CN109949951A - A kind of double shell type nuclear power station shell concrete slip measuring device - Google Patents
A kind of double shell type nuclear power station shell concrete slip measuring device Download PDFInfo
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- CN109949951A CN109949951A CN201910251957.6A CN201910251957A CN109949951A CN 109949951 A CN109949951 A CN 109949951A CN 201910251957 A CN201910251957 A CN 201910251957A CN 109949951 A CN109949951 A CN 109949951A
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- nuclear power
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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 belongs to nuclear power plant containment shell technical fields, and in particular to a kind of double shell type nuclear power station shell concrete slip measuring device.Gas hood is tested in the present invention to be mounted on containment exterior wall, tests and humidity transmitter, temperature sensor and test pressurising interface composition pressure-retaining system are installed on gas hood；Test gas source, local leak detector, pressurising interface are sequentially connected composition pressurizing system；Humidity transmitter, temperature sensor are connect with warm and humid collector, and warm and humid collector is then connected to computer, and computer is connected with barometer and high-precision pressure gauge, constitute data acquisition processing system；The present invention can guarantee the slip of accurate and flexible measurement concrete wall, ensure that containment shell seal tightness test is gone on smoothly.
Description
Technical field
The invention belongs to nuclear power plant containment shell technical fields, and in particular to a kind of double shell type nuclear power station shell concrete leakage
Rate measuring device.
Background technique
Field gulf nuclear power station VVER unit design double containment.The analysis and assessment of shell leakproofness are before nuclear power station charges
An important performance assessment mode.
Domestic nuclear power verifies the leakproofness of concrete shell wall, generally uses whole pressure maintaining flow monitoring method in shell,
The pressure of 400Pa outer higher than shell in shell is kept, starting exhausting system keeps pressure to remain unchanged, by measuring air draft pipe stream
Amount, to assess the permeability of concrete structure, this method is lower for shell overall tightness assessment accuracy, and can not refine
Each position of shell is assessed, in addition this kind of test method workload is very big, needs unit that special window cause for gossip is arranged to apply.
It key technology and lacks experience due to not knowing about, the measurement of shell concrete wall is assessed by other party, with
Machine unit characteristic is gradually understood, especially in the autonomous debugging process of unit of field gulf 3,4, for accurate, efficient assessment outside
Shell sealing performance, after consulting domestic and international related data, it is a kind of outer that we combine many years inner casing integrally to suppress experience autonomous Design
Shell concrete wall leakage rate assesses measuring device.Using dedicated measuring system by pressure to wall surface, temperature with
And humidity is for statistical analysis, finally obtains the permeability of outer containment concrete, to assess outer containment concrete wall
Sealing performance.
Summary of the invention
Present invention solves the technical problem that:
The present invention provides a kind of double shell type nuclear power station shell concrete slip measuring device, it is ensured that being capable of accurate and flexible survey
The slip of concrete wall is measured, ensures that containment shell seal tightness test is gone on smoothly.
The technical solution adopted by the present invention:
A kind of double shell type nuclear power station shell concrete slip measuring device, including test gas hood, humidity transmitter, temperature
Sensor, shut-off valve, warm and humid collector, high-precision pressure gauge, barometer, collecting computer, local leak detector, test are used
Gas source, test pressurising interface；Test gas hood is fixed on containment exterior wall, is tested and is equipped with humidity transmitter, temperature on gas hood
Sensor and test pressurising interface；Humidity transmitter, temperature sensor are connect with warm and humid collector, and warm and humid collector will be warm and humid
Computer is converted and be transmitted to degree signal, and high-precision pressure gauge is connect with computer；Pressurising interface is tested to press with high-precision simultaneously
Power table, test gas hood connect, and are equipped with shut-off valve on the pipeline of connection；High-precision pressure gauge is also connected with test gas source, atmosphere
Pressure gauge is connect with computer.
The test gas source, local leak detector, shut-off valve, test pressurising interface constitute pressurizing system.
The humidity transmitter, warm and humid collector, high-precision pressure gauge, barometer, calculates mechanism at temperature sensor
At data collection system；The humidity sensor is connect by cable with collector with temperature sensor, and epidemic disaster signal is passed
Transport to computer.
Pressure signal is transmitted to computer by cable with high-precision pressure gauge by the barometer.
The test gas hood is made by stainless steel material, and cover is along the curved surface for being designed to slight radian, in order to case surface
It is adjacent to containment exterior wall gapless.
The test gas hood supports the stabilization of guarantee test gas hood, sealing by equipment platform and Extendible knockout pin.
The retractable supports are using screwed pipe and threaded post understructure.
Beneficial effects of the present invention:
(1) a kind of double shell type nuclear power station shell concrete slip measuring device provided by the invention utilizes test gas hood
And retractable supports, rationally using particular job environment in region between double containment shell, improve testing ground execution can
Row and flexibility.
(2) a kind of double shell type nuclear power station shell concrete slip measuring device provided by the invention tests gas hood surface
It is designed to globoidal structure, so that quickly checking whether gas hood and wall contact surface have leakage in the pressurising stage, improves experiment work
Efficiency.
Detailed description of the invention
Fig. 1 is a kind of double shell type nuclear power station shell concrete slip measuring device structural schematic diagram provided by the invention；
Fig. 2 is test gas hood structural schematic diagram；
Fig. 3 is measuring device site layout project figure；
In figure: 1. containment exterior walls, 2. test gas hoods, 3. humidity transmitters, 4. temperature sensors, 5. shut-off valves, 6. innings
Gas is used in portion's leak detector, 7. warm and humid collectors, 8. high-precision pressure gauges, 9. barometers, 10. collecting computers, 11. tests
Source, 12. test pressurising interfaces, 13. ring glass gel coatings, 14. equipment platforms, 15. operation platforms, 16. containment interior walls,
17. screwed pipe and threaded post pedestal.
Specific embodiment
In the following with reference to the drawings and specific embodiments to a kind of double shell type nuclear power station shell concrete leakage provided by the invention
Rate measuring device is described in further detail.
As shown in Figure 1, a kind of double shell type nuclear power station shell concrete slip measuring device provided by the invention, including examination
Test gas hood 2, humidity transmitter 3, temperature sensor 4, shut-off valve 5, local leak detector 6, collector 7, high-precision pressure gauge 8, big
Atmospheric pressure table 9, computer 10, test gas source 11, test pressurising interface 12；
Test gas hood 2 is mounted on containment exterior wall 1, is tested and is equipped with humidity transmitter 3, temperature sensor 4 on gas hood 2
With test pressurising interface 12；
Humidity transmitter 3, temperature sensor 4 are connect with collector 7, and collector 7 is connect with computer 10；
Test pressurising interface 12 is connect with local leak detector 6, high-precision pressure gauge 8 simultaneously, is equipped on the pipeline of connection
Shut-off valve 5；
Local leak detector 6 is also connected with test gas source 11, high-precision pressure gauge 8 is connect with computer 10, computer 10
It is connected with barometer 9；
Test gas source 11, local leak detector 6, shut-off valve 5, test pressurising interface 12 constitute pressurizing device；
Humidity transmitter 3, temperature sensor 4, collector 7, high-precision pressure gauge 8, barometer 9,10 structure of computer
At data collection system；Humidity sensor 3 is connect by cable with collector 7 with temperature sensor 4, and epidemic disaster signal is passed
Transport to computer.Pressure signal is transmitted to computer by cable with high-precision pressure gauge 8 by barometer 9.
As shown in Fig. 2, test gas hood 2 is made by stainless steel material, cover is along the curved surface for being designed to slight radian, in order to outer
Shell surface is adjacent to 1 gapless of containment exterior wall.
As shown in figure 3, test gas hood 2 passes through equipment platform 14 and Extendible knockout pin support, sealant guarantee test gas hood
Stabilization, sealing.Retractable supports are using screwed pipe and 17 structure of threaded post pedestal.
Claims (7)
1. a kind of double shell type nuclear power station shell concrete slip measuring device, it is characterised in that: including test gas hood (2), wet
Spend transmitter (3), temperature sensor (4), shut-off valve (5), local leak detector (6), warm and humid collector (7), high-precision pressure gauge
(8), barometer (9), computer (10), test gas source (11), test pressurising interface (12)；Test gas hood (2) installation
On containment exterior wall (1), humidity transmitter (3), temperature sensor (4) and test pressurising are installed in test gas hood (2) and connect
Mouth (12)；Humidity transmitter (3), temperature sensor (4) are connect with warm and humid collector (7), warm and humid collector (7) and computer
(10) it connects；Test pressurising interface (12) is connect with high-precision pressure gauge (8), local leak detector (6) simultaneously, on the pipeline of connection
It is equipped with shut-off valve (5)；Local leak detector (6) is also connected with test gas source (11), high-precision pressure gauge (8) and computer
(10) it connects；Computer (10) is connected with barometer.
2. a kind of double shell type nuclear power station shell concrete slip measuring device according to claim 1, it is characterised in that:
The test gas mask (11), local leak detector (6), shut-off valve (5), test pressurising interface (12) constitute pressurizing device.
3. a kind of double shell type nuclear power station shell concrete slip measuring device according to claim 1, it is characterised in that:
The humidity transmitter (3), temperature sensor (4), warm and humid collector (7), high-precision pressure gauge (8), barometer (9),
Computer (10) constitutes data collection system；The humidity sensor (3) and temperature sensor (4) pass through cable and collector
(7) it connects, epidemic disaster signal is transmitted to computer (10).
4. a kind of double shell type nuclear power station shell concrete slip measuring device according to claim 1, it is characterised in that:
Pressure signal is transmitted to computer by cable with high-precision pressure gauge (8) by the barometer (9).
5. a kind of double shell type nuclear power station shell concrete slip measuring device according to claim 1, it is characterised in that:
The test gas hood (2) is made by stainless steel material, and cover is along the curved surface for being designed to slight radian, in order to case surface and safety
Shell exterior wall (1) gapless is adjacent to.
6. a kind of double shell type nuclear power station shell concrete slip measuring device according to claim 5, it is characterised in that:
Test gas hood (2) passes through equipment platform (14), the stabilization, close of Extendible knockout pin support and sealant guarantee test gas hood
Envelope.
7. a kind of double shell type nuclear power station shell concrete slip measuring device according to claim 6, it is characterised in that:
The retractable supports are using screwed pipe and threaded post pedestal (17) structure.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910251957.6A CN109949951A (en) | 2019-03-29 | 2019-03-29 | A kind of double shell type nuclear power station shell concrete slip measuring device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910251957.6A CN109949951A (en) | 2019-03-29 | 2019-03-29 | A kind of double shell type nuclear power station shell concrete slip measuring device |
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| CN109949951A true CN109949951A (en) | 2019-06-28 |
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| CN201910251957.6A Pending CN109949951A (en) | 2019-03-29 | 2019-03-29 | A kind of double shell type nuclear power station shell concrete slip measuring device |
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-
2019
- 2019-03-29 CN CN201910251957.6A patent/CN109949951A/en active Pending
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| FR2693551A1 (en) * | 1992-07-10 | 1994-01-14 | Electricite De France | Device indicating the flow rate of a leak in a primary circuit of a nuclear reactor. |
| KR20090003128U (en) * | 2007-09-28 | 2009-04-01 | 한국전력공사 | Dual Sensor Wireless Measurement Apparatus for Integrated Leakage Rate Test of Nuclear Power Plant |
| CN102420021A (en) * | 2011-11-15 | 2012-04-18 | 中广核工程有限公司 | Nuclear power station containment vessel leakage rate monitoring method and system |
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| CN203070790U (en) * | 2013-01-14 | 2013-07-17 | 上海核工程研究设计院 | System for quantitatively measuring coolant leakage rate of primary loop of pressurized water reactor nuclear power plant |
| KR101801529B1 (en) * | 2016-10-10 | 2017-11-27 | 한국기계연구원 | equipment for performance test of coating in loss of coolant accident test of nuclear power plant |
| CN107403652A (en) * | 2017-07-20 | 2017-11-28 | 中广核工程有限公司 | A kind of nuclear power station interlayer containment leak tightness measurement apparatus and method |
| CN210295924U (en) * | 2019-03-29 | 2020-04-10 | 江苏核电有限公司 | Double-shell type nuclear power station shell concrete leakage rate measuring device |
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