CN109973826B - Experimental device and method for measuring leakage rate of nuclear reactor pipeline - Google Patents
Experimental device and method for measuring leakage rate of nuclear reactor pipeline Download PDFInfo
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- CN109973826B CN109973826B CN201910345148.1A CN201910345148A CN109973826B CN 109973826 B CN109973826 B CN 109973826B CN 201910345148 A CN201910345148 A CN 201910345148A CN 109973826 B CN109973826 B CN 109973826B
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F17—STORING OR DISTRIBUTING GASES OR LIQUIDS
- F17D—PIPE-LINE SYSTEMS; PIPE-LINES
- F17D5/00—Protection or supervision of installations
- F17D5/02—Preventing, monitoring, or locating loss
Abstract
A nuclear reactor pipeline leakage rate measurement experimental device and a method thereof are based on the micro-break liquid diffusion principle, and the device comprises a water inlet pipe, a valve, a flowmeter, a pressure gauge, a separation plate, a measuring chamber, a flange, a crack simulation sheet, a fixed head, a drainage plate, a collecting device and a weighing instrument; wherein, the water inlet pipe is controlled by a valve; the flowmeter is connected with the water inlet pipe and is used for measuring the flow; the pressure gauge is connected with the water inlet pipe and is used for measuring pressure; the flange on the rightmost side of the water inlet pipe is connected with the crack simulation sheet and the fixing head through bolts to simulate cracks; a drainage plate is arranged below the measuring chamber and is used for guiding leaked water into a collecting device below the drainage plate; the lower part of the collecting device is connected with a weighing instrument; the device can simulate cracks with different sizes by replacing the crack simulation sheet, and the invention also provides an experimental method of the measurement experimental device; the leakage rate of the cracks with different sizes can be measured, and the whole pipeline does not need to be replaced to simulate the cracks with different sizes.
Description
Technical Field
The invention belongs to the technical field of micro-break liquid leakage, and particularly relates to an experimental device and method for measuring a leakage rate of a nuclear reactor pipeline.
Technical Field
In a nuclear power system, a high-energy pipeline of a reactor adopting a tough material forms cracks under the influence of stress load, the expansion of the cracks finally leads to the rupture and even fracture of the pipeline, and the damage of a pressure boundary causes radioactive substances to leak out so as to seriously threaten the safety of the reactor. The pre-fracture leakage technology determines the position and the size of a crack through leakage detection, and adopts human interference before the crack is unstably fractured so as to effectively avoid the accidents of fracture and double-end shear fracture. The prediction accuracy of the crack leakage rate determines the accurate prediction of the crack size and the accuracy of the leakage rate detector. Unlike conventional channels, cracks have rough channel surfaces, twisted and extremely narrow channels, and large channel length to hydraulic diameter ratios, with true cracks also potentially causing channel blockage and the like. Due to the special shapes of the cracks, the physical phenomenon in the crack leakage process is greatly different from that of a conventional channel, and the difficulty of researching the mechanism of the leakage rate before breakage is further increased. The conventional channel flow channel is smooth and regular, and existing flow mechanism (including critical flow, on-way resistance, flow pattern, phase change and the like) models are developed based on the conventional channel. The appearance of the crack is different from that of a conventional channel, the opening degree of the crack is in the range of 0.01-0.3 mm, the length of the crack is as high as dozens of times or even hundreds of times of the opening degree, an extremely flat and irregular flow channel is formed, and the flow characteristics of the channel are different from those of the conventional channel. The invention provides an experimental device and method for measuring the leakage rate of a nuclear reactor pipeline, which are designed based on the requirement.
Disclosure of Invention
In order to overcome the problems in the prior art, the invention aims to provide a nuclear reactor pipeline leakage rate measurement experimental device and a method, the device can measure the leakage rate of cracks with different sizes, and the whole pipeline is not required to be replaced to simulate the cracks with different sizes.
In order to achieve the purpose, the invention adopts the following technical scheme:
a nuclear reactor pipeline leakage rate measurement experimental device is based on a micro-break liquid diffusion principle and comprises a measuring chamber 5, a partition plate 9 covering the outside of a shell of the measuring chamber 5 and preventing water from splashing, a water inlet pipe 2 with one end penetrating through the partition plate 9 and inserted into the middle part of the measuring chamber 5, a crack simulation sheet 7 fixed on one end of the water inlet pipe 2 inserted into the measuring chamber 5 through a flange 6 and a fixing head 8 in a bolt fixing mode, and the crack simulation sheet 7 simulating cracks possibly existing in a nuclear reactor pipeline by processing a groove on a complete circular ring; a pipe section of the water inlet pipe 2, which is positioned outside the measuring chamber 5, is provided with a valve 1 for controlling water inlet, a flowmeter 3 for measuring water inlet flow and a pressure gauge 4 for measuring water inlet pressure; a flow-guiding plate 13 is arranged below the measuring chamber 5 for guiding the leaking water to a collecting device 11 below, which collecting device 11 is connected below to a weighing apparatus 12.
The surface of the drainage plate 13 is coated with a coating for preventing liquid from adhering to the surface, and the drainage plate 13 is connected with a weighing instrument 12 and used for measuring the mass of the leaked liquid.
The grooves with different shapes and sizes are processed in the radial direction of the complete ring to form the crack simulation sheet 7, the cracks with different shapes and sizes are simulated by replacing the crack simulation sheet 7, the whole pipeline does not need to be replaced, and the cost is saved.
The measuring chamber 5 is fixed on a base 10, and the isolation plate 9 is connected with the base 10 and the measuring chamber 5 through bolts.
The experimental method of the experimental device for measuring the leakage rate of the nuclear reactor pipeline comprises the steps of firstly recording the reading G of the weighing instrument 12 when measuring the leakage of the nuclear reactor pipeline1Opening the valve 1 and recording the reading W of the flowmeter 31And the indication P of the pressure gauge 41When the water in the water inlet pipe 2 flows to the crack simulation sheet 7, the water can flow out from the crevasses due to the existence of cracks, and then drops on the drainage plate 13 and finally flows into the collection device 11, and the time t and the reading G of the weighing instrument 12 are continuously recorded2. Thereby obtaining the leakage amount G of water in the pipeline under the condition of obtaining the width d of the crack2-G1And time t.
Compared with the prior art, the invention has the following advantages:
1. according to the experimental device and the method for measuring the leakage rate of the nuclear reactor pipeline, the groove is processed on the complete ring to form the crack simulation sheet, cracks with different sizes can be simulated by replacing the crack simulation sheet, the whole pipeline does not need to be replaced, and the cost can be saved.
2. According to the experimental device and the method for measuring the leakage rate of the nuclear reactor pipeline, cracks possibly existing in a nuclear reactor main pipeline can be simulated through the gap between the crack simulation sheet and the flange, and cracks in different shapes can be processed in the radial direction of the crack simulation sheet.
3. The experimental device and the method for measuring the leakage rate of the nuclear reactor pipeline adopt a weighing mode for measurement, and adopt the drainage plate with the surface coated with the coating layer for preventing the liquid from being attached on the surface, so that the leakage rate can be accurately measured.
Drawings
FIG. 1 is a schematic view of the overall structure of an experimental apparatus for measuring leakage of a nuclear reactor pipeline according to the present invention.
FIG. 2 is a partial schematic view of a simulated crack portion for nuclear reactor pipeline leak measurement according to the present invention.
Fig. 3 is a schematic structural diagram of a nuclear reactor pipeline leakage measurement crack simulator sheet according to the present invention, wherein fig. 3a is a side view and fig. 3b is a front view.
Fig. 4 is a schematic structural diagram of a nuclear reactor pipeline leakage measurement crack simulator sheet according to the present invention, wherein fig. 4a is a side view and fig. 4b is a front view.
Detailed Description
The invention is described in detail below with reference to the following figures and detailed description:
as shown in fig. 1, an experimental device for measuring the leakage rate of a nuclear reactor pipeline is based on the principle of micro-break liquid diffusion, and comprises a water inlet pipe 2 which is positioned at the left side of the whole experimental device and is used for introducing water; the water inlet pipe 2 is controlled by a valve 1; the flowmeter 3 is connected with the water inlet pipe 2 and is used for measuring pressure; the pressure gauge 4 is connected with the water inlet pipe 2 and is used for measuring pressure; the isolation plate 9 is connected with the base 10 and the measuring chamber 5 through bolts, and the isolation plate 9 is positioned in the middle and used for preventing water from splashing; the flange 6 on the rightmost side of the water inlet pipe 2 is connected with the crack simulation sheet 7 and the fixing head 8 through bolts, and the crack simulation sheet 7 is positioned in the middle; below the measuring chamber 5 there is a flow guide plate 13 for guiding the leaking water to a collecting device 11 below, which collecting device 11 is connected to a weighing apparatus 12 below.
As shown in FIG. 2, the complete ring is processed with a groove to form a crack simulation sheet 7, the left side of the crack simulation sheet 7 is connected with a flange 6, the right side of the crack simulation sheet 7 is connected with a fixed head 8, and the crack simulation sheet, the flange and the fixed head are fixed through bolts. Cracks which may be present in the nuclear reactor pipe are simulated by the gap between the crack simulator sheet 7 and the flange 6.
As shown in fig. 3 and 4, the crack simulating chip 7 can be processed into cracks of different shapes in the radial direction, wherein fig. 3a and 3b are rectangular in the radial direction in fig. 3, and fig. 4a and 4b are fan-shaped in the radial direction in fig. 4.
The foregoing is illustrative of the present invention only and is not to be construed as limiting thereof, and variations and modifications to the above-described embodiments, within the true spirit and scope of the invention, should be considered as within the scope of the claims of the present invention to those skilled in the art.
Claims (3)
1. The utility model provides a nuclear reactor pipeline leakage rate measurement experimental apparatus which characterized in that: the experimental device is based on the micro-crevasse liquid diffusion principle and comprises a measuring chamber (5), a partition plate (9) which is coated outside a shell of the measuring chamber (5) and prevents water from splashing, a water inlet pipe (2) with one end inserted into the middle part in the measuring chamber (5) through the partition plate (9), a crack simulation sheet (7) is fixed at one end of the water inlet pipe (2) inserted into the measuring chamber (5) through a flange (6) and a fixing head (8) in a bolt fixing mode, and the crack simulation sheet (7) simulates cracks possibly existing in a nuclear reactor pipeline by processing a groove on a complete circular ring; a pipe section of the water inlet pipe (2) positioned outside the measuring chamber (5) is provided with a valve (1) for controlling water inlet, a flowmeter (3) for measuring water inlet flow and a pressure gauge (4) for measuring water inlet pressure; a drainage plate (13) is arranged below the measuring chamber (5) and is used for guiding leaked water into a collecting device (11) below the drainage plate, and the lower part of the collecting device (11) is connected with a weighing instrument (12);
the surface of the drainage plate (13) is coated with a coating for preventing liquid from adhering to the surface, and the drainage plate (13) is connected with a weighing instrument (12) and used for measuring the quality of leaked water;
the grooves with different shapes and sizes are processed in the radial direction of the complete ring to form the crack simulation sheet (7), the cracks with different shapes and sizes are simulated by replacing the crack simulation sheet (7), the whole pipeline does not need to be replaced, and the cost is saved.
2. The experimental apparatus for measuring the leakage rate of the nuclear reactor pipeline according to claim 1, wherein: the device also comprises a base (10) for fixing the measuring chamber (5), and the partition plate (9) is connected with the base (10) and the measuring chamber (5) through bolts.
3. The experimental method of experimental apparatus for measuring the leak rate of a nuclear reactor pipeline according to claim 1, characterized in that: when measuring the leakage of the nuclear reactor pipe, firstly, the indication G of the weighing instrument (12) is recorded1Opening the valve (1) and recording the reading W of the flowmeter (3)1And the indication P of the pressure gauge (4)1When water in the water inlet pipe (2) flows to the crack simulation sheet (7), due to existence of cracks, the water can flow out from the crevasses, drip onto the drainage plate (13) and finally flow into the collection device (11), and the time t and the reading G of the weighing instrument (12) are continuously recorded2(ii) a Thereby obtaining the leakage amount G of water in the pipeline under the condition of obtaining the width d of the crack2-G1And time t.
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| CN109973826B true CN109973826B (en) | 2020-05-15 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| DE59608391D1 (en) * | 1995-10-16 | 2002-01-17 | Framatome Anp Gmbh | TUBE MANIPULATOR FOR TESTING OR PROCESSING THE INSIDE SURFACE OF A TUBE |
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| CN101676703A (en) * | 2008-09-18 | 2010-03-24 | 韩国电力公司 | Apparatus for detecting leakage from channel closure plug for fuel channel in heavy water reactor |
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