CN111128416A - Visual thermal hydraulic experiment device and method for dead pipe section of nuclear power station - Google Patents
Visual thermal hydraulic experiment device and method for dead pipe section of nuclear power station Download PDFInfo
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- CN111128416A CN111128416A CN201911409387.5A CN201911409387A CN111128416A CN 111128416 A CN111128416 A CN 111128416A CN 201911409387 A CN201911409387 A CN 201911409387A CN 111128416 A CN111128416 A CN 111128416A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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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
The invention discloses a visual thermal hydraulic experiment device and method in a dead pipe section of a nuclear power station, wherein the device comprises a visual test section, two ends of the visual test section are sealed by a valve clack simulator and a seal head to simulate a dead pipe section pipeline; a heating system is formed by a heating rod and a silicon controlled rectifier, and the heating rod is embedded into the valve clack simulator; a stop valve, a safety valve and a differential pressure sensor are arranged on the visual experiment section, the flow of fluid in the visual experiment section is controlled to flow in and out through a first stop valve, and a thermocouple is arranged on the visual experiment section; the CCD camera is positioned on the side of the visual experiment section, a PIV system is formed by the CCD camera and a laser sheet source at the tail end of the experiment device, pulse laser sheet light is provided by the laser sheet source, and an exposure particle image is shot by the CCD camera to form a PIV experiment image; the invention also provides an experimental method of the experimental device, which can meet the requirements of the research on thermal hydraulic phenomena such as the growth and separation of the flow field and the vapor bubble in the dead pipeline.
Description
Technical Field
The invention relates to the technical field of nuclear power safety measurement, in particular to an experimental device and method for researching visualization of a dead pipeline phenomenon of a nuclear power plant.
Background
The boundary of a pressurized water reactor primary circuit is isolated radioactivity, two isolating valves are arranged in the process, and a dead pipe section is a pipe section between the two check valves. When the safety barrier is in normal operation, the isolation valve is in a closed state, fluid in the isolation pipe is in a closed state, the high-temperature fluid in the primary circuit can heat the static fluid with lower temperature in the isolation pipe through forced convection and heat conduction, a series of thermotechnical hydraulic phenomena can occur, valve clack corrosion is caused, the valve tightness and the service life can be seriously influenced, the phenomenon is called as a dead pipe section thermotechnical hydraulic phenomenon, and the phenomenon directly threatens a second safety barrier of a nuclear power plant. Therefore, the research in the dead pipe section is developed, the generation mechanism of the hydraulic characteristics of heat in the limited space is revealed, a theoretical basis is provided for the safety improvement of the nuclear power plant, and the method has important industrial background and academic value.
At present, relevant research has been carried out at home and abroad, but no feasible experimental method is available for visually researching the thermal hydraulic phenomenon in a dead pipe section.
For example, chinese patent application No. CN201710414733.3 discloses a test system for studying the dead pipe phenomenon in a nuclear power plant. The device comprises a dead pipe section and a first mechanism for simulating and improving the internal temperature of the dead pipe section; the dead pipe section is a totally enclosed metal pipeline and is provided with a liquid inlet and a liquid outlet; the first mechanism comprises a convection tube, a heater, a remote transmission resistance thermometer, a magnetic turning plate liquid level meter and a first remote transmission differential pressure transmitter; the convection pipe is a totally enclosed metal pipeline, forms a first loop communicated with the dead pipe section through two pipelines, and is provided with an exhaust port; the heater is connected with the dead pipe section to heat the liquid; the plurality of remote-transmission thermal resistance thermometers are respectively arranged on the dead pipe section and the convection pipe; the number of the magnetic turning plate liquid level meters is two, one is arranged on the dead pipe section, and the other is arranged on the convection pipe; the first remote differential pressure transmitter is arranged on the dead pipe section and is connected with the dead pipe section in series to form a second loop. By implementing the invention, the phenomenon of dead pipe sections can be researched and discussed by adopting a technical means of experimental simulation, and the design is reasonable and reliable. However, the test system adopts a totally enclosed metal pipeline, the thermal hydraulic phenomenon in the pipeline cannot be directly observed, the temperature and the pressure difference in the system can only be measured, and the important thermal hydraulic phenomena such as the flow field, the bubble movement and the like in the dead pipeline are difficult to observe and analyze.
For example, chinese patent application No. CN201720553863.0 discloses a heating device for simulating a dead pipe phenomenon in a nuclear power plant. The heating device comprises a simulation dead pipe section, a heating body, a heating coil and a plug bush, wherein the simulation dead pipe section is of a through hollow structure, the cross section of the heating body is circular, the right end of the heating body is hermetically inserted into the simulation dead pipe section, the end surface of the right end of the heating body is of an inclined check valve clack structure, the plug bush is of a hollow structure, the plug bush is vertically and hermetically inserted into the simulation dead pipe section and inserted into the right end of the heating body, a probe of a thermal resistance thermometer is hermetically inserted into the plug bush to collect the temperature of the heating body, the heating coil is arranged around the outside of the heating body and is electrically connected with an external alternating current power supply, and the heating body generates induced current by virtue of an alternating magnetic field generated; the patent is the same as the patent, can not directly observe the thermotechnical hydraulic phenomenon in the pipeline, is difficult to observe and analyze important thermotechnical hydraulic phenomena such as flow field, vapor bubble movement and the like in the dead pipeline, has a complex structure and is difficult to manufacture.
Disclosure of Invention
In order to solve the defects in the prior art, the invention provides a device capable of performing a visual experiment on the dead pipe phenomenon, which can meet the requirements on the research on the thermal hydraulic phenomena such as the growth and separation of a flow field and a vapor bubble in the dead pipe, and also provides a corresponding experimental method.
In order to achieve the purpose, the invention adopts the following technical scheme:
a visual thermal hydraulic experiment device in a nuclear power station dead pipe section comprises a visual test section 11, wherein two ends of the visual test section 11 are sealed through a valve clack simulator 2, a seal head 8 and a flange 15 to simulate a dead pipe section pipeline; the heating system is composed of a heating rod 1 and a silicon controlled power regulator 9, the heating rod 1 is embedded into a valve clack simulator 2, and the power of a power supply is controlled through the silicon controlled power regulator 9, so that the heating power of the heating rod 1 is controlled, and the magnitude of experimental heat flow is changed; the visualization experiment section 11 is provided with a first stop valve 5, a second stop valve 14, a safety valve 7 and a differential pressure sensor 6, the first stop valve 5 and the second stop valve 14 are used for controlling the inflow and outflow of fluid in the visualization experiment section 11, and meanwhile, a thermocouple 12 is arranged on the visualization experiment section 11; the CCD camera 13 is positioned at the side of the visual experiment section 11, and forms a PIV system with a sheet laser source 16 at the tail end of the experiment device, pulse laser sheet light is provided through the sheet laser source 16, and an exposure particle image is shot through the CCD camera 13 to form a PIV experiment image.
The visual test section 11 is made of quartz glass, and when the pressure in the visual test section is too high, the safety valve 7 is used for regulating and controlling the pressure, so that the pressure is controlled within 2 MPa.
The valve clack simulator 2 is made of stainless steel, the end face connected with the visual test section 11 is inclined, the structure of the valve clack simulator is consistent with that of a check valve on site in a nuclear power plant, the RCP check valve with a dead pipe section is further accurately simulated and is in a closed state normally, and fluid in the visual test section 11 is isolated; and meanwhile, a preset gap is reserved between the visual experiment section pipe wall 11 and the visual experiment section pipe wall, so that overheating is avoided.
The valve clack simulator 2 is connected with the visual experimental device 11 through a stainless steel flange 3, a high-temperature-resistant gasket 10 and a water-cooling flange 4 by bolts; the water-cooling flange 4 is made of quartz glass and is manufactured by adopting a 3D printing technology, because high temperature is in contact with the valve clack simulator 2, a water-cooling measure is adopted for cooling, the water-cooling flange 4 comprises an inlet 4-1, a spiral channel 4-2 and an outlet 4-3, cold water enters the water-cooling flange from the inlet 4-1, the water-cooling flange is cooled through the spiral channel 4-2, and then the cold water flows out of the water-cooling flange from the outlet 4-3 below.
Measuring the experiment temperature by adopting a thermocouple, selecting five measuring sections on the visual experiment section 11, distributing three thermocouple measuring points on the inner side of the pipe wall corresponding to each measuring section, wherein the first measuring point is positioned at the highest point of the inner side of the pipe wall, the second measuring point is positioned at the rightmost point, the third measuring point is positioned at the lowest point, and measuring the temperature of different sections of the experiment section; the pressure in the experimental section can be measured by means of a differential pressure sensor 6 connected to the visual experimental section 11.
Before the experimental device is started, a first stop valve 5 is opened, a second stop valve 14 is closed tightly, water is introduced into a visual experimental section 11, when a target liquid level is reached, tracer particles are added into the visual experimental section 11, the first stop valve is closed, and then the liquid level in the pipe section is adjusted through the second stop valve 14; starting the experimental device, and checking whether the chip laser source 16 and the CCD camera 12 are normal; starting the silicon controlled power regulator 9, setting power, heating the heating rod 1, and starting the temperature rise of the valve clack simulator 2; in the process, the behavior of local bubbles in the visual test section 11, namely a dead pipe section, and the change of temperature and pressure are measured; when the pressure reaches the set pressure of the test, the safety valve 7 is automatically opened, the heating power supply is cut off, the sheet laser source 16 and the CCD camera 12 are sequentially closed, and after the test section is cooled, liquid in the test section is discharged through the second stop valve 14.
Compared with the prior art, the invention has the following advantages:
1) the invention utilizes quartz glass to manufacture an experimental section, adopts PIV technology, realizes visual research, and has important significance for researching the thermophysical hydraulic phenomena such as flow field, bubble movement and the like in a dead pipe section.
2) The water-cooling flange is manufactured by adopting a 3D printing technology, so that the overheating phenomenon is avoided, and the thermal hydraulic phenomenon of a dead pipe section is further accurately simulated.
3) The invention has simple structure and strong operability.
Drawings
FIG. 1 is a schematic view of the structure of the apparatus of the present invention.
Fig. 2 shows a water-cooled flange structure.
Fig. 3 shows the arrangement of thermocouples in the visual experiment segment.
Detailed Description
The invention is described in detail below with reference to the attached drawing figures:
as shown in fig. 1, the visual thermal hydraulic experimental device in the dead pipe section of the nuclear power station comprises a visual test section 11, wherein two ends of the visual test section 11 are sealed by a valve clack simulator 2, a seal head 8 and a flange 15 to simulate a dead pipe section pipeline; the heating system is composed of a heating rod 1 and a silicon controlled power regulator 9, the heating rod 1 is embedded into a valve clack simulator 2, and the power of a power supply is controlled through the silicon controlled power regulator 9, so that the heating power of the heating rod 1 is controlled, and the magnitude of experimental heat flow is changed; the visualization experiment section 11 is provided with a first stop valve 5, a second stop valve 14, a safety valve 7 and a differential pressure sensor 6, the first stop valve 5 and the second stop valve 14 are used for controlling the inflow and outflow of fluid in the visualization experiment section 11, and a thermocouple 12 is arranged on the visualization experiment section 11; the CCD camera 13 is positioned at the side of the visual experiment section 11, and forms a PIV system with a sheet laser source 16 at the tail end of the experiment device, pulse laser sheet light is provided through the sheet laser source 16, and an exposure particle image is shot through the CCD camera 13 to form a PIV experiment image.
In a preferred embodiment of the present invention, the visual testing section 11 is made of quartz glass, and when the pressure in the visual testing section is too high, the pressure is controlled to be within 2MPa by regulating the pressure through the safety valve 7.
As a preferred embodiment of the invention, the valve flap simulator 2 is made of stainless steel, and the end surface connected with the visual test section 11 is inclined, so that the structure of the valve flap simulator is consistent with that of a check valve on a nuclear power plant site, and the RCP check valve with a dead pipe section is further accurately simulated and is in a closed state normally, and fluid in the visual test section 11 is isolated; and meanwhile, a preset gap is reserved between the visual experiment section pipe wall 11 and the visual experiment section pipe wall, so that overheating is avoided.
As a preferred embodiment of the invention, the valve flap simulator 2 is connected with the visual experimental device 11 through a stainless steel flange 3, a high temperature resistant gasket 10 and a water-cooling flange 4 by bolts; the water-cooling flange 4 is made of quartz glass and is manufactured by adopting a 3D printing technology, because high temperature is in contact with the valve clack simulator 2, the water-cooling measure is adopted for cooling, as shown in figure 2, the water-cooling flange 4 comprises an inlet 4-1, a spiral channel 4-2 and an outlet 4-3, cold water enters the water-cooling flange from the inlet 4-1, the water-cooling flange is cooled through the spiral channel 4-2, and then the cold water flows out of the water-cooling flange from the outlet 4-3 below.
The thermocouple is adopted to measure the experiment temperature, five measurement sections are selected on the visual experiment section 11, three thermocouple measurement points are distributed on the inner side of the pipe wall corresponding to each measurement section, the first measurement point is located at the highest point of the inner side of the pipe wall, the second measurement point is located at the rightmost point, the third measurement point is located at the lowest point, the temperatures of different sections of the experiment section are measured, and the temperature distribution condition of the same hydraulic section is fully measured. The pressure in the experimental section can be measured by means of a differential pressure sensor 6 connected to the visual experimental section 11.
Before the experimental device is started, a first stop valve 5 is opened, a second stop valve 14 is closed tightly, water is introduced into a visual experimental section 11, when a target liquid level is reached, tracer particles are added into the visual experimental section 11, the first stop valve is closed, and then the liquid level in the pipe section is adjusted through the second stop valve 14; starting the experimental device, and checking whether the chip laser source 16 and the CCD camera 12 are normal; starting the silicon controlled power regulator 9, setting power, heating the heating rod 1, and starting the temperature rise of the valve clack simulator 2; in the process, the behavior of local bubbles in the visual test section 11, namely a dead pipe section, and the change of temperature and pressure are measured; when the pressure reaches the set pressure of the test, the safety valve 7 is automatically opened, the heating power supply is cut off, the sheet laser source 16 and the CCD camera 12 are sequentially closed, and after the test section is cooled, liquid in the test section is discharged through the second stop valve 14.
While the invention has been described in further detail with reference to specific preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (6)
1. A visual thermal hydraulic experimental device in a nuclear power station dead pipe section is characterized in that: the device comprises a visual test section (11), wherein two ends of the visual test section (11) are sealed by a valve clack simulator (2), a seal head (8) and a flange (15) to simulate a dead pipe section pipeline; the heating system is composed of a heating rod (1) and a silicon controlled power regulator (9), the heating rod (1) is embedded into the valve clack simulator (2), and the power of a power supply is controlled through the silicon controlled power regulator (9), so that the heating power of the heating rod (1) is controlled, and the magnitude of experimental heat flow is changed; a first stop valve (5), a second stop valve (14), a safety valve (7) and a differential pressure sensor (6) are arranged on the visual experiment section (11), the flow of fluid in the visual experiment section (11) is controlled to flow in and out through the first stop valve (5) and the second stop valve (14), and a thermocouple (12) is arranged on the visual experiment section (11); the CCD camera (13) is positioned at the side of the visual experiment section (11), and forms a PIV system with a sheet laser source (16) at the tail end of the experiment device, pulse laser sheet light is provided through the sheet laser source (16), and an exposure particle image is shot through the CCD camera (13) to form a PIV experiment image.
2. The visualized thermal hydraulic experimental device in the dead pipe section of the nuclear power plant as claimed in claim 1, is characterized in that: the visual test section (11) is made of quartz glass, and when the pressure in the visual test section is too high, the safety valve (7) is used for regulating and controlling the pressure, so that the pressure is controlled within 2 MPa.
3. The visualized thermal hydraulic experimental device in the dead pipe section of the nuclear power plant as claimed in claim 1, is characterized in that: the valve flap simulator (2) is made of stainless steel, and the end face connected with the visual test section (11) is inclined, so that the structure of the valve flap simulator is consistent with that of a check valve on a nuclear power plant site, an RCP (remote control valve) check valve with a dead pipe section is further accurately simulated, the valve flap simulator is normally in a closed state, and fluid in the visual test section (11) is isolated; meanwhile, a preset gap is reserved between the visual experiment section pipe wall (11) and the visual experiment section pipe wall, so that overheating is avoided.
4. The visualized thermal hydraulic experimental device in the dead pipe section of the nuclear power plant as claimed in claim 1, is characterized in that: the valve clack simulator (2) is connected with the visual experimental device (11) through a stainless steel flange (3), a high-temperature-resistant gasket (10) and a water-cooling flange (4) by bolts; the water-cooling flange (4) is made of quartz glass and is manufactured by adopting a 3D printing technology, because high temperature is in contact with the valve clack simulator (2), a water-cooling measure is adopted for cooling, the water-cooling flange (4) comprises an inlet (4-1), a spiral channel (4-2) and an outlet (4-3), cold water enters the water-cooling flange from the inlet (4-1), the water-cooling flange is cooled through the spiral channel (4-2), and then the cold water flows out of the water-cooling flange from the outlet (4-3) below.
5. The visualized thermal hydraulic experimental device in the dead pipe section of the nuclear power plant as claimed in claim 1, is characterized in that: measuring the experiment temperature by adopting a thermocouple, selecting five measuring sections on a visual experiment section (11), distributing three thermocouple measuring points on the inner side of the pipe wall corresponding to each measuring section, wherein the first measuring point is positioned at the highest point of the inner side of the pipe wall, the second measuring point is positioned at the rightmost point, the third measuring point is positioned at the lowest point, and measuring the temperature of different sections of the experiment section; the pressure in the experimental section can be measured by a differential pressure sensor (6) connected to the visual experimental section (11).
6. The experimental method of the visual thermal hydraulic experimental device in the dead pipe section of the nuclear power plant as claimed in any one of claims 1 to 5, characterized in that: before the experimental device is started, a first stop valve (5) is opened, a second stop valve (14) is closed, water is introduced into a visual experimental section (11), when a target liquid level is reached, tracer particles are added into the visual experimental section (11), the first stop valve is closed, and then the liquid level in a pipe section is adjusted through the second stop valve (14);
starting an experimental device, and checking whether a chip laser source (16) and a CCD camera (12) are normal;
starting the silicon controlled power regulator (9), setting power, heating the heating rod (1), and starting the temperature rise of the valve clack simulator (2); in the process, the behavior of local bubbles in a visual test section (11), namely a dead pipe section, and the change of temperature and pressure are measured; after the experiment set pressure is reached, the safety valve (7) is automatically opened, the heating power supply is cut off, the sheet laser source (16) and the CCD camera (12) are sequentially closed, and after the experiment section is cooled, liquid in the experiment section is discharged through the second stop valve (14).
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| Application Number | Priority Date | Filing Date | Title |
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| CN201911409387.5A CN111128416A (en) | 2019-12-31 | 2019-12-31 | Visual thermal hydraulic experiment device and method for dead pipe section of nuclear power station |
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| CN201911409387.5A CN111128416A (en) | 2019-12-31 | 2019-12-31 | Visual thermal hydraulic experiment device and method for dead pipe section of nuclear power station |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112881386A (en) * | 2021-01-11 | 2021-06-01 | 西安交通大学 | Narrow slit channel visualization experiment device and method under six-degree-of-freedom motion condition |
| CN116864172A (en) * | 2023-09-04 | 2023-10-10 | 哈尔滨工程大学 | Experiment method for hydraulic characteristics of solution Chi Regong under irradiation-like environment |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112881386A (en) * | 2021-01-11 | 2021-06-01 | 西安交通大学 | Narrow slit channel visualization experiment device and method under six-degree-of-freedom motion condition |
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| CN116864172A (en) * | 2023-09-04 | 2023-10-10 | 哈尔滨工程大学 | Experiment method for hydraulic characteristics of solution Chi Regong under irradiation-like environment |
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