CN103400610A - Bolt for nuclear reactor container - Google Patents
Bolt for nuclear reactor container Download PDFInfo
- Publication number
- CN103400610A CN103400610A CN2013103652479A CN201310365247A CN103400610A CN 103400610 A CN103400610 A CN 103400610A CN 2013103652479 A CN2013103652479 A CN 2013103652479A CN 201310365247 A CN201310365247 A CN 201310365247A CN 103400610 A CN103400610 A CN 103400610A
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- China
- Prior art keywords
- bolt
- section
- cross
- variable cross
- converter
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- 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.)
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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
Abstract
A disclosed bolt for a nuclear reactor container comprises a varied-cross-section bolt, a measuring bar, a guide seat, a pin, a positioning sleeve, a measuring instrument, an AD converter and an industrial control computer; the axial direction cross section of the varied-cross-section bolt is step-shaped, and the diameter of the right segment cross section is less than the diameter of the left segment cross section; the measuring bar is connected to the guide seat via a magnetic quick connector; the measuring bar is connected to the AD converter via a shield cable; and the AD converter converts an analog signal output by the measuring bar into a digital signal and transfers to the industrial control computer, and the industrial control computer controls the stretching length and the stretching force of the varied-cross-section bolt. Because the employed varied-cross-section bolt has the smaller cross section, the elongation is increased and the measurement amount by the sensor is increased, and thus the relative error is reduced while under a same measurement error. The bolt of the invention has the characteristics of rapid connection, saved space, simultaneous measurement on the stretching length and the stretching force, flexible measurement mode and on-line monitoring.
Description
Technical field
The present invention relates to a kind of bolt pick-up unit, it generally is applied to the pretension of nuclear reactor pressure container top cover cover flange sealing bolt and the bolt that bolt elongate amount and stretching force measurement, particularly a kind of nuclear reactor vessel are used.
Background technology
China at present main power source is provided by fuel-burning power plant, however coal reserves constantly reduce, burning coal can produce the harmful gases such as great amount of carbon dioxide, causes greenhouse effect.At present,, although new energy technology has also obtained fast development, be subject to all condition restriction, can not spread.Therefore, Nuclear Power Development progressively rises to the national strategy level of China, is the important directions in the fields such as development energy industry and war industry, is the major domain that improves growth of the national economic and national defence ability.
Nuclear reactor is the key equipment of nuclear power station, is " heart " of nuclear power station, is also the source of nuclear radiation.The staff during changing nuclear fuel, needs to open and close the nuclear reactor vessel top cover.When opening or close top cover, usually use bolt tensioning jack realize the fastening of nut and remove bolt tension.When using bolt tensioning jack to stretch to bolt, need to measure bolt elongate amount and tensile force, prevent that bolt from excessively being stretched or tensile elongation is inadequate.
There is abrupt-change cross section in existing nuclear power with bolt, when stretching,, if amount of tension is controlled the bad fracture that there will be, needs additionally to add sensor in the bolt outside wiring inconvenience when measuring.
Summary of the invention
The problems referred to above that exist for solving prior art, the present invention will design the bolt that a kind of nuclear reactor vessel that integrates bolt elongate amount and tensile force measurement and on-line monitoring is used.
To achieve these goals, technical scheme of the present invention is as follows: the bolt that a kind of nuclear reactor vessel is used 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 xsect is less than the diameter of left section xsect;
Described guide holder is threaded connection the right-hand member that is locked to the variable cross section bolt, makes the variable cross section bolt become as a whole with guide holder;
Described abutment sleeve is arranged on guide holder by the ball way of contact; Described sounding rod is arranged in the sounding rod mounting hole;
Described sounding rod is installed in abutment sleeve by pin, makes sounding rod, pin and abutment sleeve become as a whole;
Described measurement instrument is connected on guide holder by magnetic rapid-acting coupling; Measurement instrument is connected on AD converter by shielded cable, AD converter is converted to digital quantity signal with the analog signals of measurement instrument output and is sent in industrial computer, and industrial computer is according to tensile elongation and the tensile force of the Data Control variable cross section bolt that feeds back.
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 the variable cross section bolt, make suitable the reducing in a part of cross section of this bolt.When this bolt bore onesize power, because there is less cross section in bolt, therefore its elongation quantitative change is large, the measurement quantitative change of sensor was 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 and variable cross section bolt, reduced widely the set-up time of measurement instrument, avoid operating personnel to be in for a long time among the nuclear radiation environment.
3, conserve space.It is inner that sounding rod of the present invention is positioned at the variable cross section bolt, do not take the space outerpace of bolt, especially applicable in the place that installing space is narrow and small.Make scene use, connect up convenient.
4, measure simultaneously elongation and tensile force.Measurement instrument of the present invention when measuring the bolt elongate amount,, according to bolt elongate amount and properties of materials, also can be measured the suffered pulling force of bolt indirectly.
5, metering system is flexible.The present invention can, according to the degree of depth of bolt measured hole, measure elongation and the tensile force of the inner arbitrfary point of bolt.
6, on-line monitoring.Measurement instrument output analog signals of the present invention, can be sent to it on industrial computer by AD converter, and industrial computer is according to the size of the Data Control bolt axial tensile force that records.
Description of drawings
The present invention is 1 of drawings attached only, wherein:
Fig. 1 is structural representation of the present invention.
In figure: 1, variable cross section bolt, 2, sounding rod, 3, the 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, the bolt that a kind of nuclear reactor vessel is used, 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 xsect is less than the diameter of left section xsect;
Described guide holder 4 is threaded connection the right-hand member that is locked to variable cross section bolt 1, makes 4 one-tenth of variable cross section bolt 1 and guide holders as a whole;
Described abutment sleeve 6 is arranged on guide holder 4 by the ball way of contact; 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 6 one-tenth of abutment sleeves;
Described measurement instrument 7 is connected on guide holder 4 by magnetic rapid-acting coupling; Measurement instrument 7 is connected on AD converter 8 by shielded cable, AD converter 8 is converted to digital quantity signal with the analog signals of measurement instrument 7 outputs and is sent in industrial computer 9, and industrial computer 9 is according to tensile elongation and the tensile force of the Data Control variable cross section bolt 1 that feeds back.
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,, not take the present invention as restriction, all any modifications of doing within the spirit and principles in the present invention, be equal to and replace and improvement etc., within all should being included in protection scope of the present invention.
Claims (2)
1. the bolt that nuclear reactor vessel is used, 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 xsect is less than the diameter of left section xsect;
Described guide holder (4) is threaded connection the right-hand member that is 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 the ball way of contact; 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) and abutment sleeve (6) become as a whole;
Described measurement instrument (7) is connected on guide holder (4) by magnetic rapid-acting coupling; Measurement instrument (7) is connected on AD converter (8) by shielded cable, AD converter (8) is converted to digital quantity signal with the analog signals of measurement instrument (7) output and is sent in industrial computer (9), and industrial computer (9) is according to tensile elongation and the tensile force of the Data Control variable cross section bolt (1) that feeds back.
2. the bolt used of a kind of nuclear reactor vessel according to claim 1, it 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 true CN103400610A (en) | 2013-11-20 |
| CN103400610B CN103400610B (en) | 2016-01-13 |
Family
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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 |
|---|
| 刘俊杰 等: "10MW高温气冷堆压力容器主螺栓液压拉伸机", 《核动力工程》, vol. 21, no. 6, 31 December 2000 (2000-12-31), pages 503 - 506 * |
| 褚福国 等: "核反应堆压力容器螺栓拉伸机设计初探", 《一重技术》, 31 December 2001 (2001-12-31), pages 38 - 40 * |
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| Publication number | Publication date |
|---|---|
| CN103400610B (en) | 2016-01-13 |
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| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20160113 Termination date: 20200819 |
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| CF01 | Termination of patent right due to non-payment of annual fee |