CN113358298A - COD-adjustable nuclear-grade pipeline leakage rate measurement experimental device and method - Google Patents
COD-adjustable nuclear-grade pipeline leakage rate measurement experimental device and method Download PDFInfo
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- CN113358298A CN113358298A CN202110503304.XA CN202110503304A CN113358298A CN 113358298 A CN113358298 A CN 113358298A CN 202110503304 A CN202110503304 A CN 202110503304A CN 113358298 A CN113358298 A CN 113358298A
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- 238000005259 measurement Methods 0.000 title claims abstract description 17
- 238000000034 method Methods 0.000 title claims abstract description 12
- 230000007246 mechanism Effects 0.000 claims abstract description 98
- 238000012360 testing method Methods 0.000 claims abstract description 66
- 238000006073 displacement reaction Methods 0.000 claims abstract description 26
- 238000002474 experimental method Methods 0.000 claims abstract description 7
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- 238000001816 cooling Methods 0.000 claims description 22
- 239000012530 fluid Substances 0.000 claims description 20
- 230000008859 change Effects 0.000 claims description 6
- 238000007789 sealing Methods 0.000 claims description 6
- 238000000429 assembly Methods 0.000 claims description 5
- 230000000712 assembly Effects 0.000 claims description 5
- 238000007599 discharging Methods 0.000 claims description 4
- 229920006395 saturated elastomer Polymers 0.000 description 9
- 238000010168 coupling process Methods 0.000 description 7
- 238000005859 coupling reaction Methods 0.000 description 7
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- 238000010586 diagram Methods 0.000 description 5
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 3
- 239000001301 oxygen Substances 0.000 description 3
- 229910052760 oxygen Inorganic materials 0.000 description 3
- 238000011160 research Methods 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 229910052786 argon Inorganic materials 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
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- 239000012535 impurity Substances 0.000 description 1
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- 238000000691 measurement method Methods 0.000 description 1
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- 238000012986 modification Methods 0.000 description 1
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- 238000006467 substitution reaction Methods 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
- G01M3/26—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors
- G01M3/28—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds
- G01M3/2807—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds for pipes
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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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Abstract
The application discloses a COD adjustable nuclear grade pipeline leakage rate measurement experiment device and a method, and the device comprises a supporting rack, a conveying mechanism, a crack testing mechanism, a load applying mechanism and a crack measuring mechanism; the crack testing mechanism comprises a crack ring sheet, an inlet pipe section, an outlet pipe section and a seal head; two ends of the crack ring sheet are respectively connected with one end of the inlet pipe section and one end of the outlet pipe section; end sockets are arranged at the end part of the inlet pipe section far away from the crack ring piece and the end part of the outlet pipe section far away from the crack ring piece; the outlet pipe section is provided with a first discharge pipe section and a second discharge pipe section; the conveying mechanism comprises a main pipeline and a first mass flowmeter arranged on the main pipeline; one end of the main pipeline is communicated with the inlet pipe section; the load applying mechanism is connected with the inlet pipe section and the outlet pipe section; the crack measuring mechanism is connected with the crack ring sheet. The method and the device have the advantages that the test data under different crack opening displacements are measured by using one crack ring piece, and the test cost is reduced.
Description
Technical Field
The application relates to the technical field of leakage measurement, in particular to a nuclear grade pipeline leakage rate measurement experimental device and method with adjustable COD.
Background
The leakage-before-break analysis (LBB) is a technology applied to the pipeline safety of nuclear power stations at home and abroad. The pre-burst leakage technology can be applied to the research on leakage of a main steam pipeline, leakage of a main water supply pipeline and leakage of a steam generator of a nuclear power station, the size and the safety of a pipeline crack are evaluated through measuring the crack leakage rate, and the research on the known size crack leakage rate is very important.
The leakage process is that high-temperature and high-pressure fluid is sprayed into a low-pressure environment through cracks, and the supercooled water is subjected to flash evaporation leakage and also subjected to phase change conversion to become a gas-liquid two-phase mixture. The leakage is related to the thermal hydraulic characteristics of the fluid, the geometrical parameters of the crack, and in particular the aspect ratio of the crack.
The model research of the crack leakage process needs a large amount of high-precision test data to verify, so that the effectiveness and the reliability of the leakage rate simulation software are verified. Meanwhile, the test analysis can also analyze the influence of factors such as Crack Opening Displacement (COD), morphology size and roughness on the leakage rate. At present, most of tests for measuring the leakage rate of the pipeline are manually preformed cracks, in the test for measuring the leakage rate of the pipeline cracks, a large amount of leakage data of the cracks with different crack opening displacements need to be obtained, a plurality of crack test pieces need to be manufactured, and the test cost is high.
Disclosure of Invention
The embodiment of the invention provides a nuclear-grade pipeline leakage rate measurement experimental device and method with adjustable COD (chemical oxygen demand), and solves the technical problem that in the prior art, a plurality of crack test pieces are needed in a pipeline crack leakage rate measurement test, so that the test cost is high.
In a first aspect, the embodiment of the invention provides a nuclear grade pipeline leakage rate measurement experiment device with adjustable COD (chemical oxygen demand), which comprises a support rack, a conveying mechanism, a crack test mechanism, a load applying mechanism and a crack measuring mechanism, wherein the support rack is arranged on the support rack; the crack testing mechanism comprises a crack ring sheet, an inlet pipe section, an outlet pipe section and a sealing head; two ends of the crack ring piece are respectively connected with one end of the inlet pipe section and one end of the outlet pipe section; the end part of the inlet pipe section, which is far away from the crack ring piece, and the end part of the outlet pipe section, which is far away from the crack ring piece, are provided with the seal heads; the inlet pipe section and the outlet pipe section are both supported on the support rack; the outlet pipe section (330) is provided with a first discharge pipe section (350) and a second discharge pipe section (360); the first discharge pipe section (350) is used for opening and discharging gas in the crack testing mechanism (300) before testing, and the second discharge pipe section (360) is used for opening and discharging residual working medium in the crack testing mechanism (300) after testing; the conveying mechanism comprises a main pipeline and a first mass flow meter arranged on the main pipeline; one end of the main pipeline is communicated with the inlet pipe section, and the other end of the main pipeline is communicated with a first working medium source; the load applying mechanism is connected with the inlet pipe section and the outlet pipe section and can apply load to the inlet pipe section and the outlet pipe section so as to change crack opening displacement on the crack ring piece; the crack measuring mechanism is connected with the crack ring piece and can measure the crack opening displacement on the crack ring piece.
In a possible implementation manner, the conveying mechanism further comprises a branch pipeline, a second mass flow meter installed in the branch pipeline, a first working medium valve and a second working medium valve; both ends of the branch pipeline are communicated with the main pipeline, and both ends of the branch pipeline are respectively positioned at both sides of the first mass flow meter; one end of the main pipeline, which is far away from the inlet pipe section, is used for being communicated with a second working medium source at the same time; the first working medium valve is arranged on the main pipeline and is positioned between two ends of the branch pipeline; the second working medium valve is installed on the branch pipeline.
In a possible implementation manner, the conveying mechanism further comprises a main conveying valve, and the main conveying valve is mounted on the main pipeline and is close to an inlet of the main pipeline.
In one possible implementation, the load applying mechanism comprises two force applying assemblies, wherein each force applying assembly comprises a force sensor and a hydraulic pull rod; one end of the hydraulic pull rod is connected with the force sensor, and the force sensor is connected with the support rack; the inlet pipe section and the outlet pipe section are respectively connected with the end parts, far away from the force sensor, of the two hydraulic pull rods.
In a possible implementation manner, a sliding rail is arranged at the upper part of the support rack, and the sliding rail is positioned above the crack testing mechanism and is parallel to the extending direction of the crack testing mechanism; the force application assembly further comprises sliders, the two sliders are connected to the sliding rail in a sliding mode, and the two sliders correspond to the two force sensors and are connected with the two force sensors.
In one possible implementation, the force application assembly further comprises a coupling ring connected to an end of the hydraulic drawbar remote from the force sensor; the two connecting rings are respectively sleeved on the inlet pipe section and the outlet pipe section.
In a possible implementation manner, the crack testing mechanism further includes two extension pipe sections, the two extension pipe sections are respectively connected to the end portion of the inlet pipe section far away from the crack ring piece and the end portion of the outlet pipe section far away from the crack ring piece, and both the two extension pipe sections are supported on the support rack.
In one possible implementation, the support gantry includes a gantry and a fixed ring; the two racks are arranged at intervals, and the top of each rack is provided with an installation groove matched with the extension pipe section; the two fixing rings are respectively connected with the top of the rack and fix the extension pipe section in the mounting groove.
In one possible implementation, the crack measuring mechanism comprises a clip-on extensometer and two fixed pins; one end of each of the two fixing pins is connected to the two measuring ends of the clamp-type extensometer respectively, and the other end of each of the two fixing pins is connected to the crack ring piece and located on two sides of the crack respectively.
In a possible implementation manner, the experiment device for measuring the leakage rate of the nuclear grade pipeline with the adjustable COD further comprises a cooling jacket and a collection water tank; the cooling jacket is arranged on the support rack and surrounds the crack ring sheet; the lower opening of the cooling jacket is used for enabling the working medium leaked by the crack ring sheet to flow out of the lower opening of the cooling jacket; the collecting water tank is arranged below the crack testing mechanism and is used for receiving the working medium which is leaked by the crack ring piece and flows down through the cooling jacket.
In a second aspect, an embodiment of the present invention provides a method for measuring a nuclear pipeline leakage rate by using the experimental apparatus for measuring a nuclear pipeline leakage rate with an adjustable COD, including:
controlling the conveying mechanism to convey a first working medium to the inlet pipe section, and measuring the mass flow of the first working medium by using the first mass flow meter;
and operating the load applying mechanism to apply load to the inlet pipe section and the outlet pipe section so as to enable the crack opening displacement on the crack ring piece to reach a preset value.
One or more technical solutions provided in the embodiments of the present invention have at least the following technical effects or advantages:
the embodiment of the invention provides a nuclear-grade pipeline leakage rate measurement experimental device with adjustable COD (chemical oxygen demand), when the nuclear-grade pipeline leakage rate measurement experimental device with the adjustable COD is used, one end of a main pipeline of a conveying mechanism is communicated with a first working medium source, the first working medium is conveyed to an inlet pipe section through the main pipeline, and a first mass flow meter on the main pipeline can measure the mass flow of the first working medium; the end part of the inlet pipe section, which is far away from the crack ring piece, and the end part of the outlet pipe section, which is far away from the crack ring piece, are provided with seal heads. The first vent tube section was opened prior to testing to vent the gas within the crack testing mechanism. During testing, external force is applied to the inlet pipe section and the outlet pipe section through the load applying mechanism, so that crack opening displacement on the crack ring piece is changed, and the crack opening displacement can be measured by the crack measuring mechanism. The mass flow of the first working medium can be measured by the first mass flow meter, namely the mass flow of the first working medium leaked from the crack ring piece can be obtained, so that the test data of different crack opening displacements can be measured by using one crack ring piece, a plurality of crack test pieces do not need to be manufactured, and the test cost is greatly reduced.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings needed to be used in the description of the embodiments of the present invention or the prior art will be briefly introduced below, and it is obvious that the drawings in the following description are some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to these drawings without creative efforts.
FIG. 1 is a schematic structural diagram of an experimental apparatus for measuring the leakage rate of a nuclear-grade pipeline with adjustable COD provided by an embodiment of the present invention;
FIG. 2 is a schematic structural diagram of a conveying mechanism according to an embodiment of the present invention;
FIG. 3 is a schematic structural diagram of a crack testing mechanism provided in an embodiment of the present invention;
FIG. 4 is a schematic structural diagram of a force application assembly according to an embodiment of the present invention;
FIG. 5 is a schematic view of a crack measuring mechanism and a crack ring plate according to an embodiment of the present invention;
FIG. 6 is a schematic structural diagram of an experimental apparatus for measuring the leakage rate of a nuclear pipeline with adjustable COD, which is provided by an embodiment of the invention and has a cooling jacket and a collection water tank;
fig. 7 is a schematic structural view of the region a in fig. 6.
Icon: 100-a support stand; 110-a gantry; 120-a fixed ring; 130-a slide rail; 200-a conveying mechanism; 210-a main pipeline; 220-a first mass flow meter; 230-branch lines; 240-a second mass flow meter; 250-a first working medium valve; 260-a second working medium valve; 270-delivery main valve; 280-a filter; 290 — access line; 300-crack test mechanism; 310-crack ring sheet; 311-cracking; 320-an inlet pipe section; 330-an outlet pipe section; 340-sealing head; 350 — a first discharge pipe section; 351-a first discharge valve; 360-a second discharge pipe section; 361-a second discharge valve; 370-an extension pipe section; 400-a load applying mechanism; 410-a force application assembly; 411-a force sensor; 412-hydraulic tie rod; 413-a slider; 414-coupling ring; 500-crack measuring mechanism; 510-clip extensometer; 520-two securing pins; 600-a cooling jacket; 610-measurement window; 700-collecting water tank; 710-a drain valve.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, not all, embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
In the description of the embodiments of the present invention, it should be noted that the terms "center", "upper", "lower", "left", "right", "vertical", "horizontal", "inner", "outer", and the like indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are only for convenience in describing the embodiments of the present invention and simplifying the description, but do not indicate or imply that the referred devices or elements must have specific orientations, be configured in specific orientations, and operate, and thus, should not be construed as limiting the present invention. The terms "first," "second," and "third" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance. Furthermore, the terms "mounted," "connected," and "connected" are to be construed broadly and may, for example, be fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. Specific meanings of the above terms in the embodiments of the present invention can be understood by those of ordinary skill in the art according to specific situations.
The embodiment of the invention provides a nuclear grade pipeline leakage rate measurement experimental device with adjustable COD, and please refer to figures 1 to 7 in the attached drawings of the specification together.
As shown in fig. 1, the experimental apparatus for measuring the leakage rate of the nuclear-grade pipeline with adjustable COD provided by the embodiment of the present invention includes a support rack 100, a conveying mechanism 200, a crack testing mechanism 300, a load applying mechanism 400, and a crack measuring mechanism 500.
The crack testing mechanism 300 is shown in fig. 3, and specifically includes a crack ring 310, an inlet pipe section 320, an outlet pipe section 330, and a sealing head 340; the two ends of the crack ring plate 310 are respectively connected with one end of the inlet pipe section 320 and one end of the outlet pipe section 330; the end part of the inlet pipe section 320 far away from the crack ring piece 310 and the end part of the outlet pipe section 330 far away from the crack ring piece 310 are both provided with sealing heads 340; the inlet pipe section 320 and the outlet pipe section 330 are both supported on the support stand 100.
The outlet pipe section 330 is provided with a first discharge pipe section 350 and a second discharge pipe section 360. The first exhaust pipe section 350 is used for opening and exhausting gas in the crack testing mechanism 300 before testing, and the second exhaust pipe section 360 is used for opening and exhausting residual working medium in the crack testing mechanism 300 after testing. Specifically, a first discharge valve 351 is provided on the first discharge pipe section 350 to control the make-and-break of the first discharge pipe section 350, and a second discharge valve 361 is provided on the second discharge pipe section 360 to control the make-and-break of the second discharge pipe section 360.
The conveying mechanism 200 specifically includes a main pipeline 210 and a first mass flow meter 220 installed on the main pipeline 210, as shown in fig. 2; one end of the main pipeline 210 is communicated with the inlet pipe section 320, and the other end of the main pipeline 210 is used for being communicated with a first working medium source; the load applying mechanism 400 is connected to the inlet pipe section 320 and the outlet pipe section 330, and is capable of applying a load to the inlet pipe section 320 and the outlet pipe section 330 to change crack opening displacement on the crack ring sheet 310.
As shown in fig. 5, the crack measuring mechanism 500 is connected to the crack ring plate 310 and can measure the crack opening displacement on the crack ring plate 310.
The working medium is a medium used for a nuclear grade pipeline leakage rate measurement test, and specifically comprises supercooled water or supercritical fluid and saturated or superheated steam. The first working medium mentioned in the embodiment of the present invention may be supercooled water or supercritical fluid, and may also be saturated or superheated steam. The first mass flow meter 220 can measure the mass flow of the first working medium, and when the first working medium is supercooled water or supercritical fluid, the first mass flow meter 220 adopts a supercooled water mass flow meter; when the first working fluid is saturated or superheated steam, the first mass flow meter 220 is a steam mass flow meter.
The crack ring piece 310 and the inlet pipe section 320, and the crack ring piece 310 and the outlet pipe section 330 may be connected by argon arc welding, so that the joint between the crack ring piece 310 and the inlet pipe section 320, and the joint between the crack ring piece 310 and the outlet pipe section 330 can bear the tensile load applied by the load applying mechanism 400. Of course, the connection between the crack ring plate 310 and the inlet pipe section 320 and between the crack ring plate 310 and the outlet pipe section 330 are not limited by the argon arc welding, and bonding, friction welding, integral connection, etc. may also be adopted.
When the experimental device for measuring the leakage rate of the nuclear-grade pipeline with the adjustable COD is used, one end of a main pipeline 210 of a conveying mechanism 200 is communicated with a first working medium source, the first working medium is conveyed to an inlet pipe section 320 through the main pipeline 210, and a first mass flowmeter 220 on the main pipeline 210 can measure the flow rate of the first working medium; the end of the inlet pipe section 320 far from the crack ring piece 310 and the end of the outlet pipe section 330 far from the crack ring piece 310 are both provided with a sealing head 340. The first vent pipe section 350 is opened prior to the test to vent the gas within the crack testing mechanism 300. In the test, the crack opening displacement on the crack ring sheet 310 is changed by applying an external force to the inlet pipe section 320 and the outlet pipe section 330 by the load applying mechanism 400, and the crack opening displacement can be measured by the crack measuring mechanism 500. The first mass flow meter 220 can measure the mass flow of the first working medium, that is, the mass flow of the first working medium leaked from the crack ring piece 310 can be obtained, so that the test data of different crack opening displacements can be measured by using one crack ring piece 310, a plurality of crack 311 test pieces do not need to be manufactured, and the test cost is greatly reduced. After the test is completed, the second discharge pipe section 360 is opened, and the residual working medium in the crack test mechanism 300 is discharged.
With continued reference to fig. 2, the delivery mechanism 200 further includes a branch line 230 and a second mass flow meter 240 mounted to the branch line 230. Specifically, both ends of the branch line 230 communicate with the main line 210, and both ends of the branch line 230 are located on both sides of the first mass flow meter 220, respectively. The end of the main pipe 210 remote from the inlet pipe section 320 is configured to communicate with the second working medium source at the same time, i.e. the end of the main pipe 210 remote from the inlet pipe section 320 can communicate with the first working medium and the second working medium at the same time. For example, in the structure shown in fig. 2, a separate access pipe 290 may be disposed at an end portion of the main pipe 210 away from the inlet pipe section 320, two ends of the access pipe 290 are used to communicate with the first working medium and the second working medium respectively, and an end portion of the main pipe 210 away from the inlet pipe section 320 is communicated with a middle portion of the access pipe 290.
The second working fluid is different from the first working fluid. The first working medium is supercooled water or supercritical fluid, and the second working medium is saturated or superheated steam; or the first working medium is saturated or superheated steam, and the second working medium is supercooled water or supercritical fluid.
The second mass flow meter 240 is used to measure the mass flow of the second working fluid. When the second working medium is the supercooled water or the supercritical fluid, the second mass flow meter 240 is a supercooled water mass flow meter; when the second working fluid is saturated or superheated steam, the second mass flow meter 240 is a steam mass flow meter.
Also, delivery mechanism 200 includes a first working fluid valve 250 and a second working fluid valve 260. A first working fluid valve 250 is mounted to the main conduit 210 between the ends of the branch conduit 230. A second working fluid valve 260 is mounted to branch line 230.
When the first working medium is required to be input into the inlet pipe section 320, the first working medium valve 250 is opened, and the second working medium valve 260 is closed; when the second working medium is required to be input into the inlet pipe section 320, the second working medium valve 260 is opened, and the first working medium valve is closed. The conveying structure enables the experiment device for measuring the leakage rate of the nuclear-grade pipeline with adjustable COD provided by the embodiment of the invention to measure the leakage rate of the nuclear-grade pipeline under the condition of different working media, and realizes the switching between the two working media through the first working medium valve 250 and the second working medium valve 260.
In addition, the delivery mechanism 200 shown in fig. 2 further includes a delivery main valve 270, the delivery main valve 270 being mounted to the main pipeline 210 and adjacent to the inlet of the main pipeline 210, enabling the delivery main valve 270 to control the communication and disconnection between the main pipeline 210 and the inlet pipe section 320. The main delivery valve 270 may be an electrically operated valve, allowing a tester to remotely operate the main delivery valve 270.
Further, as shown in fig. 2, the delivery mechanism 200 further includes a filter 280, and the filter 280 is mounted to the main pipeline 210 and is adjacent to the inlet pipe section 320. The working medium in the conveying mechanism 200 enters the inlet pipe section 320 after being filtered by the filter 280, so that the crack 311 is prevented from being blocked after impurities enter the inlet pipe section 320, and the accuracy of test data is ensured.
As shown in fig. 1, the load applying mechanism 400 includes two force applying assemblies 410, and the specific structure of the force applying assemblies 410 is shown in fig. 4. Specifically, the force application assembly 410 includes a force sensor 411 and a hydraulic pull rod 412. Wherein, one end of the hydraulic pull rod 412 is connected with the force sensor 411, and the force sensor 411 is connected with the support bench 100; the inlet pipe section 320 and the outlet pipe section 330 are connected to the ends of the two hydraulic rods 412 remote from the force sensor 411.
When the load applying mechanism 400 is in operation, the hydraulic pull rod 412 is communicated with an external hydraulic pump, and the hydraulic pull rod 412 is driven to extend and retract by the hydraulic pump, so that tensile load is applied to the inlet pipe section 320 and the outlet pipe section 330, and the crack opening displacement of the crack ring piece 310 is changed. Wherein, two force sensors 411 can respectively measure the load applied by two hydraulic pull rods 412 to the inlet pipe section 320 and the outlet pipe section 330, and the tester can control the applied load by observing the load measured by the force sensors 411.
As shown in fig. 1, the upper portion of the supporting stand 100 is provided with a slide rail 130, and the slide rail 130 is located at the crack testing mechanism 300 and is parallel to the extending direction of the crack testing mechanism 300. With continued reference to the force application assembly 410 shown in fig. 4, the force application assembly 410 further includes two sliders 413, wherein the two sliders 413 are both slidably connected to the slide rail 130, and the two sliders 413 are both correspondingly connected to the two force sensors 411.
The tester adjusts the positions and relative distances of the two force application members 410 by sliding the slider 413 to control the positions of the force application members 410 applying the load on the crack testing mechanism 300.
In addition, the force application assembly 410 further comprises a coupling ring 414, the coupling ring 414 being connected to the end of the hydraulic pull rod 412 remote from the force sensor 411; two coupling rings 414 are fitted around the inlet pipe section 320 and the outlet pipe section 330, respectively. The coupling ring 414 is capable of transferring the load applied by the hydraulic tie rod 412 to the inlet pipe section 320 and the outlet pipe section 330 and evenly circumferentially stressing the inlet pipe section 320 and the outlet pipe section 330.
When the slider 413 is slid to change the position of the force application assembly 410 applying a load on the crack testing mechanism 300, the coupling ring 414 is simultaneously slid so that the force application direction of the hydraulic pull rod 412 is along the radial direction of the inlet pipe section 320 and the outlet pipe section 330.
The crack testing mechanism 300 further comprises two extension pipe sections 370, the two extension pipe sections 370 are connected to the end of the inlet pipe section 320 away from the crack ring sheet 310 and the end of the outlet pipe section 330 away from the crack ring sheet 310, respectively, and both extension pipe sections 370 are supported on the support stand 100. The extension tube segment 370 increases the length of the crack testing mechanism 300 and facilitates the installation of the crack testing mechanism 300 on the support stand 100.
A specific structure of the support stand 100 is shown in fig. 1. The support stand 100 includes a stand 110 and a fixing ring 120. Two stands 110 are provided at intervals, and the top of the stand 110 is provided with a mounting groove to be fitted with the extension pipe section 370. That is, the inner wall of the mounting groove is a curved surface, and when the extension pipe section 370 is located in the mounting groove, the outer sidewall of the extension pipe section 370 is attached to the inner wall of the mounting groove.
Two fixing rings 120 are respectively coupled to the top of the stand 110 and fix the extension pipe sections 370 in the mounting grooves. The fixing ring 120 and the top of the rack 110 may be connected by bolts and nuts, and specifically, through holes are provided on both the top of the rack 110 and the fixing ring 120, and the bolts are screwed by the nuts after passing through the through holes on the top of the rack 110 and the fixing ring 120.
The crack measuring mechanism 500 is specifically configured as shown in fig. 5, and the crack measuring mechanism 500 includes a clip-type extensometer 510 and two fixing pins 520. One ends of the two fixing pins 520 are respectively connected to the two measuring ends of the clip-type extensometer 510, and the other ends of the two fixing pins 520 are both connected to the crack ring sheet 310 and are respectively located at both sides of the crack 311.
The crack measuring mechanism 500 is connected to a computer, converts the displacement numbers of the two measuring ends into electrical signals, converts the electrical signals into A/D signals, and inputs the signals into the computer. The specific measurement method of the crack measurement mechanism 500 is as follows: first, the clip-on extensometer 510 is calibrated to obtain the linear relationship between the displacement variation and the signal of the clip-on extensometer 510. Then, a load is applied under the condition that working media are not conveyed, the size of crack opening displacement under the corresponding load is obtained by using an image measuring method, meanwhile, the corresponding displacement change is obtained by using the clamp-type extensometer 510 for measurement, and the functional relation between the measured displacement of the clamp-type extensometer 510 and the actual crack opening displacement is obtained through calibration. During the test, the crack opening displacement under different load and water pressure (internal pressure) conditions was obtained by measuring with the clip-on extensometer 510 and converting the obtained functional relationship.
As shown in fig. 6, the experimental apparatus for measuring the leakage rate of the nuclear-grade pipeline with adjustable COD provided by the embodiment of the present invention further includes a cooling jacket 600 and a collecting water tank 700. The cooling jacket 600 is mounted to the support stand 100 and surrounds the crack ring plate 310. The lower opening of the cooling jacket 600 is opened so that the working medium leaked from the crack ring plate 310 flows out of the lower opening of the cooling jacket 600. The collecting water tank 700 is arranged below the crack testing mechanism 300 and is used for receiving the working medium which leaks from the crack ring plate 310 and flows down through the cooling jacket 600.
When the working medium conveyed to the inlet pipe section 320 by the conveying mechanism 200 is saturated or superheated steam, the saturated or superheated steam leaks from the cracks 311 of the crack ring piece 310, and the leaked saturated or superheated steam is liquefied into water after contacting with the cooling jacket 600 and flows down from the lower opening of the cooling jacket 600.
Specifically, a drain valve 710 is installed at a lower portion of the collection water tank 700, and the drain valve 710 is opened to drain the water in the collection water tank 700 before the water in the collection water tank 700 overflows.
As shown in fig. 7, a measuring window 610 is formed on the cooling jacket 600, the clip-type extensometer 510 is installed on the outer side of the cooling jacket 600, and two fixing pins 520 extend from the measuring window 610 and are connected with the crack ring plate 310. Of course, in the case that the experiment apparatus for measuring the leakage rate of the nuclear grade pipeline with adjustable COD does not have the cooling jacket 600, the crack measuring mechanism 500 may be installed on the support rack 100.
The embodiment of the invention also provides a nuclear grade pipeline leakage rate measuring method using the experimental device for measuring the nuclear grade pipeline leakage rate with adjustable COD, which comprises the following steps.
The delivery mechanism 200 is controlled to deliver the first fluid to the inlet pipe section 320 while the mass flow of the first fluid is measured using the first mass flow meter 220.
The load applying mechanism 400 is operated to apply a load to the inlet pipe section 320 and the outlet pipe section 330 to cause crack opening displacement on the crack ring piece 310 to reach a preset value.
The embodiments in the present specification are described in a progressive manner, and the same or similar parts among the embodiments may be referred to each other, and each embodiment focuses on the differences from the other embodiments.
The above embodiments are only used to illustrate the technical solutions of the present application, and not to limit the present application; although the present application has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some or all of the technical features may be equivalently replaced; such modifications or substitutions do not depart from the spirit and scope of the present disclosure.
Claims (10)
1. A nuclear grade pipeline leakage rate measurement experimental device with adjustable COD is characterized by comprising a supporting rack (100), a conveying mechanism (200), a crack testing mechanism (300), a load applying mechanism (400) and a crack measuring mechanism (500);
the crack testing mechanism (300) comprises a crack ring sheet (310), an inlet pipe section (320), an outlet pipe section (330) and a sealing head (340); the two ends of the crack ring piece (310) are respectively connected with one end of the inlet pipe section (320) and one end of the outlet pipe section (330); the end part of the inlet pipe section (320) far away from the crack ring piece (310) and the end part of the outlet pipe section (330) far away from the crack ring piece (310) are both provided with the seal heads (340); the inlet pipe section (320) and the outlet pipe section (330) are supported on the support bench (100);
the outlet pipe section (330) is provided with a first discharge pipe section (350) and a second discharge pipe section (360); the first discharge pipe section (350) is used for opening and discharging gas in the crack testing mechanism (300) before testing, and the second discharge pipe section (360) is used for opening and discharging residual working medium in the crack testing mechanism (300) after testing;
the conveying mechanism (200) comprises a main pipeline (210) and a first mass flow meter (220) mounted on the main pipeline (210); one end of the main pipeline (210) is communicated with the inlet pipe section (320), and the other end of the main pipeline (210) is used for being communicated with a first working medium source;
the load applying mechanism (400) is connected to the inlet pipe section (320) and the outlet pipe section (330) and can apply load to the inlet pipe section (320) and the outlet pipe section (330) to change crack opening displacement on the crack ring sheet (310);
the crack measuring mechanism (500) is connected with the crack ring piece (310) and can measure the crack opening displacement on the crack ring piece (310).
2. The experimental apparatus for measuring the leakage rate of the nuclear-grade pipeline with the adjustable COD according to claim 1, wherein the conveying mechanism (200) further comprises a branch pipeline (230), a second mass flow meter (240) installed on the branch pipeline (230), a first working medium valve (250) and a second working medium valve (260);
both ends of the branch pipeline (230) are communicated with the main pipeline (210), and both ends of the branch pipeline (230) are respectively positioned at both sides of the first mass flow meter (220); one end of the main pipeline (210) far away from the inlet pipe section (320) is used for being simultaneously communicated with a second working medium source;
the first working medium valve (250) is arranged on the main pipeline (210) and is positioned between two ends of the branch pipeline (230); the second working fluid valve (260) is mounted to the branch line (230).
3. The experimental apparatus for measuring the leakage rate of the nuclear-grade pipeline with adjustable COD according to claim 1 or 2, characterized in that the conveying mechanism (200) further comprises a main conveying valve (270), and the main conveying valve (270) is installed on the main pipeline (210) and is close to the inlet of the main pipeline (210).
4. The COD adjustable nuclear grade pipeline leakage rate measurement experiment device according to claim 1, wherein the load applying mechanism (400) comprises two force applying assemblies (410), the force applying assemblies (410) comprise a force sensor (411) and a hydraulic pull rod (412); one end of the hydraulic pull rod (412) is connected with the force sensor (411), and the force sensor (411) is connected with the supporting rack (100);
the inlet pipe section (320) and the outlet pipe section (330) are respectively connected with the ends of the two hydraulic pull rods (412) far away from the force sensor (411).
5. The experimental device for measuring the leakage rate of the nuclear grade pipeline with the adjustable COD according to the claim 4, is characterized in that the upper part of the supporting bench (100) is provided with a slide rail (130), and the slide rail (130) is positioned above the crack testing mechanism (300) and is parallel to the extending direction of the crack testing mechanism (300);
the force application assembly (410) further comprises sliders (413), the two sliders (413) are connected to the sliding rail (130) in a sliding mode, and the two sliders (413) are connected with the two force sensors (411) correspondingly.
6. The experimental apparatus for measuring the leakage rate of the nuclear-grade pipeline with adjustable COD according to claim 1, wherein the crack testing mechanism (300) further comprises two extension pipe sections (370), the two extension pipe sections (370) are respectively connected to the end of the inlet pipe section (320) far away from the crack ring sheet (310) and the end of the outlet pipe section (330) far away from the crack ring sheet (310), and both extension pipe sections (370) are supported on the supporting rack (100).
7. The experimental apparatus for measuring the leakage rate of the nuclear grade pipeline with adjustable COD according to claim 6, characterized in that the supporting rack (100) comprises a rack (110) and a fixed ring (120);
the two racks (110) are arranged at intervals, and the top of each rack (110) is provided with a mounting groove matched with the extension pipe section (370);
the two fixing rings (120) are respectively connected with the top of the rack (110) and fix the extension pipe section (370) in the mounting groove.
8. The experimental apparatus for measuring the leakage rate of the nuclear grade pipeline with adjustable COD according to claim 1, characterized in that the crack measuring mechanism (500) comprises a clamp-type extensometer (510) and two fixed pins (520);
one end of each of the two fixing pins is connected to the two measuring ends of the clip-type extensometer (510), and the other end of each of the two fixing pins is connected to the crack ring piece (310) and located on two sides of the crack (311).
9. The experimental apparatus for measuring the leakage rate of the nuclear grade pipeline with adjustable COD according to the claim 1, is characterized by further comprising a cooling jacket (600) and a collection water tank (700);
the cooling jacket (600) is mounted to the support stand (100) and surrounds the crack ring plate (310); the lower part of the cooling jacket (600) is opened, so that the working medium leaked from the crack ring plate (310) flows out of the lower opening of the cooling jacket (600);
the collecting water tank (700) is arranged below the crack testing mechanism (300) and is used for receiving the working medium which is leaked from the crack ring piece (310) and flows down through the cooling jacket (600).
10. A nuclear grade pipeline leakage rate measuring method using the COD adjustable nuclear grade pipeline leakage rate measuring experiment device according to any one of claims 1 to 9, comprising:
controlling the conveying mechanism (200) to convey a first working medium to the inlet pipe section (320), and simultaneously measuring the mass flow of the first working medium by using the first mass flowmeter (220);
operating the load applying mechanism (400) to apply a load to the inlet pipe section (320) and the outlet pipe section (330) so as to enable the crack opening displacement on the crack ring piece (310) to reach a preset value.
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| CN202110503304.XA CN113358298B (en) | 2021-05-10 | 2021-05-10 | Nuclear grade pipeline leakage rate measurement experiment device and method with adjustable COD |
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| CN202110503304.XA CN113358298B (en) | 2021-05-10 | 2021-05-10 | Nuclear grade pipeline leakage rate measurement experiment device and method with adjustable COD |
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| CN103175658A (en) * | 2013-03-05 | 2013-06-26 | 中国核电工程有限公司 | Method and system for testing nuclear power station pipeline leakage rate |
| GB201615815D0 (en) * | 2016-09-16 | 2016-11-02 | Univ Of Cape Town And Stellenbosch Univ | Pipe condition assessment device and system |
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| CN103175658A (en) * | 2013-03-05 | 2013-06-26 | 中国核电工程有限公司 | Method and system for testing nuclear power station pipeline leakage rate |
| GB201615815D0 (en) * | 2016-09-16 | 2016-11-02 | Univ Of Cape Town And Stellenbosch Univ | Pipe condition assessment device and system |
| CN207609997U (en) * | 2017-12-18 | 2018-07-13 | 重庆科技学院 | Oil-gas pipeline blocks and leakage working-condition monitoring system |
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