CN103400610B - A kind of bolt of nuclear reactor vessel - Google Patents
A kind of bolt of nuclear reactor vessel Download PDFInfo
- Publication number
- CN103400610B CN103400610B CN201310365247.9A CN201310365247A CN103400610B CN 103400610 B CN103400610 B CN 103400610B CN 201310365247 A CN201310365247 A CN 201310365247A CN 103400610 B CN103400610 B CN 103400610B
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- China
- Prior art keywords
- bolt
- section
- variable cross
- measurement instrument
- guide holder
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
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Classifications
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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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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of bolt of nuclear reactor vessel, comprise variable cross section bolt, sounding rod, guide holder, pin, abutment sleeve, measurement instrument, AD converter and industrial computer; The axial cross section of described variable cross section bolt is stepped, and the diameter of right section of xsect is less than the diameter of left section of xsect; Described measurement instrument is connected on guide holder by magnetic rapid-acting coupling; Measurement instrument is connected in AD converter by shielded cable, the analog signals that measurement instrument exports is converted to digital quantity signal and is sent in industrial computer by AD converter, and industrial computer is according to the tensile elongation of the Data Control variable cross section bolt fed back and tensile force.The present invention adopts variable cross section bolt, and because bolt exists less cross section, therefore it extends quantitative change greatly, and the measurement quantitative change of sensor is large, and under same measuring error, relative error diminishes.The present invention has quick connection, conserve space, measures elongation and tensile force, metering system flexibly and the feature of on-line monitoring simultaneously.
Description
Technical field
The present invention relates to a kind of bolt pick-up unit, it is generally applied to the pretension of nuclear reactor pressure container top cover cover flange sealing bolt and the measurement, particularly a kind of bolt of nuclear reactor vessel of bolt elongate amount and tensile force.
Background technology
The main at present power source of China is provided by fuel-burning power plant, but coal reserves constantly reduces, and burning coal can produce the harmful gases such as great amount of carbon dioxide, causes greenhouse effect.At present, although new energy technology also obtains fast development, be subject to the restriction of all conditions, can not spread.Therefore, Nuclear Power Development progressively rises to the national strategy level of China, is the important directions in the development field such as energy industry and war industry, is the major domain improving growth of the national economic and national defence ability.
Nuclear reactor is the key equipment of nuclear power station, is nuclear power station " heart ", is also the source of nuclear radiation.Staff, during replacing nuclear fuel, needs to open and close nuclear reactor vessel top cover.When opening or close top cover, bolt tensioning jack is usually used to realize the fastening of nut to bolt tension and remove.When bolt tensioning jack stretches to bolt in use, need to measure bolt elongate amount and tensile force, prevent bolt to be excessively stretched or tensile elongation inadequate.
There is abrupt-change cross section in existing nuclear power bolt, when stretching, if amount of tension controls badly to there will be fracture, when measuring need outside bolt volume additional sensor, wiring inconvenience.
Summary of the invention
For solving the problems referred to above that prior art exists, the present invention will design a kind of bolt integrating the nuclear reactor vessel of bolt elongate amount and tensile force measurement and on-line monitoring.
To achieve these goals, technical scheme of the present invention is as follows: a kind of bolt of nuclear reactor vessel, comprises variable cross section bolt, sounding rod, guide holder, pin, abutment sleeve, measurement instrument, AD converter and industrial computer;
The axial cross section of described variable cross section bolt is stepped, and the diameter of right section of xsect is less than the diameter of left section of xsect;
Described guide holder is threaded connection the right-hand member being locked to variable cross section bolt, makes variable cross section bolt become as a whole with guide holder;
Described abutment sleeve is arranged on guide holder by ball contact mode; Described sounding rod is arranged in sounding rod mounting hole;
Described sounding rod is installed in abutment sleeve by pin, makes sounding rod, pin become as a whole with abutment sleeve;
Described measurement instrument is connected on guide holder by magnetic rapid-acting coupling; Measurement instrument is connected in AD converter by shielded cable, the analog signals that measurement instrument exports is converted to digital quantity signal and is sent in industrial computer by AD converter, and industrial computer is according to the tensile elongation of the Data Control variable cross section bolt fed back and tensile force.
The material that variable cross section bolt of the present invention uses is 18Cr2Ni4WA.
Compared with prior art, the present invention has following beneficial effect:
1, measuring accuracy is high.Adopt variable cross section bolt, make the reduction that a part of cross section of this bolt is suitable.When this bolt bears onesize power, because bolt exists less cross section, therefore it extends quantitative change greatly, and the measurement quantitative change of sensor is large, and under same measuring error, relative error diminishes.
2, connect fast.Adopt magnetic rapid-acting coupling to be connected between measurement instrument of the present invention with variable cross section bolt, greatly reduce the set-up time of measurement instrument, avoid operating personnel to be in for a long time among nuclear radiation environment.
3, conserve space.It is inner that sounding rod of the present invention is positioned at variable cross section bolt, and do not take the space outerpace of bolt, the place narrow and small at installing space is especially applicable.Make onsite application, connect up convenient.
4, measure elongation and tensile force simultaneously.Measurement instrument of the present invention, while measurement bolt elongate amount, according to bolt elongate amount and properties of materials, also can go out pulling force suffered by bolt by indirect inspection.
5, metering system is flexible.The present invention according to the degree of depth of bolt measured hole, can measure elongation and the tensile force of the inner arbitrfary point of bolt.
6, on-line monitoring.Measurement instrument of the present invention exports analog signals, and can be sent on industrial computer by AD converter by it, industrial computer is according to the size of the Data Control bolt axial tensile force recorded.
Accompanying drawing explanation
The present invention is drawings attached 1 only, wherein:
Fig. 1 is structural representation of the present invention.
In figure: 1, variable cross section bolt, 2, sounding rod, 3, sounding rod mounting hole, 4, guide holder, 5, pin, 6, abutment sleeve, 7, measurement instrument, 8, AD converter, 9, industrial computer.
Embodiment
Below in conjunction with accompanying drawing, the present invention is described further.As shown in Figure 1, a kind of bolt of nuclear reactor vessel, comprises variable cross section bolt 1, sounding rod 2, guide holder 4, pin 5, abutment sleeve 6, measurement instrument 7, AD converter 8 and industrial computer 9;
The axial cross section of described variable cross section bolt 1 is stepped, and the diameter of right section of xsect is less than the diameter of left section of xsect;
Described guide holder 4 is threaded connection the right-hand member being locked to variable cross section bolt 1, makes variable cross section bolt 1 as a whole with guide holder 4 one-tenth;
Described abutment sleeve 6 is arranged on guide holder 4 by ball contact mode; Described sounding rod 2 is arranged in sounding rod mounting hole 3;
Described sounding rod 2 is installed in abutment sleeve 6 by pin 5, makes sounding rod 2, pin 5 as a whole with abutment sleeve 6 one-tenth;
Described measurement instrument 7 is connected on guide holder 4 by magnetic rapid-acting coupling; Measurement instrument 7 is connected in AD converter 8 by shielded cable, the analog signals that measurement instrument 7 exports is converted to digital quantity signal and is sent in industrial computer 9 by AD converter 8, and industrial computer 9 is according to the tensile elongation of the Data Control variable cross section bolt 1 fed back and tensile force.
The material that variable cross section bolt 1 of the present invention uses is 18Cr2Ni4WA.
The foregoing is only preferred embodiment of the present invention, is not restriction with the present invention, and all any amendments done within the spirit and principles in the present invention, equivalent replacement and improvement etc., all should be included within protection scope of the present invention.
Claims (2)
1. a bolt for nuclear reactor vessel, is characterized in that: comprise variable cross section bolt (1), sounding rod (2), guide holder (4), pin (5), abutment sleeve (6), measurement instrument (7), AD converter (8) and industrial computer (9);
The axial cross section of described variable cross section bolt (1) is stepped, and the diameter of right section of xsect is less than the diameter of left section of xsect;
Described guide holder (4) is threaded connection the right-hand member being locked to variable cross section bolt (1), makes variable cross section bolt (1) become as a whole with guide holder (4);
Described abutment sleeve (6) is arranged on guide holder (4) by ball contact mode; Described sounding rod (2) is arranged in sounding rod mounting hole (3);
Described sounding rod (2) is installed in abutment sleeve (6) by pin (5), makes sounding rod (2), pin (5) becomes as a whole with abutment sleeve (6);
Described measurement instrument (7) is connected on guide holder (4) by magnetic rapid-acting coupling; Measurement instrument (7) is connected in AD converter (8) by shielded cable, the analog signals that measurement instrument (7) exports is converted to digital quantity signal and is sent in industrial computer (9) by AD converter (8), and industrial computer (9) is according to the tensile elongation of the Data Control variable cross section bolt (1) fed back and tensile force.
2. the bolt of a kind of nuclear reactor vessel according to claim 1, is characterized in that: the material that described variable cross section bolt (1) uses is 18Cr2Ni4WA.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310365247.9A CN103400610B (en) | 2013-08-19 | 2013-08-19 | A kind of bolt of nuclear reactor vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310365247.9A CN103400610B (en) | 2013-08-19 | 2013-08-19 | A kind of bolt of nuclear reactor vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103400610A CN103400610A (en) | 2013-11-20 |
| CN103400610B true CN103400610B (en) | 2016-01-13 |
Family
ID=49564214
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201310365247.9A Expired - Fee Related CN103400610B (en) | 2013-08-19 | 2013-08-19 | A kind of bolt of nuclear reactor vessel |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103400610B (en) |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN200968840Y (en) * | 2006-11-08 | 2007-10-31 | 哈尔滨汽轮机厂有限责任公司 | Apparatus for measuring screw bolt elongation amount for steam turbine assembly measurement |
| US20090013518A1 (en) * | 2004-06-02 | 2009-01-15 | Jean-Michel Monville | Method for controlling tensile stress of a shank, such as a screw or dowel pin, and device for carrying out said method |
| CN202494598U (en) * | 2012-03-13 | 2012-10-17 | 天津市产品质量监督检测技术研究院 | Tension tester for detecting tensile strength of electric wire insulating layer |
-
2013
- 2013-08-19 CN CN201310365247.9A patent/CN103400610B/en not_active Expired - Fee Related
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20090013518A1 (en) * | 2004-06-02 | 2009-01-15 | Jean-Michel Monville | Method for controlling tensile stress of a shank, such as a screw or dowel pin, and device for carrying out said method |
| CN200968840Y (en) * | 2006-11-08 | 2007-10-31 | 哈尔滨汽轮机厂有限责任公司 | Apparatus for measuring screw bolt elongation amount for steam turbine assembly measurement |
| CN202494598U (en) * | 2012-03-13 | 2012-10-17 | 天津市产品质量监督检测技术研究院 | Tension tester for detecting tensile strength of electric wire insulating layer |
Non-Patent Citations (2)
| Title |
|---|
| 10MW高温气冷堆压力容器主螺栓液压拉伸机;刘俊杰 等;《核动力工程》;20001231;第21卷(第6期);503-506页 * |
| 核反应堆压力容器螺栓拉伸机设计初探;褚福国 等;《一重技术》;20011231;38-40页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN103400610A (en) | 2013-11-20 |
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| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20160113 Termination date: 20200819 |