CN117705222A - Device and method for accurately measuring liquid level in tube for nuclear reactor T-shaped tube two-phase entrainment experiment - Google Patents
Device and method for accurately measuring liquid level in tube for nuclear reactor T-shaped tube two-phase entrainment experiment Download PDFInfo
- Publication number
- CN117705222A CN117705222A CN202311730854.0A CN202311730854A CN117705222A CN 117705222 A CN117705222 A CN 117705222A CN 202311730854 A CN202311730854 A CN 202311730854A CN 117705222 A CN117705222 A CN 117705222A
- Authority
- CN
- China
- Prior art keywords
- tube
- pipe
- phase
- horizontal main
- liquid level
- Prior art date
- 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.)
- Pending
Links
- 239000007788 liquid Substances 0.000 title claims abstract description 52
- 238000002474 experimental method Methods 0.000 title claims abstract description 22
- 238000000034 method Methods 0.000 title claims abstract description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 22
- 238000000926 separation method Methods 0.000 claims abstract description 19
- 238000005259 measurement Methods 0.000 claims abstract description 10
- 239000012071 phase Substances 0.000 claims description 35
- 239000007791 liquid phase Substances 0.000 claims description 16
- 230000008569 process Effects 0.000 claims description 13
- 229910001220 stainless steel Inorganic materials 0.000 claims description 7
- 239000010935 stainless steel Substances 0.000 claims description 7
- 230000009471 action Effects 0.000 claims description 3
- 239000012808 vapor phase Substances 0.000 claims 2
- 238000009434 installation Methods 0.000 abstract description 3
- 238000012545 processing Methods 0.000 abstract description 3
- 238000002347 injection Methods 0.000 description 3
- 239000007924 injection Substances 0.000 description 3
- 238000011160 research Methods 0.000 description 2
- 238000013022 venting Methods 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
Classifications
-
- 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 device and a method for accurately measuring liquid level in a tube for a nuclear reactor T-shaped tube two-phase entrainment experiment, wherein the device comprises a T-shaped tube structure, the T-shaped tube structure comprises a horizontal main tube and a vertical branch tube which are connected, and the vertical branch tube is positioned in the middle of the horizontal main tube; flanges are welded at the two ends of the horizontal main pipe and the outlets of the vertical branch pipes of the T-shaped pipe structure; an upper pressure measuring hole and a lower pressure measuring hole are respectively arranged at two ends of the horizontal main pipe; the two upper pressure measuring holes are respectively connected to the lower inlet of the corresponding steam-water separation device through respective upper pressure guiding pipes, and the upper outlet of each steam-water separation device is connected to the low pressure end of the corresponding differential pressure transmitter; the two lower pressure measuring holes are respectively connected to the high-pressure ends of the corresponding differential pressure transmitters through respective lower pressure guiding pipes; and acquiring readings of the two differential pressure transmitters and taking an average value to indirectly measure the accurate liquid level in the horizontal main pipe. The invention has simple structure, is convenient for processing and installation, and improves the accuracy of the liquid level measurement value in the horizontal tube in the T-shaped tube two-phase entrainment experiment.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor thermal hydraulic experimental devices, and particularly relates to an in-tube liquid level accurate measurement device suitable for a nuclear reactor T-shaped tube two-phase entrainment experiment.
Background
For the passive nuclear power plant, pressure relief is needed after a water loss accident occurs so as to meet the requirement of gravity water injection. After the automatic pressure relief valve is opened, steam is carried with a large amount of liquid drops to enter the containment through a T-shaped structure formed by the automatic pressure relief pipeline and the heat pipe, and when the flow of the automatic pressure relief system is greater than the safety injection flow, the liquid level of the reactor core is reduced; when the automatic pressure relief system flow is less than Yu An flow, the core level rises. In a short period, the discharged entrainment after the automatic pressure relief valve is opened has obvious influence on the liquid level of the reactor core after the water loss accident, and if the liquid level is lower than the height of the reactor core, the fuel rod can be oxidized and expanded, and even serious accidents of bare or molten reactor core occur; natural circulation is achieved during the long term phase by vapor venting through the automatic pressure relief valve (back flow to the pit by PCS condensation in the containment) and pit water injection, while during this process boron migration balance is achieved by droplet entrainment through vapor venting through the automatic pressure relief valve. Therefore, a nuclear reactor T-shaped pipe two-phase entrainment experiment is developed, and the research of automatic pressure relief entrainment has important significance for water loss accidents.
The liquid level in the T-shaped pipe horizontal main pipe is an important factor influencing the gas-liquid two-phase entrainment phenomenon, and the liquid level can influence the entrainment amount, namely the liquid level change rate of the reactor core, so that the accurate measurement of the liquid level in the pipe is very important for the entrainment phenomenon research.
For example, in the experimental section liquid level measurement of a T-shaped tube in the experimental study of entrainment of a T-shaped tube with double-end air inlet of the published paper, the liquid level is directly measured by adopting a differential pressure transmitter before and after an ADS-4 branch tube, but due to the existence of entrainment phenomenon, partial liquid drops are entrained into a pressure guiding tube at a low pressure end, so that measurement errors are caused, and the accurate measurement requirement of the liquid level in the horizontal tube cannot be met.
Disclosure of Invention
In order to overcome the defects of the prior art, the invention aims to provide the accurate in-tube liquid level measuring device suitable for a nuclear reactor T-shaped tube two-phase entrainment experiment, which can meet the accurate in-tube liquid level measuring requirement in the gas-liquid two-phase entrainment process, thereby providing a more reliable tool for predicting the entrainment phenomenon in the automatic pressure relief process under the water loss accident and improving the safety of the nuclear power station.
In order to achieve the above purpose, the present invention adopts the following technical scheme:
the device comprises a T-shaped pipe structure 1, wherein the T-shaped pipe structure 1 comprises a horizontal main pipe 11 and a vertical branch pipe 12 which are connected, and the vertical branch pipe 12 is positioned in the middle of the horizontal main pipe 11; flanges 2 are welded at the two ends of a horizontal main pipe 11 and the outlets of vertical branch pipes 12 of the T-shaped pipe structure 1; an upper pressure measuring hole 61 and a lower pressure measuring hole 62 are respectively formed at two ends of the horizontal main pipe; the two upper pressure measuring holes 61 are respectively connected to the lower inlet of the corresponding steam-water separation device 4 through respective upper pressure guiding pipes 51, and the upper outlet of each steam-water separation device 4 is connected to the low pressure end of the corresponding differential pressure transmitter 3; the two lower pressure measuring holes 62 are respectively connected to the high-pressure ends of the corresponding differential pressure transmitter 3 through respective lower pressure guiding pipes 52; the accurate liquid level in the horizontal main pipe 11 can be indirectly measured by collecting the readings of the two differential pressure transmitters 3 and taking the average value.
Preferably, the upper pressure measuring hole 61 and the lower pressure measuring hole 62 are bilaterally symmetrical about the symmetry axis of the stainless steel T-shaped pipe structure 1, and are positioned at equidistant positions from the flanges 2 at both ends of the horizontal main pipe 11 and the vertical branch pipe 12 in the horizontal direction.
Preferably, the material of the T-shaped pipe structure 1 and the flange 2 is stainless steel.
In the measuring method of the device for accurately measuring the liquid level in the tube for the two-phase entrainment experiment of the T-shaped tube of the nuclear reactor, before the two-phase entrainment experiment of the T-shaped tube begins, the lower pressure guiding tube 52 is filled with the liquid which is the same as the experimental working medium, and the upper pressure guiding tube 51 is filled with the gas which is the same as the experimental working medium; in the T-shaped pipe two-phase entrainment experiment process, gas phase and liquid phase working media enter the horizontal main pipe 11 from two ends of the horizontal main pipe 11; part of liquid phase working medium is entrained into the vertical branch pipe 12 under the action of gas phase lifting force, and the gas phase working medium and the entrained liquid phase working medium flow out of the T-shaped pipe structure 1 through the outlet of the vertical branch pipe 12; in the experimental process, due to the existence of the entrainment phenomenon, part of liquid drops are entrained into the upper pressure guiding pipe 51, the liquid phase is carried to the vapor-water separation device 4 by the gas phase to realize the separation of the gas phase and the liquid phase, and after the experimental process is continued for a period of time, a valve at the bottom of the vapor-water separation device 4 is opened to empty the accumulated liquid; at this time, the accurate liquid level in the horizontal main pipe 11 can be obtained by collecting the indication of the differential pressure transmitter in real time and taking the average value.
Compared with the prior art, the invention has the following advantages:
1. according to the invention, the pressure measuring hole is positioned in the experimental section body, the liquid level in the pipe is obtained by measuring the vertical pressure difference of the same horizontal position of the T-shaped pipe, a three-way structure can be added at the connecting section of the steam-water separation device and the low pressure end of the differential pressure transmitter, the branch pressure guiding pipe is led out on the basis of the original pressure guiding pipe and is connected to the pressure transmitter, and the pressure requirement of the experimental section is met, so that repeated hole opening on the experimental section can be avoided, the reliability of the experimental section is ensured, and the accuracy of measured data is improved.
2. The pressure measuring pipe at the upper part of the T-shaped pipe is connected to the low-pressure end of the differential pressure transmitter through the steam-water separation device, so that liquid which is entrained into the pressure guiding pipe due to the entrainment effect can be effectively removed, and the liquid level measuring precision in the horizontal pipe can be effectively improved.
3. The T-shaped pipe structure horizontal main pipe, the vertical branch pipe and the flange are all made of stainless steel and are welded and connected, the structure is simple, and the T-shaped pipe structure horizontal main pipe, the vertical branch pipe and the flange can bear gas-liquid two-phase entrainment experiments under high temperature and high pressure.
In a word, the invention has simple structure, is convenient for processing and installation, and can realize the accurate measurement of the liquid level in the horizontal tube in the process of the two-phase entrainment experiment of the T-shaped tube of the nuclear reactor.
Drawings
FIG. 1 is a front view of an in-tube liquid level accurate measurement device suitable for a nuclear reactor T-tube two-phase entrainment experiment according to the present invention.
Detailed Description
The invention is described in further detail below with reference to the attached drawings and specific examples:
referring to FIG. 1, the invention discloses an in-tube liquid level accurate measurement device for a nuclear reactor T-shaped tube two-phase entrainment experiment, which comprises a T-shaped tube structure 1; the T-shaped pipe structure 1 comprises a horizontal main pipe 11 and vertical branch pipes 12, wherein the vertical branch pipes 12 are positioned in the middle of the horizontal main pipe 11; flanges 2 are welded at the two ends of a horizontal main pipe 11 and the outlets of vertical branch pipes 12 of the T-shaped pipe structure 1; the flange 2 can be fastened with the corresponding flange through the mounting hole, so that the experimental section of the T-shaped pipe structure 1 is connected with the whole experimental loop pipeline.
Four pressure measuring holes are formed in the horizontal main pipe, an upper pressure measuring hole 61 and a lower pressure measuring hole 62 are formed in the upper portion and the lower portion of the two ends of the horizontal main pipe 11, the two upper pressure measuring holes 61 and the two lower pressure measuring holes 62 are respectively symmetrical left and right about the symmetry axis of the T-shaped pipe structure 1, and the positions of the pressure measuring holes corresponding to each other in the upper and lower directions are the same in the horizontal direction; the two upper pressure measuring holes 61 are respectively connected to the lower inlet of the corresponding steam-water separation device 4 through respective upper pressure guiding pipes 51, and the upper outlet of the steam-water separation device 4 is connected to the low pressure end of the corresponding differential pressure transmitter 3; the two lower pressure taps 62 are each connected to the high pressure end of the corresponding differential pressure transmitter 3 by a respective lower pressure tube 52.
As a preferred embodiment of the present invention, the upper pressure tap 61 and the lower pressure tap 62 are bilaterally symmetrical about the symmetry axis of the stainless steel T-shaped pipe structure 1 and are positioned at equidistant positions from the flanges 2 and the vertical branch pipes 12 at both ends of the horizontal main pipe 11 in the horizontal direction so as to calculate the average liquid level in the horizontal main pipe 11 from the liquid levels at both sides in the obtained horizontal pipe 11.
As the preferable implementation mode of the invention, the T-shaped pipe structure 1 and the flange 2 are made of stainless steel, so that the processing and the installation are convenient, the experimental conditions simulating the high-temperature and high-pressure environment in the nuclear reactor can be born, and the structural reliability of an experimental section is ensured.
Before the T-shaped pipe two-phase entrainment experiment starts, the lower pressure guiding pipe 52 is filled with the liquid same as the experimental working medium, and the upper pressure guiding pipe 51 is filled with the gas same as the experimental working medium; in the T-shaped pipe two-phase entrainment experiment process, gas phase and liquid phase working media can enter the horizontal main pipe 11 from two ends of the horizontal main pipe 11; part of liquid phase working medium is entrained into the vertical branch pipe 12 under the action of gas phase lifting force, and the gas phase working medium and the entrained liquid phase working medium flow out of the T-shaped pipe structure 1 through the outlet of the vertical branch pipe 12; in the experimental process, due to the existence of the entrainment phenomenon, part of liquid drops are entrained into the upper pressure guiding pipe 51, the liquid phase is carried to the vapor-water separation device 4 by the gas phase to realize the separation of the gas phase and the liquid phase, and after the experimental process is continued for a period of time, a valve at the bottom of the vapor-water separation device 4 can be opened to empty the accumulated liquid; at this time, two differential pressure transmitter readings, namely pressures P1 and P2, are acquired in real time, and accurate liquid level data h1 and h2 at two sides in the main horizontal pipe 11 can be obtained through a formula p=pgh, and the liquid level data h1 and h2 at two sides are averaged to obtain accurate liquid level data h in the main horizontal pipe 11, wherein ρ is the density of a liquid phase working medium.
While the invention has been described in connection with what is presently considered to be the most practical and preferred embodiment, it is to be understood that the invention is not limited to the disclosed embodiment, but on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the appended claims.
Claims (4)
1. An accurate measurement device of intraductal liquid level of nuclear reactor T type pipe two-phase entrainment experiment, its characterized in that: the device comprises a T-shaped pipe structure (1), wherein the T-shaped pipe structure (1) comprises a horizontal main pipe (11) and vertical branch pipes (12) which are connected, and the vertical branch pipes (12) are positioned in the middle of the horizontal main pipe (11); flanges (2) are welded at both ends of a horizontal main pipe (11) and at the outlets of vertical branch pipes (12) of the T-shaped pipe structure (1); an upper pressure measuring hole (61) and a lower pressure measuring hole (62) are respectively arranged at two ends of the horizontal main pipe; the two upper pressure measuring holes (61) are respectively connected to the lower inlets of the corresponding steam-water separation devices (4) through respective upper pressure guiding pipes (51), and the upper outlet of each steam-water separation device (4) is connected to the low pressure end of the corresponding differential pressure transmitter (3); the two lower pressure measuring holes (62) are respectively connected to the high-pressure ends of the corresponding differential pressure transmitters (3) through respective lower pressure guiding pipes (52); the accurate liquid level in the horizontal main pipe (11) can be indirectly measured by collecting the readings of the two differential pressure transmitters (3) and taking the average value.
2. The device for accurately measuring the liquid level in a tube for a nuclear reactor T-tube two-phase entrainment experiment according to claim 1, wherein the device comprises: the upper pressure measuring hole (61) and the lower pressure measuring hole (62) are bilaterally symmetrical about the symmetry axis of the stainless steel T-shaped pipe structure (1) and are positioned at equidistant positions from the flanges (2) at the two ends of the horizontal main pipe (11) and the vertical branch pipe (12) in the horizontal direction.
3. The device for accurately measuring the liquid level in a tube for a nuclear reactor T-tube two-phase entrainment experiment according to claim 1, wherein the device comprises: the T-shaped pipe structure (1) and the flange (2) are made of stainless steel.
4. A method for measuring the liquid level in a tube of a two-phase entrainment experiment of a T-tube of a nuclear reactor according to any one of claims 1 to 3, characterized by: before the two-phase entrainment experiment of the T-shaped pipe begins, the lower pressure guiding pipe (52) is filled with the liquid same as the experimental working medium, and the upper pressure guiding pipe (51) is filled with the gas same as the experimental working medium; in the T-shaped pipe two-phase entrainment experiment process, gas phase and liquid phase working media enter the horizontal main pipe (11) from two ends of the horizontal main pipe (11); part of liquid phase working medium is entrained into the vertical branch pipe (12) under the action of gas phase lifting force, and the gas phase working medium and the entrained liquid phase working medium flow out of the T-shaped pipe structure (1) through the outlet of the vertical branch pipe (12); in the experimental process, due to the existence of the entrainment phenomenon, partial liquid drops are entrained into the upper pressure guiding pipe (51), the liquid phase is carried to the vapor-water separation device (4) by the vapor phase to realize the separation of the vapor phase and the liquid phase, and after the experimental process is continued for a period of time, a valve at the bottom of the vapor-water separation device (4) is opened to empty the accumulated liquid; at the moment, the accurate liquid level in the horizontal main pipe (11) can be obtained by collecting the indication of the differential pressure transmitter in real time and taking the average value.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311730854.0A CN117705222A (en) | 2023-12-15 | 2023-12-15 | Device and method for accurately measuring liquid level in tube for nuclear reactor T-shaped tube two-phase entrainment experiment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311730854.0A CN117705222A (en) | 2023-12-15 | 2023-12-15 | Device and method for accurately measuring liquid level in tube for nuclear reactor T-shaped tube two-phase entrainment experiment |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN117705222A true CN117705222A (en) | 2024-03-15 |
Family
ID=90151081
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202311730854.0A Pending CN117705222A (en) | 2023-12-15 | 2023-12-15 | Device and method for accurately measuring liquid level in tube for nuclear reactor T-shaped tube two-phase entrainment experiment |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117705222A (en) |
-
2023
- 2023-12-15 CN CN202311730854.0A patent/CN117705222A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN111781075B (en) | Device and method for mechanical impact and vapor bubble migration experiment of lead-based stack evaporator heat transfer pipe fracture | |
| CN107481774A (en) | A kind of pilot system and its test method of the passive shutdown unit of nuclear reactor | |
| CN105157923B (en) | Method for testing tightness of isolation valve group at inlet and outlet of containment closed loop | |
| US7845223B2 (en) | Condensing chamber design | |
| CN105719708A (en) | T-shaped tube entrainment test system and method based on fourth-level depressurization system of reactor | |
| US5475720A (en) | Non-condensable gas tolerant condensing chamber | |
| CN110033872A (en) | A kind of universal sodium cold rapid stack component monomer hydraulic experiment rack and its experimental method | |
| CN103489492B (en) | A kind of non-active water level test device and test method | |
| CN117705222A (en) | Device and method for accurately measuring liquid level in tube for nuclear reactor T-shaped tube two-phase entrainment experiment | |
| CN103091027B (en) | Liquid pipeline equipment flowing pressure loss tester and testing method | |
| CN204203030U (en) | A kind of intelligent densitometer | |
| CN211553222U (en) | Waste heat boiler leakage detection device | |
| CN106680006B (en) | A kind of fission shell-and-tube exhaust-heat boiler experimental system and experimental method | |
| CN108766601B (en) | Experimental device and experimental method suitable for multi-working-medium liquid-phase entrainment research | |
| CN205351285U (en) | Waste heat boiler hunt leak on line device, online leak detection system and waste heat boiler system | |
| CN108798628A (en) | Gas-liquid separating metering device based on hollow billet force effect | |
| CN211477330U (en) | Device capable of overcoming impact influence of fluid on weighing device in flow detection process | |
| CN113686538A (en) | Experimental device for research pipe flow and instrument response characteristic under motion operating mode | |
| CN217359769U (en) | Tracer agent injection device for measuring steam humidity of nuclear power plant | |
| CN101655381B (en) | Circulating cooling water flow measuring method of condenser for steam turbine and on-line measuring device thereof | |
| CN201116881Y (en) | Sulfur pool liquid level measuring device | |
| CN111397679A (en) | Main steam flow measuring device of nuclear power plant and measuring method thereof | |
| CN211527540U (en) | Liquid level remote transmission measuring device for gas-liquid mixed pressure vessel | |
| CN218376434U (en) | Simple and easy applicable oil gas water three-phase flow metering device | |
| CN105181027B (en) | Gas-liquid two-phase reverse flow detection means in pipe |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |