08 上海核工程研究设计院有限公司 Method for repairing J-shaped welding seam of pressure boundary of nuclear-grade small-diameter penetration piece

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN2758938Y (en) * 2004-12-07 2006-02-15 张喜华 Device for repairing main pressure container, main sealing surface and main bolt hole of nuclear power station reactor
WO2009005446A1 (en) * 2007-07-05 2009-01-08 Novator Ab An orbital drilling tool unit
CN202994342U (en) * 2012-11-12 2013-06-12 中国广东核电集团有限公司 Nuclear power plant bolt stress data collection device and detection device thereof
CN103207187A (en) * 2012-01-17 2013-07-17 大日本网屏制造株式会社 Appearance Inspection Apparatus And Method
CN103357928A (en) * 2013-06-27 2013-10-23 中广核工程有限公司 Method for repairing main screw hole of reactor pressure vessel
CN104751914A (en) * 2013-12-31 2015-07-01 中核武汉核电运行技术股份有限公司 Non-destructive inspection circumferential position correction method for thread hole belt of nuclear reactor pressure vessel
CN205629828U (en) * 2016-05-13 2016-10-12 中广核研究院有限公司 Screw defect detecting and prosthetic devices of nuclear power station tun and equipment

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN2758938Y (en) * 2004-12-07 2006-02-15 张喜华 Device for repairing main pressure container, main sealing surface and main bolt hole of nuclear power station reactor
WO2009005446A1 (en) * 2007-07-05 2009-01-08 Novator Ab An orbital drilling tool unit
CN103207187A (en) * 2012-01-17 2013-07-17 大日本网屏制造株式会社 Appearance Inspection Apparatus And Method
CN202994342U (en) * 2012-11-12 2013-06-12 中国广东核电集团有限公司 Nuclear power plant bolt stress data collection device and detection device thereof
CN103357928A (en) * 2013-06-27 2013-10-23 中广核工程有限公司 Method for repairing main screw hole of reactor pressure vessel
CN104751914A (en) * 2013-12-31 2015-07-01 中核武汉核电运行技术股份有限公司 Non-destructive inspection circumferential position correction method for thread hole belt of nuclear reactor pressure vessel
CN205629828U (en) * 2016-05-13 2016-10-12 中广核研究院有限公司 Screw defect detecting and prosthetic devices of nuclear power station tun and equipment

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