CN110047601A - A kind of U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator - Google Patents
A kind of U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator Download PDFInfo
- Publication number
- CN110047601A CN110047601A CN201910429026.0A CN201910429026A CN110047601A CN 110047601 A CN110047601 A CN 110047601A CN 201910429026 A CN201910429026 A CN 201910429026A CN 110047601 A CN110047601 A CN 110047601A
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- CN
- China
- Prior art keywords
- transfer pipe
- heat
- single tube
- steam generator
- power plant
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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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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- 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
The present invention provides a kind of U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator comprising heat-transfer pipe, bottom supporting, intermediate support, pedestal and loading device；The both ends of the heat-transfer pipe are fixed by the bottom supporting, are supported between the both ends of the heating surface bank by the intermediate support；The heating surface bank is divided into two sections of straight pipes and one section of arc section, and two sections of straight pipes are connect with the both ends of the arc section respectively, and arc section applies load by the loading device；The heat-transfer pipe uses the heat-transfer pipe of maximum deflection radius.The U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator provided by the invention, can complete single tube dynamic characteristic test, to obtain the factor for influencing heat-transfer pipe single tube dynamic characteristic.
Description
Technical field
The present invention relates to steam generator and heat exchanger designs fields, and in particular to a kind of nuclear power plant's vertical steam generation
The U-shaped heat-transfer pipe single tube dynamic property tester of device.
Background technique
Steam generator is the capital equipment that the heat that reactor core generates is discharged, and is reactor coolant loop pressure
The a part on boundary.The converting heat of reactor coolant loop is steam by steam generator, and steam is sent into steam turbine generator
Group power generation.Steam generator is mainly by components groups such as lower head, tube sheet, secondary side body, heating surface bank and water separators
At wherein the important component of one, secondary circuit pressure boundary, operational reliability requirement is isolated in steam generator heat-transfer pipe Shu Zuowei
It is very high.
Heat-transfer pipe will cause thing because breakage caused by water flow vibration can reduce the thermal efficiency and cause escape of radioactivity when serious
Therefore shutdown.Therefore analysis heat-transfer pipe vibration mechanism and take inhibit vibrate measure be steam generator design in one it is important
Research contents.The kinetic parameter that the research of heat-transfer pipe dynamic characteristic test obtains can be the kinematic analysis of heat-transfer pipe, including stream
It causes vibration analysis and earthquake analysis to provide test basis, while analyzing for the wear-out life of heat-transfer pipe that provide important design defeated
Enter.
Steam generator heat-transfer pipe single tube dynamic characteristic test is primarily to investigating influences heat-transfer pipe single tube dynamic characteristic
Factor, consider influence of the anti-vibration bar to heat-transfer pipe dynamic characteristic, the influence in primary study gap and pretightning force, with calculation and check
The correctness of model.Heat-transfer pipe single tube dynamic characteristic test has chosen the maximum heat-transfer pipe of bending radius as test pair
As, while being provided with gap in bend pipe area and pre-tightening force loading device to simulate influence of the anti-vibration bar to heat-transfer pipe dynamic characteristic.
Summary of the invention
It is dynamic that in view of the deficiencies of the prior art, the present invention proposes a kind of U-shaped heat-transfer pipe single tubes of nuclear power plant's vertical steam generator
Step response experimental rig.
The U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator provided by the invention, feature
Including heat-transfer pipe, bottom supporting, intermediate support, pedestal and loading device；The both ends of the heat-transfer pipe pass through the bottom supporting
It is fixed, it is supported between the both ends of the heating surface bank by the intermediate support；The heating surface bank be divided into two sections of straight pipes and
One section of arc section, two sections of straight pipes are connect with the both ends of the arc section respectively, and arc section is applied by the loading device
Load lotus；The heat-transfer pipe uses the heat-transfer pipe of maximum deflection radius.
Preferably, the heat-transfer pipe is welded and fixed by sealing welding and the bottom supporting.
Preferably, the straight pipe is fixed by five layers of intermediate support.
Preferably, the intermediate support for the perforative Kong Weisan leaf plum blossom hole of the heat-transfer pipe.
Preferably, the arc section simulates seven groups of anti-vibration bar constraints by loading structure.
Preferably, the heat-transfer pipe include first across, centre three across with last across；Wherein, described first across distance
For 537mm；The centre three across, it is each across distance be 933mm；It is described last across distance be 932mm.
Preferably, the pedestal is square cold-bend hollow profiled bar, and the square cold-bend hollow profiled bar and concrete foundation pass through
Configuration by pre-embedded bolt to be coupled.
Preferably, the intermediate support and bottom supporting are connect by bolt with the square cold-bend hollow profiled bar.
It preferably, further include sensor；The bottom of the heat-transfer pipe is arranged in the sensor, for measuring the heat transfer
The stress of pipe.
Preferably, the upper and lower part of the heat-transfer pipe is respectively equipped with cushion block identical with antivibration strip material；The heat transfer
The top of tube bank is configured to pass screw rod and adjusts the load being applied on heat-transfer pipe.
Compared with prior art, the invention has the following advantages:
1, the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator provided by the invention, can be with
Single tube dynamic characteristic test is completed, to obtain the factor for influencing heat-transfer pipe single tube dynamic characteristic.
2, the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator provided by the invention, can
The simulation to steam generator single tube dynamic characteristic test is completed by the experimental rig, investigating influences heat-transfer pipe single tube dynamic
The factor of characteristic considers influence of the anti-vibration bar to heat-transfer pipe dynamic characteristic, the influence in primary study gap and pretightning force, to check
The correctness of computation model.
Detailed description of the invention
Fig. 1 is the U-shaped heat-transfer pipe single tube dynamic characteristic of nuclear power plant's vertical steam generator for meeting the preferred embodiment of the present invention
Experimental rig schematic diagram.
Fig. 2 a and 2b be meet the preferred embodiment of the present invention heat-transfer pipe single tube dynamic property tester intermediate support and
Bottom supporting structure schematic diagram.
Fig. 3 is the bend loss loading structure schematic diagram for meeting the preferred embodiment of the present invention.
Wherein, 1, bottom supporting 2, pedestal 3, heat-transfer pipe 4, intermediate support 5, loading structure
Specific embodiment
In order to make the foregoing objectives, features and advantages of the present invention clearer and more comprehensible, with reference to the accompanying drawing and specific real
Applying mode, the present invention is described in further detail.
One embodiment of the invention provides a kind of U-shaped heat-transfer pipe single tube dynamic characteristic test of nuclear power plant's vertical steam generator
Device, heat-transfer pipe single tube dynamic characteristic test using the 164th row's maximum deflection radius, straight pipe five across heat-transfer pipe, testpieces
Detailed construction it is as shown in Figure 1.
Single column run part keep first across with last across span it is consistent with actual size, remaining 8 across be reduced to 3 across.
Straight pipe first across distance be 537mm, centre three across distance be 933mm × 3, last across distance be 932mm.
For heat-transfer pipe in addition to straight pipe shortens, other such as material and shape, size are all consistent with actual product.
Fig. 2 a be simulate structure support plate intermediate support structure, the plum blossom hole shape of every piece of support plate simulating piece, size,
And the thickness of support plate is consistent with practical structures.
Fig. 2 b be simulate tube plate structure bottom supporting, tube sheet simulating piece with a thickness of 50mm, the bore size of simulating piece
It is consistent with practical structures.
The pedestal of entire testpieces is square cold-bend hollow profiled bar, and square steel is coupled with concrete foundation by pre-embedded bolt.
After the completion of in, leveling, final grouting concrete is connected square steel with concrete foundation entire pedestal, guarantees entire
The rigidity of pedestal.
Bottom supporting, intermediate support are located on square steel pedestal, are connect by bolt with square steel, then complete to adjust neutralization
Equality.After heat-transfer pipe single tube passes through intermediate support, welded with the bottom supporting of simulation tube sheet in primary side.
According to the position of practical anti-vibration bar, the device of pressure can be measured in the corresponding part setting of heat transfer pipe bend, such as
Shown in Fig. 3.Due to there are seven groups of anti-vibration bars, therefore 14 such devices are set in total.
Sensor fastening device is coupled by two bolts with basic square steel.Bottom of the tube of conducting heat is equipped with a force snesor, uses
The power suffered by measurement heat-transfer pipe.A cushion block identical with antivibration strip material is respectively arranged in heat-transfer pipe up and down, to simulate antivibration
Item.Top uses screw rod up and down adjustment spacing, and screw rod is fastened on the securing means by bolt head.This testpieces is mainly used for passing
Single heat pipe dynamic characteristic test, to obtain the factor for influencing heat-transfer pipe dynamic characteristic, the correctness of calculation and check model.
Compared with prior art, the present embodiment has the advantages that
1, the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator provided in this embodiment, can
To complete single tube dynamic characteristic test, to obtain the factor for influencing heat-transfer pipe single tube dynamic characteristic.
2, the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator provided in this embodiment, energy
It is enough that the simulation to steam generator single tube dynamic characteristic test is completed by the experimental rig, it is dynamic to investigate influence heat-transfer pipe single tube
The factor of step response considers influence of the anti-vibration bar to heat-transfer pipe dynamic characteristic, the influence in primary study gap and pretightning force, with school
The correctness of core computation model.
Those skilled in the art can use different methods to achieve the described function each specific application, but
It is that such implementation should not be considered as beyond the scope of the present invention.
Obviously, those skilled in the art can carry out various modification and variations without departing from spirit of the invention to invention
And range.If in this way, these modifications and changes of the present invention belong to the claims in the present invention and its equivalent technologies range it
Interior, then the invention is also intended to include including these modification and variations.
Claims (10)
1. a kind of U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator, feature it include heat transfer
Pipe, bottom supporting, intermediate support, pedestal and loading device；The both ends of the heat-transfer pipe are fixed by the bottom supporting, described
It is supported between the both ends of heating surface bank by the intermediate support；The heating surface bank is divided into two sections of straight pipes and one section of circular arc
Section, two sections of straight pipes are connect with the both ends of the arc section respectively, and arc section applies load by the loading device；Institute
State the heat-transfer pipe that heat-transfer pipe uses maximum deflection radius.
2. the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator as described in claim 1, special
Sign is that the heat-transfer pipe is welded and fixed by sealing welding and the bottom supporting.
3. the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator as described in claim 1, special
Sign is that the straight pipe is fixed by five layers of intermediate support.
4. the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator as claimed in claim 3, special
Sign is, the intermediate support for the perforative Kong Weisan leaf plum blossom hole of the heat-transfer pipe.
5. such as the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator that claim 1 is stated, feature
It is, the arc section is simulated seven groups of anti-vibration bars by loading structure and constrained.
6. such as the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator that claim 1 is stated, feature
Be, the heat-transfer pipe include first across, centre three across with last across；Wherein, described first across distance be 537mm；Institute
State centre three across, it is each across distance be 933mm；It is described last across distance be 932mm.
7. such as the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator that claim 1 is stated, feature
It is, the pedestal is square cold-bend hollow profiled bar, and the square cold-bend hollow profiled bar is configured to pass with concrete foundation
Pre-embedded bolt connection.
8. such as the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator that claim 7 is stated, feature
It is, the bottom supporting and intermediate support are connect by bolt with the square cold-bend hollow profiled bar.
9. such as the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator that claim 1 is stated, feature
It is, further includes sensor；The bottom of the heat-transfer pipe is arranged in the sensor, for measuring the stress of the heat-transfer pipe.
10. special such as the U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator that claim 1 is stated
Sign is that the upper and lower part of the heat-transfer pipe is respectively equipped with cushion block identical with antivibration strip material；The top of the heat-transfer pipe
It is configured to pass screw rod and adjusts the load being applied on heat-transfer pipe.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910429026.0A CN110047601A (en) | 2019-05-22 | 2019-05-22 | A kind of U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910429026.0A CN110047601A (en) | 2019-05-22 | 2019-05-22 | A kind of U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator |
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| Publication Number | Publication Date |
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| CN110047601A true CN110047601A (en) | 2019-07-23 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201910429026.0A Pending CN110047601A (en) | 2019-05-22 | 2019-05-22 | A kind of U-shaped heat-transfer pipe single tube dynamic property tester of nuclear power plant's vertical steam generator |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113695862A (en) * | 2021-09-02 | 2021-11-26 | 宝银特种钢管有限公司 | Sleeving method for multilayer spiral tube bundle with special-shaped space bend |
-
2019
- 2019-05-22 CN CN201910429026.0A patent/CN110047601A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113695862A (en) * | 2021-09-02 | 2021-11-26 | 宝银特种钢管有限公司 | Sleeving method for multilayer spiral tube bundle with special-shaped space bend |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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