CN210295924U - Double-shell type nuclear power station shell concrete leakage rate measuring device - Google Patents
Double-shell type nuclear power station shell concrete leakage rate measuring device Download PDFInfo
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- CN210295924U CN210295924U CN201920420575.7U CN201920420575U CN210295924U CN 210295924 U CN210295924 U CN 210295924U CN 201920420575 U CN201920420575 U CN 201920420575U CN 210295924 U CN210295924 U CN 210295924U
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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 utility model belongs to the technical field of the nuclear power station containment, concretely relates to rate of leakage measuring device is let out to double-shelled nuclear power station shell concrete. The utility model discloses in test gas hood install on the containment outer wall, test gas hood is installed humidity transducer, temperature sensor and test and is pressurized the interface and form the pressurize system; the test gas source, the local leak detector and the pressurizing interface are sequentially connected to form a pressurizing system; the humidity transmitter and the temperature sensor are both connected with a temperature and humidity collector, the temperature and humidity collector is connected with a computer, and the computer is connected with an atmospheric pressure gauge and a high-precision pressure gauge to form a data acquisition and processing system; the utility model discloses can ensure can accurate nimble measuring concrete wall's leakage rate, guarantee that containment shell leakproofness is experimental goes on smoothly.
Description
Technical Field
The utility model belongs to the technical field of the nuclear power station containment, concretely relates to rate of leakage measuring device is let out to double-shelled nuclear power station shell concrete.
Background
A VVER unit of a gulf nuclear power station is designed with a double-layer containment. The evaluation and analysis of the shell tightness is an important performance assessment work before the nuclear power station is charged.
The method is characterized in that the tightness of the concrete shell wall of the domestic nuclear power station is verified, an in-shell integral pressure maintaining flow monitoring method is generally adopted, namely, the pressure in the shell is kept higher than 400Pa outside the shell, an air draft system is started to keep the pressure unchanged, and the permeability of the concrete structure is evaluated by measuring the flow of an air draft pipeline.
Because key technologies and inexperience are not known, the measurement of the concrete wall of the outer shell is evaluated by other parties, along with the gradual understanding of the unit characteristics, particularly in the independent debugging process of units No. 3 and No. 4 in Tianwan, in order to accurately and efficiently evaluate the sealing performance of the outer shell, after related data at home and abroad are consulted, an estimation and measurement device for the leakage rate of the concrete wall of the outer shell is independently designed by combining the integral pressing experience of the inner shell for many years. And finally obtaining the permeability of the concrete of the outer containment by utilizing a special measuring system to carry out statistical analysis on the pressure, the temperature and the humidity of the wall surface, thereby evaluating the sealing performance of the concrete wall of the outer containment.
Disclosure of Invention
The utility model provides a technical problem:
the utility model provides a two shell type nuclear power station shell concrete leakage rate measuring device ensures can accurate nimble leakage rate of measuring the concrete wall, and guarantee containment shell leakproofness is experimental to go on smoothly.
The utility model adopts the technical proposal that:
a double-shell type nuclear power station shell concrete leakage rate measuring device comprises a test gas hood, a humidity transmitter, a temperature sensor, a stop valve, a temperature and humidity collector, a high-precision pressure gauge, an atmospheric pressure gauge, a collecting computer, a local leak detector, a gas source for test and a test pressurizing interface; the test gas hood is fixed on the outer wall of the containment, and a humidity transmitter, a temperature sensor and a test pressurizing interface are arranged on the test gas hood; the temperature and humidity acquisition device converts and transmits temperature and humidity signals to the computer, and the high-precision pressure gauge is connected with the computer; the test pressurizing interface is simultaneously connected with the high-precision pressure gauge and the test gas hood, and stop valves are arranged on the connected pipelines; the high-precision pressure gauge is also connected with an air source for testing, and the atmospheric pressure gauge is connected with a computer.
And the gas source for the test, the local leak detector, the stop valve and the test pressurizing interface form a pressurizing system.
The humidity transmitter, the temperature sensor, the temperature and humidity collector, the high-precision pressure gauge, the atmospheric pressure gauge and the calculation mechanism form a data acquisition system; the humidity sensor and the temperature sensor are connected with the collector through cables, and transmit temperature and humidity signals to the computer.
And the atmospheric pressure gauge and the high-precision pressure gauge transmit pressure signals to a computer through cables.
The test gas hood is made of stainless steel materials, and the edge of the hood is designed into a slightly-radian curved surface so that the surface of the shell is tightly attached to the outer wall of the containment shell without a gap.
The test gas hood is supported through the equipment platform and the telescopic ejector rod to ensure the stability and the sealing of the test gas hood.
The telescopic support adopts a threaded pipe and threaded column base structure.
The utility model has the advantages that:
(1) the utility model provides a pair of two shell type nuclear power station shell concrete leakage rate measuring device utilizes experimental gas hood and scalable support, and the regional special operational environment between the double-deck containment shell of rational utilization has improved feasibility and the flexibility of experimental on-the-spot execution.
(2) The utility model provides a pair of two shell type nuclear power station shell concrete leakage rate measuring device, cambered surface structure is designed into to experimental gas hood surface for whether have the hourglass at pressurization stage short-term test gas hood and wall contact surface, improved experimental work efficiency.
Drawings
Fig. 1 is a schematic structural view of a device for measuring a concrete leakage rate of a shell of a double-shell nuclear power station provided by the utility model;
FIG. 2 is a schematic diagram of a test gas hood configuration;
FIG. 3 is a diagram of a field layout of a measuring device;
in the figure: 1. the device comprises a containment outer wall, 2. a test gas hood, 3. a humidity transmitter, 4. a temperature sensor, 5. a stop valve, 6. a local leak detector, 7. a temperature and humidity collector, 8. a high-precision pressure gauge, 9. an atmospheric pressure gauge, 10. a collecting computer, 11. a test gas source, 12. a test pressurizing interface, 13. an annular glass cement coating, 14. an equipment platform, 15. a construction platform, 16. a containment inner wall, 17. a threaded pipe and a threaded column base.
Detailed Description
The following describes the concrete leakage rate measuring device for the double-shell nuclear power station shell according to the present invention in detail with reference to the accompanying drawings and specific embodiments.
As shown in fig. 1, the utility model provides a double-shell type nuclear power station shell concrete leakage rate measuring device, which comprises a test gas hood 2, a humidity transmitter 3, a temperature sensor 4, a stop valve 5, a local leak detector 6, a collector 7, a high-precision pressure gauge 8, an atmospheric pressure gauge 9, a computer 10, a test gas source 11 and a test pressurizing interface 12;
the test gas hood 2 is arranged on the containment outer wall 1, and the test gas hood 2 is provided with a humidity transmitter 3, a temperature sensor 4 and a test pressurizing interface 12;
the humidity transmitter 3 and the temperature sensor 4 are both connected with a collector 7, and the collector 7 is connected with a computer 10;
the test pressurizing interface 12 is simultaneously connected with the local leak detector 6 and the high-precision pressure gauge 8, and the connected pipelines are provided with stop valves 5;
the local leak detector 6 is also connected with a gas source 11 for testing, a high-precision pressure gauge 8 and a computer 10, and the computer 10 is connected with an atmospheric pressure gauge 9;
the test gas source 11, the local leak detector 6, the stop valve 5 and the test pressurizing interface 12 form a pressurizing device;
the humidity transmitter 3, the temperature sensor 4, the collector 7, the high-precision pressure gauge 8, the atmospheric pressure gauge 9 and the computer 10 form a data acquisition system; the humidity sensor 3 and the temperature sensor 4 are connected with the collector 7 through cables, and transmit temperature and humidity signals to the computer. The atmospheric pressure gauge 9 and the high-precision pressure gauge 8 transmit pressure signals to a computer through cables.
As shown in FIG. 2, the test gas hood 2 is made of stainless steel material, and the hood edge is designed into a slightly cambered surface so that the surface of the shell is tightly attached to the outer wall 1 of the containment shell without clearance.
As shown in fig. 3, the test gas hood 2 is supported and sealed by the equipment platform 14 and the telescopic mandril to ensure the stability and the sealing performance of the test gas hood. The telescopic support adopts a structure of a threaded pipe and a threaded column base 17.
Claims (7)
1. The utility model provides a two shell type nuclear power station shell concrete leakage rate measuring device which characterized in that: the device comprises a test gas hood (2), a humidity transmitter (3), a temperature sensor (4), a stop valve (5), a local leak detector (6), a temperature and humidity collector (7), a high-precision pressure gauge (8), an atmospheric pressure gauge (9), a computer (10), a test gas source (11) and a test pressurizing interface (12); the test gas hood (2) is arranged on the containment outer wall (1), and the test gas hood (2) is provided with a humidity transmitter (3), a temperature sensor (4) and a test pressurizing interface (12); the humidity transmitter (3) and the temperature sensor (4) are both connected with a temperature and humidity collector (7), and the temperature and humidity collector (7) is connected with a computer (10); the test pressurizing interface (12) is simultaneously connected with a high-precision pressure gauge (8) and a local leak detector (6), and stop valves (5) are arranged on connected pipelines; the local leak detector (6) is also connected with a gas source (11) for testing, and the high-precision pressure gauge (8) is connected with a computer (10); the computer (10) is connected with an atmospheric pressure gauge.
2. The apparatus for measuring the concrete leakage rate of the outer shell of the double-shell nuclear power station as claimed in claim 1, wherein: and the gas source (11) for the test, the local leak detector (6), the stop valve (5) and the test pressurizing interface (12) form a pressurizing device.
3. The apparatus for measuring the concrete leakage rate of the outer shell of the double-shell nuclear power station as claimed in claim 1, wherein: the humidity transmitter (3), the temperature sensor (4), the temperature and humidity collector (7), the high-precision pressure gauge (8), the atmosphere pressure gauge (9) and the computer (10) form a data acquisition system; and the humidity transmitter (3) and the temperature sensor (4) are connected with the collector (7) through cables, and transmit temperature and humidity signals to the computer (10).
4. The apparatus for measuring the concrete leakage rate of the outer shell of the double-shell nuclear power station as claimed in claim 1, wherein: and the atmospheric pressure gauge (9) and the high-precision pressure gauge (8) transmit pressure signals to a computer through cables.
5. The apparatus for measuring the concrete leakage rate of the outer shell of the double-shell nuclear power station as claimed in claim 1, wherein: the test gas hood (2) is made of stainless steel materials, and the hood edge is designed into a slightly-cambered curved surface so that the surface of the shell can be tightly attached to the outer wall (1) of the containment shell without a gap.
6. The apparatus for measuring the concrete leakage rate of the outer shell of the double-shell nuclear power station as claimed in claim 5, wherein: the test gas hood (2) is supported and sealed through the equipment platform (14) and the telescopic ejector rod to ensure the stability of the test gas hood.
7. The apparatus for measuring the concrete leakage rate of the outer shell of the double-shell nuclear power station as claimed in claim 6, wherein: the telescopic support adopts a structure of a threaded pipe and a threaded column base (17).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920420575.7U CN210295924U (en) | 2019-03-29 | 2019-03-29 | Double-shell type nuclear power station shell concrete leakage rate measuring device |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920420575.7U CN210295924U (en) | 2019-03-29 | 2019-03-29 | Double-shell type nuclear power station shell concrete leakage rate measuring device |
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| CN210295924U true CN210295924U (en) | 2020-04-10 |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109949951A (en) * | 2019-03-29 | 2019-06-28 | 江苏核电有限公司 | A kind of double shell type nuclear power station shell concrete slip measuring device |
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2019
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109949951A (en) * | 2019-03-29 | 2019-06-28 | 江苏核电有限公司 | A kind of double shell type nuclear power station shell concrete slip measuring device |
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