WO2022218423A1 - System for testing containment building of nuclear power plant - Google Patents

System for testing containment building of nuclear power plant Download PDF

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Publication number
WO2022218423A1
WO2022218423A1 PCT/CN2022/087188 CN2022087188W WO2022218423A1 WO 2022218423 A1 WO2022218423 A1 WO 2022218423A1 CN 2022087188 W CN2022087188 W CN 2022087188W WO 2022218423 A1 WO2022218423 A1 WO 2022218423A1
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WIPO (PCT)
Prior art keywords
containment
module
data
sound
power plant
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PCT/CN2022/087188
Other languages
French (fr)
Chinese (zh)
Inventor
赵健
何锐
乔丕业
金成毅
张国军
蔡建涛
张波
李少纯
肖志雪
赵岩
周亚文
陈威
赵云涛
杨宏星
沈东明
周创彬
宋文奎
李思锦
Original Assignee
中广核工程有限公司
中国广核集团有限公司
中国广核电力股份有限公司
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Application filed by 中广核工程有限公司, 中国广核集团有限公司, 中国广核电力股份有限公司 filed Critical 中广核工程有限公司
Publication of WO2022218423A1 publication Critical patent/WO2022218423A1/en

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/07—Leak testing
    • G—PHYSICS
    • G06—COMPUTING; CALCULATING OR COUNTING
    • G06F—ELECTRIC DIGITAL DATA PROCESSING
    • G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
    • G06F17/10—Complex mathematical operations
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/003—Remote inspection of vessels, e.g. pressure vessels
    • 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

Definitions

  • the invention relates to the technical field of nuclear power plant containment pressure test, and more particularly, to a nuclear power plant containment test system.
  • the nuclear power plant containment is a prestressed reinforced concrete structure with prestressed steel bundles arranged in the vertical and horizontal directions respectively.
  • the containment is the third safety barrier after the nuclear fuel cladding and the primary circuit pressure vessel. It plays an important role in restricting the diffusion of radioactive substances from the reactor to the atmosphere. Its construction quality will directly affect the functional integrity of the containment body. Its function is to limit and eliminate the fission in the accident when the primary circuit pipeline ruptures and causes a water loss accident, so as to ensure the safety of the social environment and the public. Therefore, a containment test (CTT) is required before the unit is put into operation to verify the strength and tightness of the containment.
  • CTT containment test
  • one of the cores of the existing containment pressure test is the leakage rate test, which involves the continuous acquisition and fitting calculation of temperature, humidity and pressure data during the test, which is a high-precision
  • the computing category due to its particularity, must be processed with special technical specifications and algorithms, and special data acquisition and processing software can be developed to meet the requirements.
  • the original sensor algorithms after years of absorption and introduction of the current reactor type, the original sensor algorithms have been unable to meet the requirements, resulting in a large error in the overall leakage rate of the containment.
  • the technical problem to be solved by the present invention is to provide a nuclear power plant containment test system aiming at the above-mentioned defects of the prior art.
  • the technical scheme adopted by the present invention to solve the technical problem is: constructing a nuclear power plant containment test system, including: a containment overall leakage rate measurement module, a containment sound leak detection module, an alarm module and a display module;
  • the containment overall leakage rate measurement module is used to measure the overall leakage rate in the containment and calculate the measurement data to obtain the real-time overall leakage rate and uncertainty of the containment;
  • the containment sound leak detection module is used to monitor the sound signal of the containment and analyze and process the monitored sound signal, and then output the containment sound leak detection measurement result to obtain the containment leak location and area;
  • the alarm module is configured to output a corresponding alarm signal when the real-time overall leakage rate, the uncertainty, and the containment sound leak;
  • the display module is configured to display the real-time overall leak rate, the uncertainty and the measurement result of the containment acoustic leak detection.
  • the overall containment leak rate measurement module includes: a leak rate measurement device, a pressure regulation module, a pressure operation module, and a calculation module;
  • the leakage rate measuring device is used to collect the parameters of the containment leakage signal in real time, obtain leakage data based on the parameters of the containment leakage signal, and perform real-time calculation on the leakage data to obtain a calculation result, and in the calculation result Calculate the real-time leak rate and its uncertainty after satisfying the gas stability conditions;
  • the pressure regulation module is used to perform real-time fitting and calculation processing on the leakage acquisition signal, obtain the real-time pressure increase speed and the real-time pressure reduction speed, and control the pressure increase when the real-time pressure increase speed and the real-time pressure reduction speed are greater than the preset values.
  • the pressure operation module is used to control and close the buck-boost electric regulating valve when the pressure reaches the threshold value, and monitor all parameters in the containment and perform real-time calculation;
  • the calculation module is configured to perform calculation according to the leak acquisition signal to obtain the real-time overall leak rate and uncertainty of the containment.
  • the containment overall leakage rate measurement module further includes: a data simulation module and a data display module;
  • the data simulation module is used for simulating the function of the overall leakage rate measurement module of the containment to obtain simulation data before the containment test;
  • the data display module is used for the status information and working information of the containment shell.
  • the containment overall leakage rate measurement module further includes: a storage and printing module;
  • the storage and printing module is used for storing and printing out the real-time overall leakage rate and uncertainty of the containment vessel.
  • the uncertainty includes: type A uncertainty and type B uncertainty;
  • the type A uncertainty includes: temperature standard uncertainty, humidity standard uncertainty Certainty and pressure standard uncertainty;
  • the temperature standard uncertainty is calculated using the subregional fitting method;
  • the humidity standard uncertainty and the pressure standard uncertainty are calculated using a subregional fitting algorithm.
  • the containment overall leakage rate measurement module further includes: a penetration measurement module;
  • the penetration measurement module is used for measuring the tightness of the penetration of the containment, so as to obtain the sealing test result of the penetration of the containment.
  • the penetration measurement module includes: a pressure-bearing box, a single-chip microcomputer, a display, a penetration measurement unit and an actuator arranged in the pressure-bearing box;
  • the penetration measurement unit performs data acquisition and obtains measurement data
  • the single-chip microcomputer controls the actuator according to the test instruction and the measurement data
  • the executor performs work according to the control of the single-chip microcomputer
  • the display displays the result of the tightness test of the penetration of the containment.
  • the penetration measurement unit includes: a pressure sensor, a temperature sensor, a small flow sensor, a medium flow sensor and a large flow sensor;
  • the actuator includes: provided on the input pipeline The first solenoid valve, the second solenoid valve set on the first input branch pipeline, the third solenoid valve set on the second input branch pipeline, the seventh solenoid valve set on the first output branch pipeline, the The eighth solenoid valve on the second output branch pipe, the fourth solenoid valve on the first sub-pipe, the fifth solenoid valve on the second sub-pipe, and the sixth solenoid valve on the third sub-pipe and the ninth solenoid valve arranged on the output pipeline;
  • the first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged in parallel, and the first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged in the first sub-pipeline between the input branch pipe and the first output branch pipe;
  • the pressure sensor and the temperature sensor are arranged between the second input branch pipe and the second output branch pipe;
  • the penetration measurement module further includes: a gas drying filter disposed on the input pipeline and located outside the pressure-containing box;
  • the gas drying filter is used for drying and filtering the gas input into the pressure-holding box.
  • the containment overall leakage rate measurement module and the containment strength monitoring module measure the free volume of the containment by the free volume method, and perform the sensor test according to the area where the sensor in the containment is located. Weight distribution.
  • the calculation module includes: a containment parameter processing module, a containment monitoring data processing module, an optimal path calculation module, a volume weight distribution module, and a data output module;
  • the containment parameter processing module performs modeling and grid division according to the containment wall size data to obtain free space grid data
  • the containment monitoring data processing module performs grid coordinate gridization of the instrument according to the position data of the temperature sensor and the position data of the humidity sensor, and obtains the grid data of the instrument;
  • the optimal path calculation module calculates according to the free space grid data and the meter grid data to obtain the optimal path of each meter;
  • the volume weight allocation module calculates according to the optimal path to obtain the volume weight of each meter
  • the data output module outputs the weight of each meter volume.
  • the containment acoustic leak detection module includes: a sound acquisition module, a sound monitoring module, a vibration monitoring module and a directional transmission module;
  • the sound collection module is used for real-time monitoring and collection of the sound signal of the containment to obtain the sound collection signal
  • the sound monitoring module is used for monitoring the sound collection signal and outputting the sound leak detection measurement result of the containment
  • the vibration monitoring module is used to monitor the vibration value of the fixed pipeline and the working state of the valve
  • the directional transmission module is used for outputting the measurement result of the containment acoustic leak detection and the containment leak location and area.
  • the sound monitoring module includes: a signal acquisition module, a signal analysis module and a sound amplification module;
  • the signal acquisition module is used to collect the sound acquisition signal and transmit it to the signal analysis module;
  • the signal analysis module is configured to analyze and filter the sound acquisition signal to obtain a filtered sound signal, and send the filtered sound signal to the sound amplification module;
  • the sound amplifying module is used for amplifying the filtered sound signal to obtain the sound leak detection measurement result of the containment vessel.
  • the containment sound leak detection measurement result includes: sound acquisition module address and sound data;
  • the sound monitoring module further includes: a storage circuit and a sound transmission module;
  • the storage circuit is used for storing the sound data
  • the sound transmission module is used for outputting the address of the sound acquisition module and the sound data to obtain the leak location and area of the containment vessel.
  • the sound transmission module includes: a wireless transmitting module and a wireless receiving module;
  • the wireless transmitting module is configured to receive the address of the sound acquisition module and the sound data and send them to the wireless receiving module;
  • the wireless receiving module is used for receiving and outputting the address of the sound collecting module and the sound data.
  • the sound monitoring module further includes: a vibration sensor
  • the vibration sensor is used to monitor the vibration displacement of the sound monitoring module and send the address of the sound monitoring module to the wireless transmitting module when the vibration displacement of the sound monitoring module is greater than a preset value.
  • the directional transmission module includes: a directional transmission cable
  • the directional transmission cable receives the containment acoustic leak detection measurement and transmits it to the outside of the containment.
  • the nuclear power plant containment test system of the present invention further includes: a containment appearance inspection module;
  • the containment appearance inspection module includes: a wall climbing robot, a ground station unit, an image acquisition unit, an image acquisition and processing unit, an appearance data transmission unit, a position confirmation device, a spraying device and an anti-fall device;
  • the wall-climbing robot is used to perform the walking action on the wall of the containment according to the control instruction
  • the ground station unit is used to collect the geometric information of the appearance defect image of the containment vessel and analyze and process the image information
  • the image acquisition unit is configured to scan and photograph the containment wall to obtain image data of the containment wall;
  • the image acquisition and processing unit is configured to collect and analyze the image data to obtain the geometric information of the appearance defect image of the containment vessel;
  • the appearance data transmission unit is configured to send the geometric information of the appearance defect image of the containment to the ground station unit;
  • the spraying device is used for marking the detected defect information.
  • the position confirmation device is used to record and store the position information of the defect after the robot completes the defect marking
  • the anti-fall device is used to prevent the wall-climbing robot from falling.
  • the image acquisition and processing unit includes: a receiving and sending drive module, a bottom communication module, a host computer interface module, a background operation database module, a background service system module and a sub-function module;
  • the receiving and sending drive modules are used to convert and transmit the received and received data
  • the underlying communication module is used for calling, distributing and temporarily storing underlying data
  • the host computer interface module is used for displaying the appearance defect image information and receiving the operation information input by the user;
  • the background operation database module is used to store the image data of the containment wall and manage user information
  • the background service system is used for controlling and coordinating the operation of the sub-function modules.
  • the sub-function modules include: a control module, a positioning module, a video system module, an image system module, a tool module, a menu module, a document marking module, a retrieval module, and a defect drawing module , storage module and algorithm module;
  • the control module is used to integrate and transmit control commands
  • the positioning module is used for positioning and converting the position information of the wall-climbing robot into coordinates corresponding to the position information;
  • the video system module is used to encode and convert the video information in the appearance defect image information wirelessly transmitted to the ground station unit into a video stream;
  • the image system module is used for photographing, magnifying and analyzing images with appearance defects
  • the tool module is used to provide a visual inspection tool
  • the menu module is used to combine with control instructions and/or conversion instructions
  • the document marking module is used to integrate defect data
  • the retrieval module is used for data retrieval and data allocation
  • the defect drawing module is used to redraw the two-dimensional image of the appearance defect image information
  • the storage module is used for storing the appearance defect image information
  • the algorithm module is used to perform defect identification, analysis and calculation on the image data of the containment wall surface, and obtain the geometric information of the appearance defect image of the containment vessel.
  • nuclear power plant containment test system of the present invention further comprises: a fire monitoring module;
  • the fire monitoring module is used for carrying out fire monitoring on the containment and outputting fire monitoring information.
  • the fire monitoring module includes: a plurality of thermal imagers, gas sensors, smoke sensors, electrical penetrations arranged on the containment, and transmission cables;
  • the plurality of thermal imagers are used for monitoring the temperature in the containment and outputting fire monitoring information
  • the gas sensor is used for monitoring gas information in the containment
  • the smoke sensor is used for monitoring smoke information in the containment
  • the transmission cable receives the fire monitoring information, gas information and smoke information and transmits it to the outside of the containment through the electrical penetration, and transmits the thermal imager and gas sensor power from outside the containment to the safety inside the shell.
  • each of the thermal imagers is built into a protective cover, and the protective cover is a stainless steel protective cover; the smoke sensor measures through a gas leakage pipe.
  • the protective cover includes an outer shell and a sealing test interface disposed at the bottom of the outer shell; the thermal imager is built in the outer shell and passes the sealing test The interface is tested for tightness.
  • nuclear power plant containment test system of the present invention further comprises: a main circuit check valve leakage rate monitoring module;
  • the main loop check valve leakage rate monitoring module is used for monitoring the main loop check valve leakage rate and outputting the main loop check valve leakage rate monitoring results.
  • the leakage rate monitoring module of the check valve of the main circuit includes: a check valve blocking device;
  • the check valve blocking device includes a valve cavity, a sealing airbag, an axial Balance device, charging unit and monitoring unit;
  • the charging unit is used for charging the valve cavity of the check valve or the sealing airbag;
  • the axial balance device is used to balance the axial force in the valve cavity
  • the monitoring unit is used to monitor the charging data of the check valve, and calculate the leakage rate of the check valve according to the charging data;
  • the leakage rate monitoring result of the check valve of the main circuit is output.
  • the charging unit includes: a first charging device and a second charging device;
  • the first pressurizing device is used to pressurize the valve cavity of the check valve and collect pressure data of the valve cavity;
  • the second inflating device is used for inflating the sealing airbag and collecting pressure data of the sealing airbag.
  • the charging data includes: the pressure data of the valve cavity and the pressure data of the sealed airbag;
  • the first inflating device includes: a first inflatable air bag, a first valve and a first pressure gauge;
  • the second inflatable device includes: a second inflatable air bag, a second valve and a second pressure gauge;
  • the first inflatable air bag is used to inflate the valve cavity
  • the first pressure gauge is used to collect pressure data of the valve cavity during the inflation of the first inflatable airbag
  • the first valve is opened when the first inflatable air bag is inflated
  • the second inflatable airbag is used to inflate the sealing airbag
  • the second pressure gauge is used to collect pressure data of the sealed airbag during the inflation of the second inflatable airbag
  • the second valve opens when the second inflation bladder is inflated.
  • the check valve blocking device further comprises: a valve cover located at the opening of the valve cavity so that the valve cavity forms a closed space.
  • the check valve blocking device further comprises: an axial balance device located in the valve cavity to balance the axial force in the valve cavity.
  • the nuclear power plant containment test system of the present invention further includes: a containment strength monitoring module;
  • the containment strength monitoring module is used for monitoring the strength of the containment and outputting strength monitoring data.
  • the containment strength monitoring module includes: a strength monitoring data acquisition device, an EAU automatic reading module and a wireless communication module;
  • the strength monitoring data acquisition device is used for collecting the strength data of the containment to obtain the strength monitoring data of the containment
  • the EAU automatic reading module is used to read and output the containment strength monitoring data
  • the wireless communication module is used for transmitting the monitoring data of the containment strength.
  • the strength monitoring data acquisition device includes: a thermocouple, an audio frequency strain gauge, a level box, a displacement gauge, and a plumb line monitoring device;
  • thermocouple is used to collect thermocouple data
  • the audio frequency strain gauge is used to collect the deformation stress of the containment and obtain the deformation stress data
  • the level box is used to collect the deformation displacement of the containment and obtain the deformation displacement data
  • the displacement gauge is connected to the level box and the terrain reference point, and is used to obtain relative change data between the geodetic reference point and the containment raft during the test;
  • the plumb line monitoring device is used to monitor plumb line deformation of the containment and obtain plumb line data.
  • the containment strength monitoring module further includes: a plumb line data acquisition module;
  • the plumb line data acquisition module is used for receiving and outputting plumb line data collected by the plumb line monitoring equipment.
  • the EAU automatic counting module includes: an EAU automatic reading box, a three-way adapter box and an EAU automatic reading device;
  • the EAU automatic reading box reads the thermocouple data collected by the thermocouple, the deformation stress data collected by the audio frequency strain gauge, and the deformation displacement data collected by the level box, and converts the thermocouple data, the deformation The stress data and the deformation displacement data are sent to the three-way adapter box;
  • the three-way adapter box receives and coordinates the deformation displacement data collected by the level box, and transmits the thermocouple data, the deformation stress data and the deformation displacement data to the EAU automatic reading device;
  • the EAU automatic reading device receives the deformation displacement data collected by the level box, and sends the thermocouple data, the deformation stress data and the deformation displacement data to the wireless communication module after conversion processing.
  • nuclear power plant containment test system of the present invention further comprises: an outer containment measurement module;
  • the outer containment measuring module measures the tightness of the outer containment and outputs the tightness measurement result.
  • the outer containment measurement module includes: a containment monitoring module, a flow controller, a collector and an industrial computer;
  • the containment monitoring module is used for collecting gas information of the outer containment
  • the flow controller is used to control the injection flow and collect flow data
  • the collector collects the outer containment data and the flow data and sends the data to the industrial computer;
  • the industrial computer analyzes and processes the outer containment data and the flow data, and outputs the tightness measurement result.
  • the outer containment measurement module further comprises: a display;
  • the display receives and displays the tightness measurement.
  • the nuclear power plant containment test system of the present invention further comprises: a containment bulge measurement module;
  • the containment bulge measurement module is used to measure the bulge in the containment and output the bulge measurement result.
  • the containment bulge measurement module includes: a containment bulge positioning unit, a containment bulge measurement unit, a containment bulge data transmission unit, and a containment bulge data processing unit;
  • the containment bulge positioning unit is used to locate and mark the defect position of the containment bulge
  • the containment bulge measurement unit is used to collect the containment bulge and output the bulge acquisition signal
  • the containment defect data transmission unit receives and transmits the bulge acquisition signal
  • the containment bulge data processing unit processes the bulge acquisition signal and outputs the bulge measurement result.
  • the containment bulge measurement unit includes: a positioning device, a slide rail, a bracket, a pan/tilt, a laser distance sensor and a ranging encoder arranged on the pan/tilt;
  • the bracket includes a first support column and a second support column, the first end of the first support column is fixed at one end of the containment, and the second end of the first support column is connected to the first end of the slide rail.
  • the first end of the second support column is fixed on the other end of the containment shell, and the second end of the second support column is connected with the second end of the slide rail; the pan/tilt is slidably arranged at the on the slide rail;
  • the positioning device is arranged on the pan/tilt.
  • the containment bulge data transmission unit includes: a data communication module and a power supply unit;
  • the data communication module is connected with the containment bulge measurement unit to receive the bulge acquisition signal and transmit it to the containment bulge data processing unit;
  • the power supply unit is used for supplying power to the laser distance sensor, the distance measuring encoder and the safe shell bulging data processing unit.
  • the containment bulge data processing unit includes: a comparison module, a comparison analysis compensation, and a result output module;
  • the comparison module is used to compare and process the bulge acquisition signal, and output the bulge measurement data
  • the comparative analysis compensation is used to calculate the bulge measurement data in combination with the compensation data to obtain a bulge measurement result.
  • the containment defect measurement module further comprises: a display unit;
  • the display unit is used for displaying the measurement result of the bulge
  • the transmission unit sends the bulge measurement result to the containment strength monitoring module for correcting containment strength monitoring.
  • Implementing the nuclear power plant containment test system of the present invention has the following beneficial effects: comprising: a containment overall leak rate measurement module, a containment sound leak detection module, an alarm module and a display module; the containment overall leak rate measurement module is used for the containment Measure and calculate the overall leak rate in the containment to obtain the real-time overall leak rate and uncertainty of the containment; the containment sound leak detection module is used to monitor the sound signal of the containment and monitor the sound After the signal is analyzed and processed, the measurement result of the containment sound leak detection is output; the alarm module is used to output the corresponding alarm signal when the real-time overall leak rate, uncertainty, and containment sound leak; the display module is used to monitor the real-time overall leak rate , uncertainty and containment acoustic leak detection measurement results are displayed.
  • the invention can accurately measure the overall leakage rate of the containment, has high precision, and can detect whether the containment leaks through sound, thereby improving the reliability of the sealing test.
  • FIG. 1 is a schematic block diagram of a nuclear power plant containment test system provided by an embodiment of the present invention
  • Fig. 2 is the principle block diagram of the overall leakage rate measurement module of the containment of the present invention.
  • Fig. 3 is the schematic diagram of the inner space partition of the containment of the present invention.
  • Figure 6 is a schematic diagram of the optimal path
  • Fig. 7 is the layout diagram of a test temperature sensor T18/T19/T30 of the present invention.
  • FIG. 8 is a schematic diagram of the temperature curve of a certain test temperature sensor T18/T19/T30 of the present invention.
  • Fig. 9 is the principle block diagram of the penetration measurement module of the present invention.
  • FIG. 10 is a schematic plan view of the penetration measurement module of the present invention.
  • Fig. 11 is the control work logic diagram of the single-chip microcomputer of the present invention.
  • Fig. 12 is the principle block diagram of the containment sound leak detection module of the present invention.
  • Fig. 13 is the sound monitoring module principle block diagram of the present invention.
  • Fig. 14 is the principle block diagram of the safety square meter appearance inspection module of the present invention.
  • 15 is a schematic block diagram of an image acquisition and processing unit of the present invention.
  • FIG. 16 is a schematic structural diagram of a fire monitoring module of the present invention.
  • FIG. 17 is a schematic structural diagram of a protective cover of the thermal imager of the present invention.
  • FIG. 19 is a schematic block diagram of the containment strength monitoring module of the present invention.
  • Fig. 20 is the intensity data processing flow chart of the present invention.
  • Fig. 21 is the principle block diagram of the outer containment measurement module of the present invention.
  • Figure 22 is a schematic diagram of the leakage source of the outer containment of the present invention.
  • Fig. 23 is the principle block diagram of the containment bulge measurement module of the present invention.
  • Figure 24 is a schematic structural diagram of the containment bulge measurement module of the present invention.
  • FIG. 1 is a schematic block diagram of a nuclear power plant containment test system provided by an embodiment of the present invention.
  • the nuclear power plant containment test system automatically collects relevant sensor signals in the containment concrete, and classifies, calculates, and eliminates the collected data, and then evaluates the overall performance of the containment based on the concrete data during construction.
  • the nuclear power plant containment test system includes: a containment overall leak rate measurement module 10 , a containment acoustic leak detection module 20 , an alarm module 100 and a display module 90 .
  • the overall leakage rate measurement module 10 of the containment is used to measure the overall leakage rate in the containment and calculate the measurement data to obtain the real-time overall leakage rate and uncertainty of the containment.
  • the containment sound leak detection module 20 is used to monitor the sound signal of the containment and analyze and process the monitored sound signal, and then output the containment sound leak detection measurement result to obtain the containment leak location and area;
  • the alarm module 100 is used to output a corresponding alarm signal when the real-time overall leak rate, uncertainty, and containment sound leak;
  • the display module 90 is used to display the real-time overall leak rate, uncertainty, and containment sound leak detection measurement results.
  • the entire containment leak rate measurement module 10 includes: a leak rate measurement device 101 , a pressure adjustment module 102 , a pressure operation module 103 and a calculation module 104 .
  • the leak rate measurement device 101 is used for real-time collection of containment leakage signal parameters, to obtain leakage data based on the obtained safety over-leakage signal parameters, and to perform real-time calculation on the leakage data to obtain a calculation result, and when the calculation result satisfies the gas stability condition The real-time leak rate and uncertainty are then calculated.
  • the pressure adjustment module 102 is used to perform real-time fitting and calculation processing on the leakage acquisition signal, obtain the real-time pressure increase speed and the real-time pressure reduction speed, and control the buck-boost electric motor when the real-time pressure increase speed and the real-time pressure reduction speed are greater than the preset values. Adjust valve opening.
  • the pressure operation module 103 is configured to control the closing of the boosting and boosting when the pressure reaches the threshold value
  • the electric regulating valve is used to monitor and calculate all the parameters in the containment in real time.
  • the pressure reaching the threshold is that the pressure is greater than or equal to the threshold.
  • the calculation module 104 is configured to perform calculation according to the leakage acquisition signal to obtain the real-time overall leakage rate and uncertainty of the containment.
  • the gas stability conditions are:
  • the absolute value of the difference between L 2h and L 1h is less than or equal to 0.25L a , where L 2h : two-hour leak rate, L 1h : 1-hour leak rate, and La: the design maximum leak rate limit of the containment.
  • the leak rate measuring device 101 includes but is not limited to a plurality of temperature sensors (generally about 59 can be set), a plurality of humidity sensors (generally about 9 can be set) and a plurality of pressure sensors arranged in the containment. (Generally, about 3 can be set). Therefore, corresponding adjustment control can be performed based on the data measured by each sensor.
  • the pressure adjustment module 102 is generally used for the initial pressure adjustment of the pressure boosting platform, and mainly performs real-time processing on the data of the pressure transmitter, calculates the real-time pressure increase rate or pressure reduction rate at the same time, and analyzes the obtained pressure increase rate. Or the depressurization rate can be displayed in real time, as well as stored and printed.
  • the pressure operation module 103 generally monitors all parameters in the containment when the pressure adjustment module 102 adjusts the pressure to a threshold value, and simultaneously calculates the current pressure increase rate or pressure decrease rate in real time.
  • the calculation module 104 is an offline calculation module 104, which can calculate the overall leakage rate and uncertainty of the containment with reference to the original data of the containment test or the current test data of the containment test.
  • the whole containment leakage rate measurement module 10 further includes: a data simulation module 105 and a data display module 106 .
  • the data simulation module 105 is used for simulating the function of the overall leakage rate measurement module 10 of the containment to obtain simulation data.
  • the obtained simulation data can verify whether the stability and accuracy of the leak rate measurement system and measurement network meet the test requirements.
  • the data display module 106 is used for displaying the status information and working information of the containment vessel.
  • the status information of the containment includes: real-time overall leak rate, uncertainty, simulation data, real-time buck-boost data (boost speed/rate, buck speed/rate), and real-time measurement data of each sensor.
  • the working information includes: the current working status of the containment.
  • the overall leakage rate measurement module 10 of the containment further includes: a storage and printing module 107; the storage and printing module 107 is configured to store and print out the real-time overall leakage rate and uncertainty of the containment .
  • the data simulation module 105 is mainly used to simulate the function of collecting the overall leakage rate of the entire containment, and also has an offline data simulation function.
  • the data display module 106 displays current data and change trends in real time in the form of data and/or graphs.
  • the storage and printing module 107 stores the real-time data in the database according to the specified format and prints out the corresponding report.
  • the entire containment leak rate measurement module 10 is a containment leak rate measurement module based on a PXI (multiplexer).
  • the calculation of the overall leakage rate of the containment can be based on the absolute method, that is, the leakage rate is derived by calculating the change of the dry air quality in the containment.
  • the total mass of dry air in the containment is:
  • M is the mass of dry air in the containment, kg
  • P is the absolute pressure in the containment, MPa
  • H is the partial pressure of water vapor in the containment, MPa
  • V is the free volume of the containment, m3
  • T is the average temperature in the containment, K.
  • the overall leakage rate of the containment can be determined by calculating the rate of change of temperature, humidity and pressure respectively. This calculation method can facilitate the analysis of the influence of each parameter in the test process on the final result.
  • the uncertainty includes: Type A uncertainty and Type B uncertainty.
  • the uncertainty of type B can be obtained by experience and analysis of instrument characteristics, and will not be described in detail here.
  • Type A uncertainty includes: temperature standard uncertainty, humidity standard uncertainty, and pressure standard uncertainty.
  • the temperature standard uncertainty can be calculated by the following formula:
  • uT1 is the temperature standard uncertainty, K/h; n is the total number of probes; ⁇ is the standard deviation of the temperature, K/h; ⁇ T is the overall temperature change rate, K/h; ⁇ Ti is the temperature of the ith probe Change gradient, K/h.
  • the humidity standard uncertainty can be calculated by the following formula:
  • the pressure standard uncertainty can be calculated by the following formula:
  • the position of the sensors determines the volume that each sensor can represent. Therefore, the volume weight of each sensor must be considered in the calculation process.
  • the arrangement of the sensors has obvious regional characteristics, which can be arranged according to the layers of the structures in the containment. According to the principle of temperature distribution in the container, in a stable state, the temperature values at the same elevation are close. Therefore, in the test During the process, the temperature data also showed obvious layering phenomenon.
  • the standard uncertainty of temperature, the standard uncertainty of humidity, and the standard uncertainty of pressure are calculated by using the sub-regional fitting method. By using the subregional fitting method, it is not necessary to calculate the volume weight of each temperature sensor separately before the containment test, but only to allocate the volume in the containment according to the level.
  • nj is the number of probes of the jth layer, K/h
  • uTj is the temperature standard uncertainty of the jth layer, K/h.
  • Vj is the free volume of the jth layer of the containment.
  • the temperature sensors in the containment are distributed basically according to the elevation to form specific five areas, and the overall leakage rate of the containment is calculated according to the layered method.
  • the schematic diagram of the internal space partition of the containment is shown in FIG. 3 .
  • T01 to T70 in the figure represent the temperature sensors of each serial number.
  • the containment overall leakage rate measurement module 10 and the containment strength monitoring module 60 may measure the free volume in the containment by the free volume method, and assign weights to the sensors according to the regions where the sensors are located in the containment. . Among them, the assigned weights can be used to calculate the containment leakage rate and evaluate the containment strength.
  • the optimal path refers to the shortest path when the air temperature and humidity exchange convection, rather than the straight-line distance in space.
  • the thick black line is the wall
  • V is the air micro-unit.
  • S1, S2 are measuring instruments
  • P1, P4 represent the straight line path from V to S1, S2 respectively
  • P2+P3 is the shortest path from V around the wall to S2. It can be seen that although P1>P4, P3+P2>P1, so the instrument with the shortest optimal path from V is S1 instead of S2.
  • the optimized A* algorithm or the ant algorithm can be used to find the optimal path.
  • FIG 7 it is the layout diagram of temperature sensors T18, T19 and T30 during the containment pressure test, in which the thick black line is the wall.
  • the straight-line distance between T18 and T30 is 2.28m, and the straight-line distance between T18 and T19 is 7.99m.
  • the temperature curves of these three sensors are shown in Figure 8. It can be seen from Figures 7 and 8 that although the straight-line distance between T18 and T30 is smaller, due to the wall isolation between the two points, the exchange and convection of temperature and humidity are insufficient, and the temperature at T19 is closer to T18 than T30. This phenomenon can be explained by the "optimal path”: the optimal path from T18 to T19 is smaller than the optimal path to T30.
  • the air temperature or temperature at a certain point can be measured by the instrument with the shortest optimal path.
  • calculation module 104 includes: a containment parameter processing module, a containment monitoring data processing module, an optimal path calculation module 104, a volume weight allocation module and a data output module.
  • the containment parameter processing module conducts modeling and meshing according to the containment wall size data to obtain free space grid data; the containment monitoring data processing module performs an instrument coordinate grid based on the position data of the temperature sensor and the position data of the humidity sensor
  • the optimal path calculation module 104 calculates according to the free space grid data and the meter grid data to obtain the optimal path of the area represented by each meter; the volume weight distribution module calculates according to the optimal path , obtain the volume weight of each meter; the data output module outputs the volume weight of each meter. It can be understood that when a certain sensor fails, the representative weight of the sensor can be allocated to one or several surrounding sensors in an automatic or manual manner. That is, when the containment temperature sensor, humidity sensor and pressure sensor fail, the volume weight of the sensor is eliminated, and its weight is distributed to two or more adjacent sensors according to the optimal path.
  • the entire containment leakage rate measurement module 10 further includes: a penetration measurement module 108 .
  • the penetration measurement module 108 is used to measure the tightness of the penetration of the containment, so as to obtain the test result of the sealing of the penetration of the containment.
  • the penetration measurement module 108 includes: a pressure-bearing box, a single-chip microcomputer 1081 , a display module 1082 , a penetration-piece measurement unit 1083 and an actuator 1084 arranged in the pressure box.
  • the penetration measurement unit 1083 collects data and obtains measurement data; the single-chip microcomputer 1081 controls the actuator 1084 according to the test instructions and the measurement data; the actuator 1084 performs work according to the control of the single-chip microcomputer 1081; the display module 1082 seals the penetration of the containment shell The test results are displayed.
  • the penetration measurement unit 1083 includes: a pressure sensor, a temperature sensor, a small flow sensor, a medium flow sensor, and a large flow sensor.
  • the actuator 1084 includes: a first solenoid valve V1 arranged on the input pipeline, a second solenoid valve V2 arranged on the first input branch pipeline, and a second input branch pipeline.
  • the valve V4 the fifth solenoid valve V5 provided on the second sub-pipeline, the sixth solenoid valve V6 provided on the third sub-pipeline, and the ninth solenoid valve V9 provided on the output pipe.
  • first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged in parallel, and the first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged between the first input branch pipe and the first output branch pipe;
  • the pressure sensor and the temperature sensor are arranged between the second input branch pipe and the second output branch pipe, and are used to measure the temperature of the gas in the pipe, which solves the problem that the original solution cannot directly measure the air in the high-pressure pipe.
  • the penetration measurement module 108 further includes: a gas drying filter 1085 disposed on the input pipeline and located outside the pressure-bearing box; the gas drying filter 1085 is used for The gas is dried and filtered.
  • the pressure box is made of stainless steel. By using stainless steel to make the pressure box, its strength can be guaranteed.
  • the accuracy of the temperature sensor is ⁇ 0.5°C
  • the measurement accuracy of the small flow sensor, the medium flow sensor and the large flow sensor is 1%FS
  • the measurement accuracy of the pressure sensor is 1 ⁇ .
  • a maintenance interface and a module calibration interface can be reserved for a pressure sensor, a temperature sensor, and a volume sensor (a small flow sensor, a medium flow sensor, and a large flow sensor).
  • the casing 411 of the pressure-bearing box is designed to be sealed with a penetration piece software, so as to lead the cable out of the casing 411 to connect with the microcontroller 1081 and prevent it from leaking, wherein the pressure-bearing box is connected to the external pipeline through a quick connector, wherein the quick connector And the pressure relief valve and the shell 411 are connected with G1/4 thread to ensure its tightness and easy disassembly and assembly.
  • finite element analysis can be used to simulate the strength of the casing 411, and the optimal size of the casing 411 can be determined on the basis of ensuring safety to ensure portability and safety.
  • FIG. 11 it is a logic diagram of the control operation of the microcontroller 1081 .
  • the tester selects the pressure test method according to the isolation valve to be tested. If it is an inner valve, click the direct flow method button.
  • the single-chip 1081 controls and closes the third solenoid valve V3 and the eighth solenoid valve V8, and opens the first solenoid valve V1, the second solenoid valve V2, and the seventh solenoid valve V7.
  • the gas passes through the single-chip 1081, and the single-chip 1081 measures its volume and volume through the built-in volume sensor. gas temperature.
  • the microcontroller 1081 selects the passage path according to the gas flow.
  • the microcontroller 1081 controls to open the fourth solenoid valve V4 and close the fifth solenoid valve V5 and the sixth solenoid valve V6. If it is within the mid-range range, the single-chip microcomputer controls to open the fifth solenoid valve V5, close the fourth solenoid valve V4 and the sixth solenoid valve V6, and use the medium flow sensor. Otherwise, the microcontroller 1081 controls to open the sixth solenoid valve V6, close the fourth solenoid valve V4 and the fifth solenoid valve V5, and use a large flow sensor. Among them, when the solenoid valve is opened, the timer starts to count. After 15 minutes, the single-chip microcomputer 1081 reads the gas temperature through the temperature sensor, and then displays the converted result on the display module 1082 according to the measurement result of the volume sensor and the gas temperature. superior.
  • the microcontroller 1081 closes the second solenoid valve V2 and the eighth solenoid valve V8, and opens the third solenoid valve V3.
  • the tester clicks the read temperature and pressure button as the initial pressure and initial temperature, and the timer starts timing. When the test is over, click the read temperature and pressure button again. At this time, the microcontroller 1081 reads the temperature and pressure data as the end temperature. and pressure, and calculate the real-time leakage rate, and display the real-time leakage rate through the display module 1082.
  • the containment sound leak detection module 20 includes: a sound acquisition module 201 , a sound monitoring module 202 and a directional transmission module 203 .
  • the containment acoustic measurement module 20 also includes a vibration monitoring module.
  • the sound acquisition module 201 is used to monitor and collect the sound signal of the containment in real time to obtain the sound acquisition signal; the sound monitoring module 202 is used to monitor the sound acquisition signal and output the sound leak detection measurement result of the containment; the directional transmission module 203 uses To output containment audio leak detection measurement results and containment leak location and area.
  • the vibration monitoring module is used to monitor the vibration value of the fixed pipeline and the working state of the valve.
  • the sound monitoring module 202 includes: a signal acquisition module 2021 , a signal analysis module 2022 and a sound amplification module 2023 .
  • the signal collection module 2021 is used to collect the sound collection signal and transmit it to the signal analysis module 2022; the signal analysis module 2022 is used to analyze and filter the sound collection signal to obtain a filtered sound signal, and send the filtered sound signal to the sound amplification module 2023; the sound amplifying module 2023 is used for amplifying the filtered sound signal to obtain the sound leak detection measurement result of the containment.
  • the measurement result of the containment sound leak detection includes: the address of the sound acquisition module 201 and sound data.
  • the sound monitoring module 202 further includes: a storage circuit 2025 and a sound transmission module 2024 .
  • the storage circuit 2025 is used to store the sound data; the sound transmission module 2024 is used to output the address and the sound data of the sound acquisition module 201 to obtain the leak location and area of the containment vessel.
  • the directional transmission module 203 includes: a directional transmission cable; the directional transmission electric cable receives the sound leak detection measurement result of the containment and transmits it to the outside of the containment.
  • the sound transmission module 2024 includes: a wireless transmission module and a wireless reception module; the wireless transmission module is used to receive the address and sound data of the sound acquisition module 201 and send them to the wireless reception module; the wireless reception module is used to receive The address of the sound collection module 201 and the sound data are output.
  • the wireless transmitting module and the wireless receiving module adopt the Zigbee wireless transmission technology, wherein the wireless transmitting module can be realized by a Zigbee router, the wireless receiving is realized by a Zigbee coordinator, and a Zigbee router can be used for sound transmission.
  • the data output by the amplification module 2023 is collected, and all data collection is summarized through the Zigbee coordinator, and then transmitted to the outside of the containment through the directional transmission cable in the containment (generally, it can be transmitted to a safe POE switch outside the containment, and then It is transmitted from the POE switch to the leakage monitoring host computer, where the POE switch also provides power for the Zigbee coordinator and Zigbee router installed in the containment through the electrical penetrations while receiving data).
  • the sound monitoring module 202 also includes: a vibration sensor 2026; the vibration sensor 2026 is used to monitor the vibration displacement of the sound monitoring module 202 and when the vibration displacement of the sound monitoring module 202 is greater than a preset value, the address of the sound monitoring module 202 is sent to the wireless transmitter module.
  • the sound collection module 201 may include multiple sound sensors.
  • sound sensors can be installed on the pipe walls of all containment isolation valves, in the transition cabin of the 0m/8m personnel gate, and at the connection between the equipment gate and the containment steel lining bolts 513, and the The above-mentioned about 120 sound sensors define their sensor addresses according to the number of the penetration part and the elevation number of the personnel gate, so as to ensure that the leak location can be determined at the first time when a leak occurs during the test.
  • the sound monitoring module 202 is in a dormant state.
  • the sound monitoring module 202 starts from dormancy, and the sound acquisition module 201 transmits the measured sound data to the signal analysis module 2022. If The signal analysis module 2022 analyzes the sound frequency greater than 1000HZ, and then sends it to the sound amplification module 2023. The sound amplification module 2023 stores the sensor address and the amplified sound, and transmits the compressed and stored sensor address and sound data to the wireless transmission module. The wireless receiving module is then transmitted out of the containment through the electrical penetration. When the sound frequency collected by the signal collection module 2021 is less than 1000 Hz, the data is directly discarded.
  • the vibration sensor 2026 in the sound monitoring module 202, the displacement of the sound monitoring module 202 can be monitored by the vibration sensor 2026.
  • the vibration sensor 2026 measures that the vibration displacement of the sound monitoring module 202 is greater than 300 ⁇ m, this The address of the module is transmitted to the wireless receiving module through the wireless transmitting module, and then sent out of the containment through the electrical penetration.
  • the system After reaching the 1 bar.g platform, after 1 hour of air standing and absorption, the system is used to conduct acoustic leak detection in the containment.
  • a sound sensor measures the sound of leakage, it outputs a high-level signal to the upper computer.
  • the upper computer determines its position through the sensor address, and further confirms the leakage position at the first time, and then manually conducts manual operation from the isolation valve outside the containment Double check and deal with leaks.
  • the nuclear power plant containment test system further includes: a containment appearance inspection module 30 .
  • the containment appearance inspection module 30 includes a wall climbing robot 301 , a ground station unit 306 , an image acquisition unit 302 , an image acquisition and processing unit 303 , an appearance data transmission unit 304 and a fall prevention device 305 .
  • the containment appearance inspection module 30 further includes: a position confirmation device and a spraying device.
  • the wall-climbing robot 301 is used to perform the walking action on the wall of the containment according to the control instructions; the ground station unit 306 is used to collect the geometric information of the appearance defect image of the containment and analyze and process the image information; the image acquisition unit 302 is used to The wall surface is scanned and photographed to obtain image data of the containment wall; the image acquisition and processing unit 303 is used to collect and analyze the image data to obtain the geometric information of the appearance defect image of the containment; the appearance data transmission unit 304 is used to The geometric information of the appearance defect image is sent to the ground station unit 306; the anti-fall device 305 is used to prevent the wall-climbing robot 301 from falling.
  • the spraying device is used to mark the detected defect information.
  • the position confirmation device is used to record and store the position information of the defect after the robot completes the defect marking.
  • the present invention completes concrete defect identification and defect measurement by carrying a high-resolution camera on the wall-climbing robot 301, and transmits the remote image data back to the ground station unit 306 through a wireless transmission module, and the ground station completes the back-end data processing.
  • the wall-climbing robot 301 can be equipped with a camera to be adsorbed on the concrete surface to complete vertical split-plane walking. At the same time, it carries an image acquisition unit 302 and an appearance data transmission unit 304.
  • the body of the wall-climbing robot 301 also integrates the necessary measurement requirements. Devices, including but not limited to altitude meters, spraying devices, anti-fall devices 305, inclinometers, etc.
  • the anti-fall device 305 can avoid the risk of the robot falling from high altitude and protect the safety of equipment and personnel under abnormal conditions such as equipment failure.
  • the anti-fall device 305 can be implemented by suspending a safety rope above the wall-climbing robot 301 , wherein the other end of the safety rope can be pulled by a test person or a hoist.
  • the wall-climbing robot 301 has excellent wall surface adsorption capacity and bearing capacity, wherein the wall surface adsorption force should not only provide sufficient positive pressure for the robot to travel, but also be able to withstand the interference of strong winds of level 6 or above.
  • the carrying capacity is not less than 1 kg, and it is used to carry cameras and wireless transmission equipment.
  • the spraying device is arranged on the wall-climbing robot 301, so that the wall-climbing robot 301 has a spraying function, and the spraying function is used to mark defects on site.
  • the design of the spraying function is realized by pressing the paint spraying can installed on the robot body by the cam drive mechanism, wherein the spraying instruction can be issued by the ground station unit 306 .
  • the position confirmation device is arranged on the wall-climbing robot 301, so that it has a positioning function, wherein the positioning function of the wall-climbing robot 301 is used to provide defect position information, and the position information is also used for the subsequent compilation of defect data sheets and defect expansion diagrams drawing. Since the wall of the containment vessel is cylindrical, its position information consists of horizontal angle and vertical height.
  • the horizontal angle data is provided by the test personnel, and the vertical height needs to be provided by the robot through the altimeter.
  • the accuracy of the altimeter can reach 0.1 m, and at the same time, in order to reduce the influence of external wind pressure on the measurement accuracy of the altimeter, the altimeter can be designed inside the wall-climbing robot 301 .
  • the image acquisition and processing unit 303 includes: a receiving and sending drive module 3031, a bottom communication module 3032, a host computer interface module 3033, a background operation database module 3034, a background service system module 3035, and a sub-system. Function module 3036.
  • the receiving and sending drive module 3031 is used to convert and transmit the received and received data; the underlying communication module 3032 is used to call, allocate and temporarily store the underlying data; the host computer interface module 3033 is used to display the geometric information of the appearance defect image and receive user input
  • the background operation database module 3034 is used to store the image data of the containment wall and manage user information; the background service system is used to control the operation of the coordination sub-function module 3036.
  • the sub-function module 3036 includes: a control module, a positioning module, a video system module, an image system module, a tool module, a menu module, a document marking module, a retrieval module, a defect drawing module, a storage module, and an algorithm module.
  • the control module is used to integrate and transmit control commands; the positioning module is used to locate and convert the position information of the wall-climbing robot 301 into coordinates corresponding to the position information; the video system module is used to wirelessly transmit the information to the ground station unit 306.
  • the video information in the geometric information of the appearance defect image is encoded and converted into a video stream; the image system module is used to take pictures, enlarge and analyze the image with appearance defects; the tool module is used to provide appearance inspection tools; the menu module is used to control and control The combination of instructions and/or conversion instructions; the document marking module is used to integrate defect data; the retrieval module is used to perform data retrieval and data allocation; the defect drawing module is used to redraw the two-dimensional image geometric information of the appearance defect image; storage module It is used to store the geometric information of the appearance defect image; the algorithm module is used to analyze and calculate the image data of the containment wall surface to obtain the geometric information of the appearance defect image of the containment vessel.
  • visual inspection tools include but are not limited to crack rulers, width rulers, video playback controls, curves, straight lines, areas, and the like.
  • the document markup module integrates information such as crack length, width, location coordinates, time, etc., and can automatically generate an easily identifiable document markup data format.
  • the retrieval module is responsible for the overall data retrieval service and data allocation service in the entire defect detection system, which is equivalent to a data interface. When the defect drawing module completes or partially completes the containment defect detection task, it can automatically redraw the two-dimensional graphics of the cracks and damage information on the containment outer column machine, which is convenient for containment inspection and historical data viewing.
  • each sub-function module 3036 is built into the wall-climbing robot 301 .
  • the nuclear power plant containment test system further includes: a fire monitoring module 40 .
  • the fire monitoring module 40 is used to perform fire monitoring on the containment and output fire monitoring information.
  • the fire monitoring module 40 includes: a plurality of thermal imagers 401 , an electrical penetration piece 402 disposed on the containment, and a transmission cable.
  • the fire monitoring module 40 further includes: a gas sensor and a smoke sensor.
  • a plurality of thermal imagers 401 are used to monitor the temperature in the containment and output fire monitoring information.
  • the transmission cable receives fire monitoring information, gas information and smoke information and transmits it to the outside of the containment through electrical penetrations, and transmits the thermal imager and gas sensor power from outside the containment to the inside of the containment.
  • the variation is less than 1ppm/month, Ensure the stability of the power supply during the test and that there is no power supply in the containment to prevent fire.
  • Gas sensors are used to monitor gas information within the containment.
  • the gas information includes: O 2 , CO 2 , SO 2 , CO and other gas trends; its signal transmission in the containment relies on the branch of the backup sensor connected in parallel to the containment leak rate measurement network.
  • Smoke sensors are used to monitor smoke information inside the containment.
  • the response time of the smoke sensor is less than 2s, and the accuracy is 100ppm.
  • the smoke sensor measures through the gas leakage pipe.
  • each thermal imager 401 is built in a protective cover 4011 , and the protective cover 4011 is a stainless steel protective cover 4011 .
  • the stainless steel protective cover 4011 can withstand a maximum pressure of 10bar.g.
  • a special penetration design can be used, the fixed end is fixed in the gland head, and high temperature sealant is used to seal the gap. , to prevent air leakage of the cable core.
  • the protective cover 4011 includes a casing 411 and a tightness test interface 412 disposed at the bottom of the casing 411 ; the thermal imager 401 is built in the casing 411 and conducts a tightness test through the tightness test interface 412 .
  • the sealing test interface 412 is a G1/4 thread.
  • the panel 415 uses germanium glass, and the infrared transmittance reaches 99%, which makes the thermal imager 401 more stable. Performance is maximized and guaranteed not to be damaged by high pressure air.
  • FIG. 17 it is a schematic structural diagram of the protective cover 4011 .
  • the interior of the protective cover 4011 can be designed to match the shape of the thermal imager 401 , and at the same time, a limit buckle 416 is provided, which can play the role of fixing the thermal imager 401 .
  • the fixing member 413 is used to fix and seal, wherein, the fixing member 413 is filled with high temperature resistant sealant to achieve the purpose of sealing and also to facilitate disassembly.
  • a metric external thread is added.
  • Flat sealing O-type silicone rubber ring fixed with screws to achieve sealing effect.
  • the bottom of the protective cover 4011 is sealed with the side through a special connector 414.
  • the special connector 414 adopts a pressure-proof design similar to a pressure cooker, and the silicone rubber adopts an E-shaped groove. The screw with uniform force is stable to ensure the strength and stability of the seal.
  • the upper part of the panel 415 and the protective cover 4011 are fixed and sealed by a gasket 417, wherein two silicone rubber O-rings can be used to achieve the purpose of double-layer protection and protect the germanium glass at the same time.
  • the gasket 417 is a waterproof gasket 417, which can achieve high temperature resistance, acid resistance and alkali resistance.
  • the panel 415 can use a germanium glass optical lens with an ultra-thick design of 10 mm, so that the infrared transmittance of the thermal imager 401 can reach 99% or more, and the compressive strength can reach more than 10 bar.
  • the nuclear power plant containment test system further includes: a main loop check valve leakage rate monitoring module 50 .
  • the main loop check valve leakage rate monitoring module 50 is used for monitoring the main loop check valve leakage rate and outputting the main loop check valve leakage rate monitoring results, and the results are used to correct the overall leakage rate of the containment.
  • the main circuit check valve leakage rate monitoring module 50 includes a check valve blocking device.
  • the check valve blocking device includes a valve cavity 501, a sealing airbag 508, an axial balance device 5081, a charging unit and a monitoring unit.
  • the charging unit is used to charge the valve cavity 501 of the check valve or the sealing airbag 508; the axial balance device 5081 is used to balance the axial force in the valve cavity 501; the monitoring unit is used to monitor the charging of the check valve.
  • the leakage rate of the check valve is calculated according to the charging data; according to the leakage rate of the check valve, the leakage rate monitoring result of the check valve of the main circuit is output.
  • the charging unit includes: a first charging device and a second charging device; the first charging device is used to pressurize the valve cavity 501 of the check valve and collect pressure data of the valve cavity 501;
  • the second inflating device is used to inflate the airtight airbag 508 and collect pressure data of the airtight airbag 508 .
  • the charging data includes: the pressure data of the valve cavity 501 and the pressure data of the sealing airbag 508;
  • the check valve blocking device further includes: a valve body 51 located at the opening of the valve cavity 501 so that the valve cavity 501 forms a closed space.
  • the valve body 51 has its own bolts 513 .
  • the first inflation device includes: a first inflation air bag 502 , a first valve 503 and a first pressure gauge.
  • the first charging device further includes a charging pipeline 509 of the valve body 51 , wherein one end of the charging pipeline 509 of the valve body 51 is connected to the first inflating air bag 502 through the first quick connector 511 , and the other end is inserted into the valve body of the valve cover 506 for charging Pressure port 5101. Easy to disassemble and maintain.
  • the second inflation device includes: a second inflation air bag 504 , a second valve 505 and a second pressure gauge.
  • the second inflating device further includes: an airbag inflating line 510, the airbag inflating line 510 is connected to the second inflating airbag 504 through a second quick connector 512 at one end, and the other end passes through the airbag inflating port 5102 of the valve cover 506 and is It extends into the valve cavity 501 and is connected to the sealing airbag 508 . It can be easily disassembled and maintained by using the quick connector.
  • the first inflatable airbag 502 is used to inflate the valve cavity 501; the first pressure gauge is used to collect the pressure data of the valve cavity 501 during the inflation of the first inflatable airbag 502;
  • the second inflatable airbag 504 is used to inflate the sealing airbag 508;
  • the second pressure gauge is used to collect the pressure data of the sealing airbag 508 during the inflation of the second inflatable airbag 504;
  • the second valve 505 is used for the second inflation
  • the bladder 504 opens when inflated. It should be noted that the first pressure gauge and the second pressure gauge are not shown in FIG. 18 .
  • the sealing airbag 508 is also provided with a stainless steel protective net 5082.
  • the sealing airbag 508 can be formed into a cylindrical shape when it is not stamped, so as to facilitate the Airbag installation.
  • the air bag inflation and monitoring device is used to inflate and monitor the air bag.
  • the pressure is lower than 1.5 bar.g, the pressure is supplemented, so that the air bag 508 is well sealed with the inner wall of the pipeline, which is used to achieve reverse sealing of the pipeline.
  • the sealing airbag 508 and the test-specific valve cover 506 jointly establish the test closed space.
  • the axial balance device 5081 is used to balance the axial force caused by the gas pressure in the valve cavity 501, so as to prevent the internal pressure of the valve cavity 501 during the test.
  • the axial pressure created by the high pressure gas forces the sealing bladder 508 into the system lines.
  • the tightness of the check valve under test is measured by the pressure gauge on the valve cover 506 .
  • the check valve blocking device is located on the side of the check valve outlet pipeline, and the sealing airbag 508 and the valve cover 506 are connected by a quick joint, which has the advantages of convenient connection, good sealing performance, and real-time monitoring of self-sealing performance and axial balance. and easy installation.
  • the nuclear power plant containment test system further includes: a containment strength monitoring module 60 .
  • the containment strength monitoring module 60 is used to monitor the containment strength and output strength monitoring data.
  • the containment strength monitoring module 60 includes: a strength monitoring data acquisition device 601 , an EAU automatic reading module 602 and a wireless communication module 604 .
  • the strength monitoring data collection device 601 is used to collect the strength data of the containment to obtain the strength monitoring data of the containment; the EAU automatic reading module 602 is used to read and output the monitoring data of the strength of the containment; the wireless communication module 604 is used to read and output the strength monitoring data of the containment. Containment strength monitoring data is transmitted.
  • the intensity monitoring data acquisition device 601 includes, but is not limited to, thermocouples, audio strain gauges, level boxes, and plumb line monitoring equipment. Further, the intensity monitoring data acquisition module 601 may further include: a force gauge and a displacement gauge. Among them, the dynamometer mainly measures the prestress of the containment; the displacement meter corrects and measures the actual settlement of the containment cylinder.
  • the thermocouple is used to collect the thermocouple data to correct the concrete strain during the test, and it is also used to calibrate whether the installation position of the acoustic strain gauge is consistent with the design position; the acoustic strain gauge is used to collect the deformation stress of the containment and obtain the deformation stress data;
  • the level box is used to collect the deformation and displacement of the raft foundation of the containment and obtain the deformation and displacement data of the raft foundation;
  • the plumb line monitoring equipment is used to monitor the cylinder deformation of the containment and obtain the plumb line data.
  • the containment strength monitoring module 60 further includes: a plumb line data collection module 603 .
  • the plumb line data collection module 603 is configured to receive and output plumb line data collected by the plumb line monitoring equipment.
  • the containment strength monitoring module 60 further includes: a displacement gauge and a dynamometer. The displacement meter is connected with the level box and the terrain base point to obtain the relative change data between the geodetic reference point and the containment raft foundation during the test, so as to realize the settlement monitoring of the containment.
  • the dynamometer provides stress monitoring of the containment.
  • the EAU (Containment Permanent Instrumentation) automatic reading module includes: an EAU automatic reading box, a three-way adapter box, and an EAU automatic reading device.
  • the EAU automatic reading box reads the thermocouple data collected by the thermocouple, the deformation stress data collected by the audio strain gauge and the deformation displacement data collected by the level box, and sends the thermocouple data, deformation stress data and deformation displacement data to the tee adapter box;
  • the three-way adapter box receives the deformation displacement data collected by the coordination level box, and transmits the thermocouple data, deformation stress data and deformation displacement data to the EAU automatic reading device;
  • the EAU automatic reading device receives the deformation displacement data collected by the level box. , and send the thermocouple data, deformation stress data and deformation displacement data to the wireless communication module 604 after conversion processing.
  • the deformation stress data, deformation displacement data and thermocouple data collected by the audio frequency strain gauge, level box, displacement gauge and thermocouple can be read by the EAU automatic reading box and transmitted to the three-way adapter box.
  • the three-way adapter box is sent to the multi-channel switching module for channel switching, the corresponding vibrating wire signal and thermocouple signal are acquired by the NI vibrating wire acquisition module and NI thermocouple acquisition module, and then controlled and adjusted by the NI control module and then passed through the conversion module. After conversion, it is sent to the wireless communication module 604, and then sent to the server by the wireless communication module 604.
  • the plumb line data collected by the plumb line monitoring equipment is adopted by the plumb line data acquisition module 603 and transmitted to the wireless communication module 604 through the RS485 bus, and then sent to the server by the wireless communication module 604 .
  • the conversion module converts RS232 data into RS485 data.
  • the EAU automatic reading device further includes: a power supply module for providing electrical energy.
  • the power supply module includes a power polymer lithium battery (optional 12V/80Ah) and a power adapter (AC220 to 12V/5V).
  • the server After receiving the vibrating wire signal, the thermocouple signal and the plumb line data sent by the wireless communication module 604, the server converts the analog signal (the vibrating wire signal, the thermocouple signal and the plumb line data) into a digital signal, and then performs the process.
  • Calculation result 1 is obtained by real-time calculation.
  • the above sensitive areas are carried out.
  • the Young's modulus and Poisson's ratio are fitted and calculated to obtain calculation result 2, as well as the average Young's modulus and Poisson's ratio of the concrete samples during the construction stage.
  • the above results are subjected to data fitting processing to obtain the overall containment during the containment compression test.
  • Deformation, deformation, strain and settlement According to the calculation results, the maximum deformation position, maximum strain and maximum settlement angle of the current containment are displayed, and the temperature and trend of the thermocouple in the same area and the audio frequency strain gauge are compared, and the audio frequency strain in the same area is compared.
  • the strain measured by the gauge is compared with the displacement measured by the plumb line and the level box to ensure that the measurement is true and effective, so that the strength of the containment can be evaluated more intuitively and accurately.
  • the audio frequency strain gauge may include 52 channels
  • the level box may include 13 channels
  • the thermocouple may include 28 channels. Therefore, in the later data processing, it can support the removal of readings with damaged sensors or wrong results. After removing one or more sensor data, the remaining sensors are re-added to the calculation process and the corresponding calculation results are displayed.
  • the server After the data monitored by the containment strength monitoring module 60 is sent to the server through the wireless communication module 604, the server is based on the reference power station test data, the EAU measurement data during the containment construction phase, and the prestressed tension data combined with real-time read wireless communication
  • the test data transmitted by the module 604 is calculated in real time.
  • the radial deformation of the containment is calculated based on the plumb line data, the maximum deformation position and angle are displayed, and the real-time curve of the deformation of the containment with the pressure can be generated; each position is calculated based on the measurement data of the acoustic strain gauge Strain, display the maximum strain position, and generate the curve of each strain of the containment with the pressure; calculate the temperature at each position based on the measurement data of the thermocouple, display the maximum temperature, and generate the real-time temperature change curve of the containment; based on the measurement data of the level box Calculate the settlement of each area of the raft, and generate the curve of the settlement of the raft with the pressure; calculate the settlement of the cylinder based on the measurement data of the convergence meter, and generate the curve of the settlement of the cylinder with the pressure; calculate the prestressed ring gallery based on the measurement data of the dynamometer Settlement data, and generate a curve of settlement versus pressure; based on the Poisson's ratio
  • the variation curves of the strain of the containment with the pressure and the curve of the settlement of the raft foundation with the pressure are compared with each other, and the real-time deformation and stress comparison curves of the containment raft are generated, and the effectiveness of the measurement system is judged according to the change trend of the two.
  • the nuclear power plant containment test system further includes: an outer containment measurement module 70 .
  • the outer containment measuring module 70 measures the tightness of the outer containment and outputs the tightness measurement result.
  • the outer containment measurement module 70 includes: a containment monitoring module 701 , a flow controller 702 , a collector 703 and an industrial computer 704 .
  • the containment monitoring module 701 is used to collect the gas information of the outer containment; the flow controller 702 is used to control the injection flow and collect the flow data; the collector 703 collects the outer containment data and the flow data and sends it to the industrial computer 704; The industrial computer 704 analyzes and processes the outer containment data and flow data, and outputs the sealing measurement result.
  • the gas information of the outer containment vessel includes, but is not limited to, gas temperature, gas humidity, pressure, air volume, volume, and the like.
  • the outer containment measurement module 70 further includes: a display 705; the display 705 receives and displays the sealing measurement result.
  • the EPR nuclear power unit adopts a double-layer containment design.
  • the inner containment is a post-tensioned prestressed concrete structure with a 6mm-thick steel lining, and the cylinder wall thickness is 1300mm.
  • the outer containment is a reinforced concrete structure with a thickness of 1300mm.
  • the thickness of the outer wall of the exposed part of the outer containment and the surrounding fuel workshop and safety workshop is 1800mm.
  • a ring corridor with a width of 1800mm is formed between the inner and outer containment, and the ring corridor maintains negative pressure through the ring corridor ventilation system (EDE).
  • EEE ring corridor ventilation system
  • the containment leakage monitoring system (EPP) can collect trace amounts of radioactive substances leaked from personnel gates, equipment gates, fuel transfer channel isolation valves, etc. Filters and iodine adsorbers are filtered and discharged to the chimney to limit the release of radioactive materials to the environment. Therefore, the outer containment vessel needs to be tested for tightness during commissioning.
  • the leakage rate of the outer containment is measured by using a large-volume confined space under unsteady working conditions. That is, before the outer containment test, the negative pressure of the ring gallery is pumped to above -2000Pa. After reaching the test pressure, the pumping fan is stopped to isolate the outer containment ring gallery, and the gas parameters in the ring gallery are dynamically measured during the leakage process. By fitting a large amount of data, the functional relationship between the leakage and the differential pressure is obtained, and then the leakage rate under the design pressure is obtained.
  • the leakage rate Qpei of the outer containment under a certain pressure difference is the difference between the total leakage Qeee and the injection flow rate Qinj.
  • a process in which the negative pressure is drawn and the internal and external pressures are balanced is called a pressure cycle.
  • several pressure cycles are required to inject quantitative dry air into the ring gallery.
  • the injected dry air served as the reference leak during the test.
  • the flow rate of each injection is a fixed value between 10 and 20 m 3 /h.
  • the test requires at least 1 pressure cycle without dry air injection and at least 2 pressure cycles with dry air injection as a verification comparison.
  • the determination principle of "constant pressure drop at a constant speed" is used for determination. Specifically, in the process of measurement data analysis, if the following two conditions are met at the same time, it can be considered that the leakage rate of the ring corridor in the 60-minute period can be determined by using the gas parameter gradient method (the gas state satisfies the "homogeneous beam pressure drop steady state") calculate:
  • the gas in the corridor meets the requirement of "uniform change", that is, the linear fitting degree r 2 ⁇ 0.95 when the gas temperature and pressure data are linearly fitted to the time within 30 minutes.
  • the nuclear power plant containment test system further includes: a containment bulge measurement module 80 .
  • the containment bulge measurement module 80 is used to measure the bulge in the containment and output the bulge measurement result.
  • the containment wrapping measurement module 80 includes: a containment wrapping measure unit 801 , a containment wrapping data transmission unit 802 and a containment wrapping data processing unit 803 .
  • the containment bulge measurement module 80 further includes: a containment bulge positioning unit.
  • the containment bulge positioning unit is used to locate and mark the defect position of the containment bulge.
  • the containment bulge measurement unit 801 is used to collect the containment bulge and output the bulge acquisition signal; the containment defect data transmission unit receives and transmits the bulge acquisition signal; the containment bulge data processing unit 803 processes the bulge acquisition signal and outputs the bulge measurement result.
  • the containment bulge measurement unit 801 includes: a slide rail 811 , a bracket 812 , a pan/tilt 813 , a laser distance sensor 814 and a ranging encoder 815 arranged on the pan/tilt 813 .
  • the containment bulge measurement unit 801 further includes: a positioning device.
  • the laser distance sensor 814 is used to measure the distance between the steel lining and the slide rail 811 (that is, the y-coordinate of the bulge curve)
  • the ranging encoder 815 is used to measure the x-coordinate of the laser distance sensor 814 (that is, the x-coordinate of the bulge curve). coordinate).
  • the measurement period of the laser distance sensor 814 is lower than 0.02s, and the measurement distance accuracy is better than 0.3mm.
  • the measurement period of the ranging encoder 815 is less than 0.01s, and the measurement angle accuracy is 0.5°.
  • the positioning device is set on the PTZ, which can be composed of an altimeter and an inclinometer, and is used to record the position of the steel lining of the containment shell where the marked bulge is located.
  • the bracket 812 includes a first support column 8121 and a second support column 8122 .
  • the first end of the first support column 8121 is fixed at one end of the containment shell, and the second end of the first support column 8121 is connected to the sliding rail 811 .
  • the first end is connected; the first end of the second support column 8122 is fixed on the other end of the containment, the second end of the second support column 8122 is connected with the second end of the slide rail 811 ; the pan/tilt 813 is slidably arranged on the slide rail 811 .
  • the safe shell data transmission unit 802 includes: a data communication module 821 and a power supply unit 822 .
  • the data communication module 821 is connected with the containment bulge measurement unit 801 to receive the bulge acquisition signal and transmit it to the containment bulge data processing unit 803; the power supply unit 822 is used to process the laser distance sensor 814, the distance encoder 815 and the containment bulge data Unit 803 is powered.
  • the data communication module 821 is composed of a MAX485 serial port module and a UART2 unit of the microcontroller, so as to realize the communication between the sensor and the microcontroller.
  • the containment bulge data processing unit 803 includes: a comparison module 831, a comparison analysis compensation module 832, and a result output module 833; the comparison module 831 is used to perform comparison processing on the bulge acquisition signal, and output bulge measurement data; comparative analysis The compensation module 832 is configured to calculate the measurement data of the bulge in combination with the compensation data to obtain the measurement result of the bulge.
  • the safety shell data processing unit 803 may be a single chip microcomputer.
  • the single chip chip may also be provided with a test interface for testing, and an ISP interface for ISP data transmission.
  • the containment defect measurement module further includes: a display unit 804; the display unit 804 is used to display the measurement result of the bulge.
  • the display unit 804 includes a liquid crystal display screen and/or a digital display tube.
  • the containment defect measurement module further includes: a transmission unit, which sends the bulge measurement result to the containment strength monitoring module for correcting containment strength monitoring.
  • the nuclear power plant containment test system of the embodiment of the present invention solves the problems of large error in the appearance inspection test of the containment and high risk of falling from high altitude; the fire monitoring is not timely in the high-pressure dark environment, and the fire location and fire scale cannot be located; the internal view of the containment Check the problems of low measurement accuracy of the bulge, poor anti-interference ability, and high requirements for operators; the leakage rate of the double-layer containment enclosure cannot be directly measured due to the too small internal and external pressure difference; the problem of large error in the algorithm of the leakage rate of the inner containment;
  • the sealing test of the check valve is subject to the problem of the state of the unit; the leakage rate error of the mechanical penetration test due to the inability to directly measure the temperature; the problem that the charging and discharging rate cannot be directly controlled during the charging and discharging of the existing test; the existing test In the scheme, the data acquisition rate of the strength evaluation requirements is low, real-time measurement is impossible, the strength evaluation is not intuitive, and it is impossible to track the evolution of
  • the automatic identification and processing of the appearance defects of the containment can be realized, the test method of the check valve and the required specific window are optimized, the measurement accuracy of the steel lining bulge is improved, and the leakage rate of the containment and its required specific window are improved.
  • the algorithm of uncertain measurement further improves the weight distribution of the containment volume and the calculation method of the leakage rate, and solves the problem of untimely fire monitoring in the nuclear island powerhouse under the high pressure environment, improving the safety and efficiency of the test.

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Abstract

A system for testing a containment building of a nuclear power plant, the system comprising: a containment building overall leakage rate measurement module (10), a containment building acoustic leakage detection module (20), an alarm module (100), and a display module (90). The containment building overall leakage rate measurement module (10) is used to measure the overall leakage rate in a containment building and perform calculation on measured data to obtain the real-time overall leakage rate of the containment building and the degree of uncertainty; the containment building acoustic leakage detection module (20) is used to monitor sound signals of the containment building and output containment building acoustic leakage detection measurement results after analyzing and processing the monitored sound signals; the alarm module (100) outputs a corresponding alarm signal in the case of the real-time overall leakage rate, the degree of uncertainty, and containment building acoustic leakage; and the display module (90) displays the measurement results of the real-time overall leakage rate, the degree of uncertainty, and the containment building acoustic leakage.

Description

一种核电站安全壳试验系统A nuclear power plant containment test system 技术领域technical field
本发明涉及核电站安全壳打压试验的技术领域，更具体地说，涉及一种核电站安全壳试验系统。The invention relates to the technical field of nuclear power plant containment pressure test, and more particularly, to a nuclear power plant containment test system.
背景技术Background technique
核电厂安全壳为预应力钢筋混凝土结构，其竖向和水平方向分别设置有预应力钢束。安全壳是继核燃料包壳、一回路压力壳之后的第三道安全屏障，扮演着限制放射性物质从反应堆扩散至大气的重要角色，其建造质量将直接影响到安全壳本体的功能完整性。其功能是当一回路管道发生破裂、造成失水事故时，将事故中的裂变产生限制和消除在其内部，确保社会环境和公众的安全。因此，在机组投运前需进行安全壳试验(CTT)，以验证安全壳的强度及密封性。The nuclear power plant containment is a prestressed reinforced concrete structure with prestressed steel bundles arranged in the vertical and horizontal directions respectively. The containment is the third safety barrier after the nuclear fuel cladding and the primary circuit pressure vessel. It plays an important role in restricting the diffusion of radioactive substances from the reactor to the atmosphere. Its construction quality will directly affect the functional integrity of the containment body. Its function is to limit and eliminate the fission in the accident when the primary circuit pipeline ruptures and causes a water loss accident, so as to ensure the safety of the social environment and the public. Therefore, a containment test (CTT) is required before the unit is put into operation to verify the strength and tightness of the containment.
原有试验方案实施时质量和效率显现出明显的滞后和不足。The quality and efficiency of the original test plan showed obvious lags and deficiencies.
例如，对于安全壳整体泄漏率测量方面，现有的安全壳打压试验的核心之一即是泄漏率试验，其涉及到试验期间温度、湿度和压力数据的连续采集和拟合计算，属于高精度计算范畴，由于其特殊性，必须采用专门的技术规范和算法进行处理，开发专门的数据采集与处理软件方能满足要求。然而，随着目前堆型经过多年的吸收引进后，原各传感器算法已无法满足要求，进而导致安全壳整体泄漏率误差偏大。For example, for the measurement of the overall leakage rate of the containment, one of the cores of the existing containment pressure test is the leakage rate test, which involves the continuous acquisition and fitting calculation of temperature, humidity and pressure data during the test, which is a high-precision The computing category, due to its particularity, must be processed with special technical specifications and algorithms, and special data acquisition and processing software can be developed to meet the requirements. However, after years of absorption and introduction of the current reactor type, the original sensor algorithms have been unable to meet the requirements, resulting in a large error in the overall leakage rate of the containment.
另外，现有的安全壳打压试验期间，无法对安全壳音响进行泄漏测量，当发现泄漏时，无法定位泄漏位置，进而降低试验结果可靠性。In addition, during the current containment pressure test, the leak measurement of the containment sound cannot be performed, and when a leak is found, the leak location cannot be located, thereby reducing the reliability of the test result.
发明内容SUMMARY OF THE INVENTION
本发明要解决的技术问题在于，针对现有技术的上述缺陷，提供一种核 电站安全壳试验系统。The technical problem to be solved by the present invention is to provide a nuclear power plant containment test system aiming at the above-mentioned defects of the prior art.
本发明解决其技术问题所采用的技术方案是：构造一种核电站安全壳试验系统，包括：安全壳整体泄漏率测量模块、安全壳音响测漏模块、报警模块以及显示模块；The technical scheme adopted by the present invention to solve the technical problem is: constructing a nuclear power plant containment test system, including: a containment overall leakage rate measurement module, a containment sound leak detection module, an alarm module and a display module;
所述安全壳整体泄漏率测量模块用于对安全壳内的总体泄漏率进行测量并对测量数据进行计算，获得安全壳的实时整体泄漏率和不确定度；The containment overall leakage rate measurement module is used to measure the overall leakage rate in the containment and calculate the measurement data to obtain the real-time overall leakage rate and uncertainty of the containment;
所述安全壳音响测漏模块用于对安全壳的声音信号进行监测并对所监测到的声音信号进行分析处理后，输出安全壳音响测漏测量结果，以获得安全壳泄漏位置及区域；The containment sound leak detection module is used to monitor the sound signal of the containment and analyze and process the monitored sound signal, and then output the containment sound leak detection measurement result to obtain the containment leak location and area;
所述报警模块用于在所述实时整体泄漏率、所述不确定度、所述安全壳音响泄漏时，输出相应的报警信号；The alarm module is configured to output a corresponding alarm signal when the real-time overall leakage rate, the uncertainty, and the containment sound leak;
所述显示模块用于对所述实时整体泄漏率、所述不确定度和所述安全壳音响测漏测量结果进行显示。The display module is configured to display the real-time overall leak rate, the uncertainty and the measurement result of the containment acoustic leak detection.
在本发明所述的核电站安全壳试验系统中，所述安全壳整体泄漏率测量模块包括：泄漏率测量装置、压力调节模块、压力运行模块以及计算模块；In the nuclear power plant containment test system of the present invention, the overall containment leak rate measurement module includes: a leak rate measurement device, a pressure regulation module, a pressure operation module, and a calculation module;
所述泄漏率测量装置用于对安全壳泄漏信号参数进行实时采集，基于所述安全壳泄漏信号参数获得泄漏数据，并对所述泄漏数据进行实时计算以获得计算结果，以及在所述计算结果满足气体稳定条件后计算实时泄漏率及其不确定度；The leakage rate measuring device is used to collect the parameters of the containment leakage signal in real time, obtain leakage data based on the parameters of the containment leakage signal, and perform real-time calculation on the leakage data to obtain a calculation result, and in the calculation result Calculate the real-time leak rate and its uncertainty after satisfying the gas stability conditions;
所述压力调节模块用于对泄漏采集信号进行实时拟合计算处理，获得实时升压速度和实时降压速度，以及在所述实时升压速度和实时降压速度大于预设数值时，控制升降压电动调节阀开度；The pressure regulation module is used to perform real-time fitting and calculation processing on the leakage acquisition signal, obtain the real-time pressure increase speed and the real-time pressure reduction speed, and control the pressure increase when the real-time pressure increase speed and the real-time pressure reduction speed are greater than the preset values. The opening of the step-down electric regulating valve;
所述压力运行模块用于在压力达到阈值时，控制关闭升降压电动调节阀，对安全壳内的所有参量进行监测并进行实时计算；The pressure operation module is used to control and close the buck-boost electric regulating valve when the pressure reaches the threshold value, and monitor all parameters in the containment and perform real-time calculation;
所述计算模块用于根据所述泄漏采集信号进行计算，获得安全壳的实时整体泄漏率和不确定度。The calculation module is configured to perform calculation according to the leak acquisition signal to obtain the real-time overall leak rate and uncertainty of the containment.
在本发明所述的核电站安全壳试验系统中，所述安全壳整体泄漏率测量模块还包括：数据仿真模块和数据显示模块；In the nuclear power plant containment test system of the present invention, the containment overall leakage rate measurement module further includes: a data simulation module and a data display module;
所述数据仿真模块用于在安全壳试验前对所述安全壳整体泄漏率测量模块的功能进行模拟仿真，获得仿真数据；The data simulation module is used for simulating the function of the overall leakage rate measurement module of the containment to obtain simulation data before the containment test;
所述数据显示模块用于对所述安全壳的状态信息和工作信息。The data display module is used for the status information and working information of the containment shell.
在本发明所述的核电站安全壳试验系统中，所述安全壳整体泄漏率测量模块还包括：存储与打印模块；In the nuclear power plant containment test system of the present invention, the containment overall leakage rate measurement module further includes: a storage and printing module;
所述存储与打印模块用于对所述安全壳的实时整体泄漏率和不确定度进行存储并打印输出。The storage and printing module is used for storing and printing out the real-time overall leakage rate and uncertainty of the containment vessel.
在本发明所述的核电站安全壳试验系统中，所述不确定度包括：A类不确定度和B类不确定度；所述A类不确定度包括：温度标准不确定度、湿度标准不确定度以及压力标准不确定度；所述温度标准不确定度采用采用分区域拟合法计算；In the nuclear power plant containment test system of the present invention, the uncertainty includes: type A uncertainty and type B uncertainty; the type A uncertainty includes: temperature standard uncertainty, humidity standard uncertainty Certainty and pressure standard uncertainty; the temperature standard uncertainty is calculated using the subregional fitting method;
所述湿度标准不确定度和所述压力标准不确定度采用分区域拟合算法计算。The humidity standard uncertainty and the pressure standard uncertainty are calculated using a subregional fitting algorithm.
在本发明所述的核电站安全壳试验系统中，所述安全壳整体泄漏率测量模块还包括：贯穿件测量模块；In the nuclear power plant containment test system of the present invention, the containment overall leakage rate measurement module further includes: a penetration measurement module;
所述贯穿件测量模块用于对所述安全壳的贯穿件的密封性进行测量，以获得所述安全壳的贯穿件的密封性测试结果。The penetration measurement module is used for measuring the tightness of the penetration of the containment, so as to obtain the sealing test result of the penetration of the containment.
在本发明所述的核电站安全壳试验系统中，所述贯穿件测量模块包括：承压箱、单片机、显示器、设置在所述承压箱中的贯穿件测量单元和执行器；In the nuclear power plant containment test system according to the present invention, the penetration measurement module includes: a pressure-bearing box, a single-chip microcomputer, a display, a penetration measurement unit and an actuator arranged in the pressure-bearing box;
所述贯穿件测量单元进行数据采集并获得测量数据；The penetration measurement unit performs data acquisition and obtains measurement data;
所述单片机根据试验指令以及测量数据控制所述执行器；The single-chip microcomputer controls the actuator according to the test instruction and the measurement data;
所述执行器根据所述单片机的控制执行工作；The executor performs work according to the control of the single-chip microcomputer;
所述显示器对所述安全壳的贯穿件的密封性测试结果进行显示。The display displays the result of the tightness test of the penetration of the containment.
在本发明所述的核电站安全壳试验系统中，所述贯穿件测量单元包括：压力传感器、温度传感器、小流量传感器、中流量传感器以及大流量传感器；所述执行器包括：设置在输入管道上的第一电磁阀、设置在第一输入支管道上的第二电磁阀、设置在第二输入支管道上的第三电磁阀、设置在第一 输出支管道上的第七电磁阀、设置在第二输出支管道上的第八电磁阀、设置在第一子管道上的第四电磁阀、设置在第二子管道上的第五电磁阀、设置在第三子管道上的第六电磁阀以及设置在输出管道上的第九电磁阀；In the nuclear power plant containment test system of the present invention, the penetration measurement unit includes: a pressure sensor, a temperature sensor, a small flow sensor, a medium flow sensor and a large flow sensor; the actuator includes: provided on the input pipeline The first solenoid valve, the second solenoid valve set on the first input branch pipeline, the third solenoid valve set on the second input branch pipeline, the seventh solenoid valve set on the first output branch pipeline, the The eighth solenoid valve on the second output branch pipe, the fourth solenoid valve on the first sub-pipe, the fifth solenoid valve on the second sub-pipe, and the sixth solenoid valve on the third sub-pipe and the ninth solenoid valve arranged on the output pipeline;
所述第一子管道、所述第二子管道以及所述第三子管道并行设置，且所述第一子管道、所述第二子管道以及所述第三子管道设置在所述第一输入支管道和所述第一输出支管道之间；The first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged in parallel, and the first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged in the first sub-pipeline between the input branch pipe and the first output branch pipe;
所述压力传感器和所述温度传感器设置在所述第二输入支管道和所述第二输出支管道之间；the pressure sensor and the temperature sensor are arranged between the second input branch pipe and the second output branch pipe;
在本发明所述的核电站安全壳试验系统中，所述贯穿件测量模块还包括：设置在所述输入管道上且位于所述承压箱外的气体干燥过滤器；In the nuclear power plant containment test system of the present invention, the penetration measurement module further includes: a gas drying filter disposed on the input pipeline and located outside the pressure-containing box;
所述气体干燥过滤器用于对输入所述承压箱内的气体进行干燥过滤。The gas drying filter is used for drying and filtering the gas input into the pressure-holding box.
在本发明所述的核电站安全壳试验系统中，所述安全壳整体泄漏率测量模块和安全壳强度监测模块通过自由容积法测量安全壳自由容积，并根据安全壳内的传感器所在区域对传感器进行权重分配。In the nuclear power plant containment test system of the present invention, the containment overall leakage rate measurement module and the containment strength monitoring module measure the free volume of the containment by the free volume method, and perform the sensor test according to the area where the sensor in the containment is located. Weight distribution.
在本发明所述的核电站安全壳试验系统中，所述计算模块包括：安全壳参数处理模块、安全壳监测数据处理模块、最优路径计算模块、体积权重分配模块以及数据输出模块；In the nuclear power plant containment test system of the present invention, the calculation module includes: a containment parameter processing module, a containment monitoring data processing module, an optimal path calculation module, a volume weight distribution module, and a data output module;
所述安全壳参数处理模块根据安全壳墙体尺寸数据进行建模、网格划分，获得自由空间网格数据；The containment parameter processing module performs modeling and grid division according to the containment wall size data to obtain free space grid data;
所述安全壳监测数据处理模块根据温度传感器的位置数据和湿度传感器的位置数据进行仪表坐标网格化，获得仪表网格数据；The containment monitoring data processing module performs grid coordinate gridization of the instrument according to the position data of the temperature sensor and the position data of the humidity sensor, and obtains the grid data of the instrument;
所述最优路径计算模块根据所述自由空间网格数据和所述仪表网格数据进行计算，获得每个仪表的最优路径；The optimal path calculation module calculates according to the free space grid data and the meter grid data to obtain the optimal path of each meter;
所述体积权重分配模块根据所述最优路径进行计算，获得每个仪表体积权重；The volume weight allocation module calculates according to the optimal path to obtain the volume weight of each meter;
所述数据输出模块输出所述每个仪表体积权重。The data output module outputs the weight of each meter volume.
在本发明所述的核电站安全壳试验系统中，所述安全壳音响测漏模块包括：声音采集模块、声音监测模块、振动监测模块以及定向传输模块；In the nuclear power plant containment test system of the present invention, the containment acoustic leak detection module includes: a sound acquisition module, a sound monitoring module, a vibration monitoring module and a directional transmission module;
所述声音采集模块用于对安全壳的声音信号进行实时监测并采集，获得声音采集信号；The sound collection module is used for real-time monitoring and collection of the sound signal of the containment to obtain the sound collection signal;
所述声音监测模块用于对所述声音采集信号进行监测并输出安全壳音响测漏测量结果；The sound monitoring module is used for monitoring the sound collection signal and outputting the sound leak detection measurement result of the containment;
所述振动监测模块用于监测固定管道的振动数值以及阀门的工作状态；The vibration monitoring module is used to monitor the vibration value of the fixed pipeline and the working state of the valve;
所述定向传输模块用于输出所述安全壳音响测漏测量结果和安全壳泄漏位置及区域。The directional transmission module is used for outputting the measurement result of the containment acoustic leak detection and the containment leak location and area.
在本发明所述的核电站安全壳试验系统中，所述声音监测模块包括：信号采集模块、信号分析模块以及声音放大模块；In the nuclear power plant containment test system of the present invention, the sound monitoring module includes: a signal acquisition module, a signal analysis module and a sound amplification module;
所述信号采集模块用于对所述声音采集信号进行采集并传送给所述信号分析模块；The signal acquisition module is used to collect the sound acquisition signal and transmit it to the signal analysis module;
所述信号分析模块用于对所述声音采集信号进行分析过滤，以获得过滤声音信号，并将所述过滤声音信号发送给所述声音放大模块；The signal analysis module is configured to analyze and filter the sound acquisition signal to obtain a filtered sound signal, and send the filtered sound signal to the sound amplification module;
所述声音放大模块用于对所述过滤声音信号进行放大处理，获得安全壳音响测漏测量结果。The sound amplifying module is used for amplifying the filtered sound signal to obtain the sound leak detection measurement result of the containment vessel.
在本发明所述的核电站安全壳试验系统中，所述安全壳音响测漏测量结果包括：声音采集模块地址和声音数据；In the nuclear power plant containment test system of the present invention, the containment sound leak detection measurement result includes: sound acquisition module address and sound data;
所述声音监测模块还包括：存储电路和声音传输模块；The sound monitoring module further includes: a storage circuit and a sound transmission module;
所述存储电路用于对所述声音数据进行存储；the storage circuit is used for storing the sound data;
所述声音传输模块用于将所述声音采集模块地址和所述声音数据输出，以获得所述安全壳泄漏位置及区域。The sound transmission module is used for outputting the address of the sound acquisition module and the sound data to obtain the leak location and area of the containment vessel.
在本发明所述的核电站安全壳试验系统中，所述声音传输模块包括：无线发射模块和无线接收模块；In the nuclear power plant containment test system of the present invention, the sound transmission module includes: a wireless transmitting module and a wireless receiving module;
所述无线发射模块用于接收所述声音采集模块地址和所述声音数据并发送给所述无线接收模块；The wireless transmitting module is configured to receive the address of the sound acquisition module and the sound data and send them to the wireless receiving module;
所述无线接收模块用于接收所述声音采集模块地址和所述声音数据并输出。The wireless receiving module is used for receiving and outputting the address of the sound collecting module and the sound data.
在本发明所述的核电站安全壳试验系统中，所述声音监测模块还包括： 振动传感器；In the nuclear power plant containment test system of the present invention, the sound monitoring module further includes: a vibration sensor;
所述振动传感器用于监测所述声音监测模块的振动位移并在所述声音监测模块的振动位移大于预设值时，将声音监测模块的地址发送给所述无线发射模块。The vibration sensor is used to monitor the vibration displacement of the sound monitoring module and send the address of the sound monitoring module to the wireless transmitting module when the vibration displacement of the sound monitoring module is greater than a preset value.
在本发明所述的核电站安全壳试验系统中，所述定向传输模块包括：定向传输电缆；In the nuclear power plant containment test system of the present invention, the directional transmission module includes: a directional transmission cable;
所述定向传输电线缆接收所述安全壳音响测漏测量结果并传输至安全壳外。The directional transmission cable receives the containment acoustic leak detection measurement and transmits it to the outside of the containment.
在本发明所述的核电站安全壳试验系统中，还包括：安全壳外观检查模块；The nuclear power plant containment test system of the present invention further includes: a containment appearance inspection module;
所述安全壳外观检查模块包括：爬壁机器人、地面站单元、图像获取单元、图像采集处理单元、外观数据传输单元、位置确认装置、喷涂装置以及防坠落装置；The containment appearance inspection module includes: a wall climbing robot, a ground station unit, an image acquisition unit, an image acquisition and processing unit, an appearance data transmission unit, a position confirmation device, a spraying device and an anti-fall device;
所述爬壁机器人用于根据控制指令执行在安全壳壁面的行走动作；The wall-climbing robot is used to perform the walking action on the wall of the containment according to the control instruction;
所述地面站单元用于收集所述安全壳的外观缺陷图像几何信息并对所述图像信息进行分析处理；The ground station unit is used to collect the geometric information of the appearance defect image of the containment vessel and analyze and process the image information;
所述图像获取单元用于对所述安全壳壁面进行扫描和拍照以获得所述安全壳壁面的图像数据；The image acquisition unit is configured to scan and photograph the containment wall to obtain image data of the containment wall;
所述图像采集处理单元用于对所述图像数据进行采集和分析，获得所述安全壳的外观缺陷图像几何信息；The image acquisition and processing unit is configured to collect and analyze the image data to obtain the geometric information of the appearance defect image of the containment vessel;
所述外观数据传输单元用于将所述安全壳的外观缺陷图像几何信息发送给所述地面站单元；The appearance data transmission unit is configured to send the geometric information of the appearance defect image of the containment to the ground station unit;
所述喷涂装置用于对检测到的缺陷信息进行标记。The spraying device is used for marking the detected defect information.
位置确认装置用于在机器人完成缺陷标记后记录并存储该缺陷的位置信息；The position confirmation device is used to record and store the position information of the defect after the robot completes the defect marking;
所述防坠落装置用于防止所述爬壁机器人坠落。The anti-fall device is used to prevent the wall-climbing robot from falling.
在本发明所述的核电站安全壳试验系统中，所述图像采集处理单元包括：接收和发送驱动模块、底层通讯模块、上位机界面模块、后台运行数据 库模块、后台服务系统模块以及子功能模块；In the nuclear power plant containment test system of the present invention, the image acquisition and processing unit includes: a receiving and sending drive module, a bottom communication module, a host computer interface module, a background operation database module, a background service system module and a sub-function module;
所述接收和发送驱动模块用于将收发数据进行转换并传送；The receiving and sending drive modules are used to convert and transmit the received and received data;
所述底层通讯模块用于对底层数据进行调用分配暂存；The underlying communication module is used for calling, distributing and temporarily storing underlying data;
所述上位机界面模块用于对所述外观缺陷图像信息进行显示以及接收用户输入的操作信息；The host computer interface module is used for displaying the appearance defect image information and receiving the operation information input by the user;
所述后台运行数据库模块用于对所述安全壳壁面的图像数据进行存储以及对用户信息进行管理；The background operation database module is used to store the image data of the containment wall and manage user information;
所述后台服务系统用于控制协调所述子功能模块的运行。The background service system is used for controlling and coordinating the operation of the sub-function modules.
在本发明所述的核电站安全壳试验系统中，所述子功能模块包括：控制模块、定位模块、视频系统模块、图像系统模块、工具模块、菜单模块、文档标记模块、检索模块、缺陷绘制模块、存储模块以及算法模块；In the nuclear power plant containment test system of the present invention, the sub-function modules include: a control module, a positioning module, a video system module, an image system module, a tool module, a menu module, a document marking module, a retrieval module, and a defect drawing module , storage module and algorithm module;
所述控制模块用于对控制命令进行整合及传递；The control module is used to integrate and transmit control commands;
所述定位模块用于对所述爬壁机器人的位置信息进行定位并转换为与所述位置信息对应的坐标；The positioning module is used for positioning and converting the position information of the wall-climbing robot into coordinates corresponding to the position information;
所述视频系统模块用于将无线传送至所述地面站单元的外观缺陷图像信息中的视频信息进行编码并转换为视频流；The video system module is used to encode and convert the video information in the appearance defect image information wirelessly transmitted to the ground station unit into a video stream;
所述图像系统模块用于对带有外观缺陷的图像进行拍照放大及分析；The image system module is used for photographing, magnifying and analyzing images with appearance defects;
所述工具模块用于提供外观检查工具；The tool module is used to provide a visual inspection tool;
所述菜单模块用于与控制指令和/或转换指令结合；The menu module is used to combine with control instructions and/or conversion instructions;
所述文档标记模块用于将缺陷数据进行整合；The document marking module is used to integrate defect data;
所述检索模块用于进行数据检索及数据调配；The retrieval module is used for data retrieval and data allocation;
所述缺陷绘制模块用于将外观缺陷图像信息进行二维图像重绘；The defect drawing module is used to redraw the two-dimensional image of the appearance defect image information;
所述存储模块用于对所述外观缺陷图像信息进行存储；The storage module is used for storing the appearance defect image information;
所述算法模块用于对所述安全壳壁面的图像数据进行缺陷识别分析计算，获得所述安全壳的外观缺陷图像几何信息。The algorithm module is used to perform defect identification, analysis and calculation on the image data of the containment wall surface, and obtain the geometric information of the appearance defect image of the containment vessel.
在本发明所述的核电站安全壳试验系统中，还包括：火灾监测模块；In the nuclear power plant containment test system of the present invention, it further comprises: a fire monitoring module;
所述火灾监测模块用于对安全壳进行火灾监测并输出火灾监测信息。The fire monitoring module is used for carrying out fire monitoring on the containment and outputting fire monitoring information.
在本发明所述的核电站安全壳试验系统中，所述火灾监测模块包括：多 个热像仪、气体传感器、烟雾传感器、设置在安全壳上的电气贯穿件以及传输线缆；In the nuclear power plant containment test system of the present invention, the fire monitoring module includes: a plurality of thermal imagers, gas sensors, smoke sensors, electrical penetrations arranged on the containment, and transmission cables;
所述多个热像仪用于对安全壳内的温度进行监测并输出火灾监测信息；The plurality of thermal imagers are used for monitoring the temperature in the containment and outputting fire monitoring information;
所述气体传感器用于监测安全壳内的气体信息；The gas sensor is used for monitoring gas information in the containment;
所述烟雾传感器用于监测安全壳内的烟雾信息；The smoke sensor is used for monitoring smoke information in the containment;
所述传输线缆接收所述火灾监测信息、气体信息和烟雾信息并通过所述电气贯穿件传输至所述安全壳外，以及将所述热像仪和气体传感器电源由安全壳外传输至安全壳内。The transmission cable receives the fire monitoring information, gas information and smoke information and transmits it to the outside of the containment through the electrical penetration, and transmits the thermal imager and gas sensor power from outside the containment to the safety inside the shell.
在本发明所述的核电站安全壳试验系统中，每一个所述热像仪内置于防护罩中，所述防护罩为不锈钢防护罩；所述烟雾传感器通过气体引漏管进行测量。In the nuclear power plant containment test system of the present invention, each of the thermal imagers is built into a protective cover, and the protective cover is a stainless steel protective cover; the smoke sensor measures through a gas leakage pipe.
在本发明所述的核电站安全壳试验系统中，所述防护罩包括外壳以及设置在所述外壳底部的密封性试验接口；所述热像仪内置于所述外壳中并通过所述密封性试验接口进行密封性试验。In the nuclear power plant containment test system of the present invention, the protective cover includes an outer shell and a sealing test interface disposed at the bottom of the outer shell; the thermal imager is built in the outer shell and passes the sealing test The interface is tested for tightness.
在本发明所述的核电站安全壳试验系统中，还包括：主回路逆止阀泄漏率监测模块；In the nuclear power plant containment test system of the present invention, it further comprises: a main circuit check valve leakage rate monitoring module;
所述主回路逆止阀泄漏率监测模块用于对主回路逆止阀泄漏率进行监测并输出主回路逆止阀泄漏率监测结果。The main loop check valve leakage rate monitoring module is used for monitoring the main loop check valve leakage rate and outputting the main loop check valve leakage rate monitoring results.
在本发明所述的核电站安全壳试验系统中，所述主回路逆止阀泄漏率监测模块包括：逆止阀封堵装置；所述逆止阀封堵装置包括阀腔，密封气囊、轴向平衡装置、充压单元以及监测单元；In the nuclear power plant containment test system of the present invention, the leakage rate monitoring module of the check valve of the main circuit includes: a check valve blocking device; the check valve blocking device includes a valve cavity, a sealing airbag, an axial Balance device, charging unit and monitoring unit;
所述充压单元用于向所述逆止阀的阀腔内充压或者所述密封气囊充压；The charging unit is used for charging the valve cavity of the check valve or the sealing airbag;
所述轴向平衡装置用于平衡所述阀腔内的轴向力；The axial balance device is used to balance the axial force in the valve cavity;
所述监测单元用于监测所述逆止阀的充压数据，根据所述充压数据计算所述逆止阀的泄漏率；The monitoring unit is used to monitor the charging data of the check valve, and calculate the leakage rate of the check valve according to the charging data;
根据所述逆止阀的泄漏率输出主回路逆止阀泄漏率监测结果。According to the leakage rate of the check valve, the leakage rate monitoring result of the check valve of the main circuit is output.
在本发明所述的核电站安全壳试验系统中，所述充压单元包括：第一充压装置和第二充压装置；In the nuclear power plant containment test system of the present invention, the charging unit includes: a first charging device and a second charging device;
所述第一充压装置用于向所述逆止阀的阀腔内充压并采集阀腔的压力数据；The first pressurizing device is used to pressurize the valve cavity of the check valve and collect pressure data of the valve cavity;
所述第二充压装置用于向所述密封气囊充压并采集密封气囊的压力数据。The second inflating device is used for inflating the sealing airbag and collecting pressure data of the sealing airbag.
在本发明所述的核电站安全壳试验系统中，所述充压数据包括：所述阀腔的压力数据和所述密封气囊的压力数据；In the nuclear power plant containment test system of the present invention, the charging data includes: the pressure data of the valve cavity and the pressure data of the sealed airbag;
所述第一充压装置包括：第一充气气囊、第一阀门以及第一压力表；所述第二充压装置包括：第二充气气囊、第二阀门以及第二压力表；The first inflating device includes: a first inflatable air bag, a first valve and a first pressure gauge; the second inflatable device includes: a second inflatable air bag, a second valve and a second pressure gauge;
所述第一充气气囊用于向所述阀腔内充压；the first inflatable air bag is used to inflate the valve cavity;
所述第一压力表用于在所述第一充气气囊充压过程中采集所述阀腔的压力数据；the first pressure gauge is used to collect pressure data of the valve cavity during the inflation of the first inflatable airbag;
所述第一阀门在所述第一充气气囊充压时打开；the first valve is opened when the first inflatable air bag is inflated;
所述第二充气气囊用于向所述密封气囊充压；the second inflatable airbag is used to inflate the sealing airbag;
所述第二压力表用于在所述第二充气气囊充压过程中采集所述密封气囊的压力数据；The second pressure gauge is used to collect pressure data of the sealed airbag during the inflation of the second inflatable airbag;
所述第二阀门在所述第二充气气囊充压时打开。The second valve opens when the second inflation bladder is inflated.
在本发明所述的核电站安全壳试验系统中，所述逆止阀封堵装置还包括：位于所述阀腔开口处以使所述阀腔形成密闭空间的阀盖。In the nuclear power plant containment test system of the present invention, the check valve blocking device further comprises: a valve cover located at the opening of the valve cavity so that the valve cavity forms a closed space.
在本发明所述的核电站安全壳试验系统中，所述逆止阀封堵装置还包括：位于所述阀腔内以平衡阀腔内的轴向力的轴向平衡装置。In the nuclear power plant containment test system of the present invention, the check valve blocking device further comprises: an axial balance device located in the valve cavity to balance the axial force in the valve cavity.
在本发明所述的核电站安全壳试验系统中，还包括：安全壳强度监测模块；The nuclear power plant containment test system of the present invention further includes: a containment strength monitoring module;
所述安全壳强度监测模块用于对所述安全壳强度进行监测并输出强度监测数据。The containment strength monitoring module is used for monitoring the strength of the containment and outputting strength monitoring data.
在本发明所述的核电站安全壳试验系统中，所述安全壳强度监测模块包括：强度监测数据采集装置、EAU自动读数模块以及无线通信模块；In the nuclear power plant containment test system of the present invention, the containment strength monitoring module includes: a strength monitoring data acquisition device, an EAU automatic reading module and a wireless communication module;
所述强度监测数据采集装置用于对安全壳的强度数据进行采集，获得安全壳强度监测数据；The strength monitoring data acquisition device is used for collecting the strength data of the containment to obtain the strength monitoring data of the containment;
所述EAU自动读数模块用于对所述安全壳强度监测数据进行读取并输出；The EAU automatic reading module is used to read and output the containment strength monitoring data;
所述无线通信模块用于对所述安全壳强度监测数据进行传输。The wireless communication module is used for transmitting the monitoring data of the containment strength.
在本发明所述的核电站安全壳试验系统中，所述强度监测数据采集装置包括：热电偶、声频应变计、水准盒、变位计以及铅垂线监测设备；In the nuclear power plant containment test system of the present invention, the strength monitoring data acquisition device includes: a thermocouple, an audio frequency strain gauge, a level box, a displacement gauge, and a plumb line monitoring device;
所述热电偶用于采集热电偶数据；The thermocouple is used to collect thermocouple data;
所述声频应变计用于采集安全壳的形变应力并获得形变应力数据；The audio frequency strain gauge is used to collect the deformation stress of the containment and obtain the deformation stress data;
所述水准盒用于采集安全壳的变形位移并获得变形位移数据；The level box is used to collect the deformation displacement of the containment and obtain the deformation displacement data;
所述变位计连接所述水准盒和地形基准点，用于获得大地基准点和安全壳筏基之间在试验期间的相对变化数据；The displacement gauge is connected to the level box and the terrain reference point, and is used to obtain relative change data between the geodetic reference point and the containment raft during the test;
所述铅垂线监测设备用于监测安全壳的铅垂线形变并获得铅垂线数据。The plumb line monitoring device is used to monitor plumb line deformation of the containment and obtain plumb line data.
在本发明所述的核电站安全壳试验系统中，所述安全壳强度监测模块还包括：铅垂线数据采集模块；In the nuclear power plant containment test system of the present invention, the containment strength monitoring module further includes: a plumb line data acquisition module;
所述铅垂线数据采集模块用于接收所述铅垂线监测设备采集的铅垂线数据并输出。The plumb line data acquisition module is used for receiving and outputting plumb line data collected by the plumb line monitoring equipment.
在本发明所述的核电站安全壳试验系统中，所述EAU自动计数模块包括：EAU自动读数箱、三通适配箱以及EAU自动读数装置；In the nuclear power plant containment test system of the present invention, the EAU automatic counting module includes: an EAU automatic reading box, a three-way adapter box and an EAU automatic reading device;
所述EAU自动读数箱读取所述热电偶采集的热电偶数据、所述声频应变计采集的形变应力数据以及所述水准盒采集的变形位移数据，并将所述热电偶数据、所述形变应力数据和所述变形位移数据发送给所述三通适配箱；The EAU automatic reading box reads the thermocouple data collected by the thermocouple, the deformation stress data collected by the audio frequency strain gauge, and the deformation displacement data collected by the level box, and converts the thermocouple data, the deformation The stress data and the deformation displacement data are sent to the three-way adapter box;
所述三通适配箱接收协调所述水准盒采集的变形位移数据，并将所述热电偶数据、所述形变应力数据和所述变形位移数据并传送至所述EAU自动读数装置；The three-way adapter box receives and coordinates the deformation displacement data collected by the level box, and transmits the thermocouple data, the deformation stress data and the deformation displacement data to the EAU automatic reading device;
所述EAU自动读数装置接收所述水准盒采集的变形位移数据，并将所述热电偶数据、所述形变应力数据和所述变形位移数据并进行转换处理后发送给所述无线通信模块。The EAU automatic reading device receives the deformation displacement data collected by the level box, and sends the thermocouple data, the deformation stress data and the deformation displacement data to the wireless communication module after conversion processing.
在本发明所述的核电站安全壳试验系统中，还包括：外层安全壳测量模块；In the nuclear power plant containment test system of the present invention, it further comprises: an outer containment measurement module;
所述外层安全壳测量模块对外层安全壳密封性进行测量并输出密封性测量结果。The outer containment measuring module measures the tightness of the outer containment and outputs the tightness measurement result.
在本发明所述的核电站安全壳试验系统中，所述外层安全壳测量模块包括：安全壳监测模块、流量控制器、采集器以及工控机；In the nuclear power plant containment test system of the present invention, the outer containment measurement module includes: a containment monitoring module, a flow controller, a collector and an industrial computer;
所述安全壳监测模块用于采集外层安全壳的气体信息；The containment monitoring module is used for collecting gas information of the outer containment;
所述流量控制器用于控制注入流量并采集流量数据；The flow controller is used to control the injection flow and collect flow data;
所述采集器对所述外层安全壳数据和所述流量数据进行采集并发送给所述工控机；The collector collects the outer containment data and the flow data and sends the data to the industrial computer;
所述工控机对所述外层安全壳数据、所述流量数据进行分析处理，并输出所述密封性测量结果。The industrial computer analyzes and processes the outer containment data and the flow data, and outputs the tightness measurement result.
在本发明所述的核电站安全壳试验系统中，所述外层安全壳测量模块还包括：显示器；In the nuclear power plant containment test system of the present invention, the outer containment measurement module further comprises: a display;
所述显示器接收所述密封性测量结果并显示。The display receives and displays the tightness measurement.
在本发明所述的核电站安全壳试验系统中，还包括：安全壳鼓包测量模块；The nuclear power plant containment test system of the present invention further comprises: a containment bulge measurement module;
所述安全壳鼓包测量模块用于对安全壳内的鼓包进行测量并输出鼓包测量结果。The containment bulge measurement module is used to measure the bulge in the containment and output the bulge measurement result.
在本发明所述的核电站安全壳试验系统中，所述安全壳鼓包测量模块包括：安全壳鼓包定位单元、安全壳鼓包测量单元、安全壳鼓包数据传输单元以及安全壳鼓包数据处理单元；In the nuclear power plant containment test system of the present invention, the containment bulge measurement module includes: a containment bulge positioning unit, a containment bulge measurement unit, a containment bulge data transmission unit, and a containment bulge data processing unit;
所述安全壳鼓包定位单元用于对安全壳鼓包缺陷位置进行定位及标记；The containment bulge positioning unit is used to locate and mark the defect position of the containment bulge;
所述安全壳鼓包测量单元用于对安全壳鼓包进行采集并输出鼓包采集信号；The containment bulge measurement unit is used to collect the containment bulge and output the bulge acquisition signal;
所述安全壳缺陷数据传输单元接收并传输所述鼓包采集信号；The containment defect data transmission unit receives and transmits the bulge acquisition signal;
所述安全壳鼓包数据处理单元对所述鼓包采集信号进行处理并输出鼓包测量结果。The containment bulge data processing unit processes the bulge acquisition signal and outputs the bulge measurement result.
在本发明所述的核电站安全壳试验系统中，所述安全壳鼓包测量单元包括：定位装置、滑轨、支架、云台、设置在所述云台上的激光距离传感器以 及测距编码器；In the nuclear power plant containment test system of the present invention, the containment bulge measurement unit includes: a positioning device, a slide rail, a bracket, a pan/tilt, a laser distance sensor and a ranging encoder arranged on the pan/tilt;
所述支架包括第一支撑柱和第二支撑柱，所述第一支撑柱的第一端固定在所述安全壳一端，所述第一支撑柱的第二端与所述滑轨的第一端连接；所述第二支撑柱的第一端固定在所述安全壳另一端，所述第二支撑柱的第二端与所述滑轨的第二端连接；所述云台滑动设置在所述滑轨上；The bracket includes a first support column and a second support column, the first end of the first support column is fixed at one end of the containment, and the second end of the first support column is connected to the first end of the slide rail. The first end of the second support column is fixed on the other end of the containment shell, and the second end of the second support column is connected with the second end of the slide rail; the pan/tilt is slidably arranged at the on the slide rail;
所述定位装置设置在所述云台上。The positioning device is arranged on the pan/tilt.
在本发明所述的核电站安全壳试验系统中，所述安全壳鼓包数据传输单元包括：数据通讯模块以及供电单元；In the nuclear power plant containment test system of the present invention, the containment bulge data transmission unit includes: a data communication module and a power supply unit;
所述数据通讯模块与所述安全壳鼓包测量单元连接以接收所述鼓包采集信号并传送给所述安全壳鼓包数据处理单元；The data communication module is connected with the containment bulge measurement unit to receive the bulge acquisition signal and transmit it to the containment bulge data processing unit;
所述供电单元用于给所述激光距离传感器、所述测距编码器和所述安全壳鼓包数据处理单元供电。The power supply unit is used for supplying power to the laser distance sensor, the distance measuring encoder and the safe shell bulging data processing unit.
在本发明所述的核电站安全壳试验系统中，所述安全壳鼓包数据处理单元包括：对比模块、对比分析补偿、结果输出模块；In the nuclear power plant containment test system of the present invention, the containment bulge data processing unit includes: a comparison module, a comparison analysis compensation, and a result output module;
所述对比模块用于对所述鼓包采集信号进行对比处理，输出鼓包测量数据；The comparison module is used to compare and process the bulge acquisition signal, and output the bulge measurement data;
所述对比分析补偿用于结合补偿数据对所述鼓包测量数据进行计算，获得鼓包测量结果。The comparative analysis compensation is used to calculate the bulge measurement data in combination with the compensation data to obtain a bulge measurement result.
在本发明所述的核电站安全壳试验系统中，所述安全壳缺陷测量模块还包括：显示单元；In the nuclear power plant containment test system of the present invention, the containment defect measurement module further comprises: a display unit;
所述显示单元用于对所述鼓包测量结果进行显示；The display unit is used for displaying the measurement result of the bulge;
所述传输单元将所述鼓包测量结果发送给所述安全壳强度监测模块用于修正安全壳强度监测。The transmission unit sends the bulge measurement result to the containment strength monitoring module for correcting containment strength monitoring.
实施本发明的核电站安全壳试验系统，具有以下有益效果：包括：安全壳整体泄漏率测量模块、安全壳音响测漏模块、报警模块以及显示模块；安全壳整体泄漏率测量模块用于对安全壳内的总体泄漏率进行测量并对测量数据进行计算，获得安全壳的实时整体泄漏率和不确定度；安全壳音响测漏模块用于对安全壳的声音信号进行监测并对所监测到的声音信号进行分析处理 后，输出安全壳音响测漏测量结果；报警模块用于在实时整体泄漏率、不确定度、安全壳音响泄漏时，输出相应的报警信号；显示模块用于对实时整体泄漏率、不确定度和安全壳音响测漏测量结果进行显示。本发明可准确测量安全壳整体泄漏率、精度高，且还能通过音响检测安全壳是否泄漏，提升密封性试验的可靠性。Implementing the nuclear power plant containment test system of the present invention has the following beneficial effects: comprising: a containment overall leak rate measurement module, a containment sound leak detection module, an alarm module and a display module; the containment overall leak rate measurement module is used for the containment Measure and calculate the overall leak rate in the containment to obtain the real-time overall leak rate and uncertainty of the containment; the containment sound leak detection module is used to monitor the sound signal of the containment and monitor the sound After the signal is analyzed and processed, the measurement result of the containment sound leak detection is output; the alarm module is used to output the corresponding alarm signal when the real-time overall leak rate, uncertainty, and containment sound leak; the display module is used to monitor the real-time overall leak rate , uncertainty and containment acoustic leak detection measurement results are displayed. The invention can accurately measure the overall leakage rate of the containment, has high precision, and can detect whether the containment leaks through sound, thereby improving the reliability of the sealing test.
附图说明Description of drawings
下面将结合附图及实施例对本发明作进一步说明，附图中：The present invention will be further described below in conjunction with the accompanying drawings and embodiments, in which:
图1是本发明实施例提供的核电站安全壳试验系统的原理框图；1 is a schematic block diagram of a nuclear power plant containment test system provided by an embodiment of the present invention;
图2是本发明安全壳整体泄漏率测量模块的原理框图；Fig. 2 is the principle block diagram of the overall leakage rate measurement module of the containment of the present invention;
图3是本发明安全壳内部空间分区示意图；Fig. 3 is the schematic diagram of the inner space partition of the containment of the present invention;
图4是本发明安全壳内温度与标高关系曲线示意图；4 is a schematic diagram of the relationship between temperature and elevation in the containment of the present invention;
图5是本发明安全壳内温度与标高关系曲线示意图；5 is a schematic diagram of the relationship between temperature and elevation in the containment of the present invention;
图6是本最优路径示意图；Figure 6 is a schematic diagram of the optimal path;
图7是本发明某试验温度传感器T18/T19/T30布置图；Fig. 7 is the layout diagram of a test temperature sensor T18/T19/T30 of the present invention;
图8是本发明某试验温度传感器T18/T19/T30温度曲线示意图；8 is a schematic diagram of the temperature curve of a certain test temperature sensor T18/T19/T30 of the present invention;
图9是本发明贯穿件测量模块原理框图；Fig. 9 is the principle block diagram of the penetration measurement module of the present invention;
图10是本发明贯穿件测量模块平面示意图；10 is a schematic plan view of the penetration measurement module of the present invention;
图11是本发明单片机控制工作逻辑图；Fig. 11 is the control work logic diagram of the single-chip microcomputer of the present invention;
图12是本发明安全壳音响测漏模块原理框图；Fig. 12 is the principle block diagram of the containment sound leak detection module of the present invention;
图13是本发明声音监测模块原理框图；Fig. 13 is the sound monitoring module principle block diagram of the present invention;
图14是本发明安全平方米外观检查模块原理框图；Fig. 14 is the principle block diagram of the safety square meter appearance inspection module of the present invention;
图15是本发明图像采集处理单元原理框图；15 is a schematic block diagram of an image acquisition and processing unit of the present invention;
图16是本发明火灾监测模块结构示意图；16 is a schematic structural diagram of a fire monitoring module of the present invention;
图17是本发明热像仪的防护罩结构示意图；17 is a schematic structural diagram of a protective cover of the thermal imager of the present invention;
图18是本发明逆止阀封堵装置结构示意图；18 is a schematic structural diagram of the check valve blocking device of the present invention;
图19是本发明安全壳强度监测模块原理框图；19 is a schematic block diagram of the containment strength monitoring module of the present invention;
图20是本发明强度数据处理流程图；Fig. 20 is the intensity data processing flow chart of the present invention;
图21是本发明外层安全壳测量模块原理框图；Fig. 21 is the principle block diagram of the outer containment measurement module of the present invention;
图22是本发明外层安全壳泄漏来源示意图；Figure 22 is a schematic diagram of the leakage source of the outer containment of the present invention;
图23是本发明安全壳鼓包测量模块原理框图；Fig. 23 is the principle block diagram of the containment bulge measurement module of the present invention;
图24是本发明安全壳鼓包测量模块结构示意图。Figure 24 is a schematic structural diagram of the containment bulge measurement module of the present invention.
具体实施方式Detailed ways
为了对本发明的技术特征、目的和效果有更加清楚的理解，现对照附图详细说明本发明的具体实施方式。In order to have a clearer understanding of the technical features, objects and effects of the present invention, the specific embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
参考图1，图1为本发明实施例提供的核电站安全壳试验系统的原理框图。Referring to FIG. 1 , FIG. 1 is a schematic block diagram of a nuclear power plant containment test system provided by an embodiment of the present invention.
该核电站安全壳试验系统自动采集安全壳混凝土内相关传感器信号，并对采集到的数据进行分类、计算、剔除，然后结合建造期间的混凝土数据进行安全壳整体性能评价。The nuclear power plant containment test system automatically collects relevant sensor signals in the containment concrete, and classifies, calculates, and eliminates the collected data, and then evaluates the overall performance of the containment based on the concrete data during construction.
如图1所示，该核电站安全壳试验系统包括：安全壳整体泄漏率测量模块10、安全壳音响测漏模块20、报警模块100以及显示模块90。As shown in FIG. 1 , the nuclear power plant containment test system includes: a containment overall leak rate measurement module 10 , a containment acoustic leak detection module 20 , an alarm module 100 and a display module 90 .
其中，安全壳整体泄漏率测量模块10用于对安全壳内的总体泄漏率进行测量并对测量数据进行计算，获得安全壳的实时整体泄漏率和不确定度。安全壳音响测漏模块20用于对安全壳的声音信号进行监测并对所监测到的声音信号进行分析处理后，输出安全壳音响测漏测量结果，以获得安全壳泄漏位置及区域；报警模块100用于在实时整体泄漏率、不确定度、安全壳音响泄漏时，输出相应的报警信号；显示模块90用于对实时整体泄漏率、不确定度和安全壳音响测漏测量结果进行显示。Wherein, the overall leakage rate measurement module 10 of the containment is used to measure the overall leakage rate in the containment and calculate the measurement data to obtain the real-time overall leakage rate and uncertainty of the containment. The containment sound leak detection module 20 is used to monitor the sound signal of the containment and analyze and process the monitored sound signal, and then output the containment sound leak detection measurement result to obtain the containment leak location and area; the alarm module 100 is used to output a corresponding alarm signal when the real-time overall leak rate, uncertainty, and containment sound leak; the display module 90 is used to display the real-time overall leak rate, uncertainty, and containment sound leak detection measurement results.
一些实施例中，如图2所示，该安全壳整体泄漏率测量模块10包括：泄漏率测量装置101、压力调节模块102、压力运行模块103以及计算模块104。In some embodiments, as shown in FIG. 2 , the entire containment leak rate measurement module 10 includes: a leak rate measurement device 101 , a pressure adjustment module 102 , a pressure operation module 103 and a calculation module 104 .
泄漏率测量装置101用于对安全壳泄漏信号参数进行实时采集，基于所获得的安全过泄漏信号参数获得泄漏数据，并对泄漏数据进行实时计算以获得计算结果，以及在计算结果满足气体稳定条件后计算实时泄漏率和不确定 度。压力调节模块102用于对泄漏采集信号进行实时拟合计算处理，获得实时升压速度和实时降压速度，以及在实时升压速度和实时降压速度大于预设数值时，控制升降压电动调节阀开度。即，当实时升压速度大于预设数值/或者实时降压速度大于预设数值时，控制升降压电动调节阀的开度；压力运行模块103用于在压力达到阈值时，控制关闭升降压电动调节阀，对安全壳内的所有参量进行监测并进行实时计算。其中，压力达到阈值为压力大于或者等于阈值。计算模块104用于根据泄漏采集信号进行计算，获得安全壳的实时整体泄漏率和不确定度。The leak rate measurement device 101 is used for real-time collection of containment leakage signal parameters, to obtain leakage data based on the obtained safety over-leakage signal parameters, and to perform real-time calculation on the leakage data to obtain a calculation result, and when the calculation result satisfies the gas stability condition The real-time leak rate and uncertainty are then calculated. The pressure adjustment module 102 is used to perform real-time fitting and calculation processing on the leakage acquisition signal, obtain the real-time pressure increase speed and the real-time pressure reduction speed, and control the buck-boost electric motor when the real-time pressure increase speed and the real-time pressure reduction speed are greater than the preset values. Adjust valve opening. That is, when the real-time boosting speed is greater than the preset value/or the real-time depressurizing speed is greater than the preset value, control the opening degree of the boosting and boosting electric regulating valve; the pressure operation module 103 is configured to control the closing of the boosting and boosting when the pressure reaches the threshold value The electric regulating valve is used to monitor and calculate all the parameters in the containment in real time. Wherein, the pressure reaching the threshold is that the pressure is greater than or equal to the threshold. The calculation module 104 is configured to perform calculation according to the leakage acquisition signal to obtain the real-time overall leakage rate and uncertainty of the containment.
具体的，气体稳定条件为：Specifically, the gas stability conditions are:
L 2h与L 1h之差的绝对值小于或等于0.25L a,，其中L 2h:两小时泄漏率，L 1h：1小时泄漏率，La:安全壳设计最大泄漏率限值。 The absolute value of the difference between L 2h and L 1h is less than or equal to 0.25L a , where L 2h : two-hour leak rate, L 1h : 1-hour leak rate, and La: the design maximum leak rate limit of the containment.
可选的，该泄漏率测量装置101包括但不限于设置在安全壳内的多个温度传感器(一般可设置59个左右)、多个湿度传感器(一般可设置9个左右)以及多个压力传感器(一般可设置3个左右)。因此，基于各个传感器测量得到的数据可进行相应的调节控制。Optionally, the leak rate measuring device 101 includes but is not limited to a plurality of temperature sensors (generally about 59 can be set), a plurality of humidity sensors (generally about 9 can be set) and a plurality of pressure sensors arranged in the containment. (Generally, about 3 can be set). Therefore, corresponding adjustment control can be performed based on the data measured by each sensor.
具体的，压力调节模块102一般用于升压平台初期压力调节，主要对压力变送器的数据进行实时处理，同时计算出实时的升压速率或者降压速率，并对所得到的升压速率或者降压速率进行实时显示，以及存储与打印。Specifically, the pressure adjustment module 102 is generally used for the initial pressure adjustment of the pressure boosting platform, and mainly performs real-time processing on the data of the pressure transmitter, calculates the real-time pressure increase rate or pressure reduction rate at the same time, and analyzes the obtained pressure increase rate. Or the depressurization rate can be displayed in real time, as well as stored and printed.
压力运行模块103一般为在压力调节模块102将压力调节至阈值时，对安全壳内所有的参量进行监控，同时实时计算当前的升压速率或者降压速率。The pressure operation module 103 generally monitors all parameters in the containment when the pressure adjustment module 102 adjusts the pressure to a threshold value, and simultaneously calculates the current pressure increase rate or pressure decrease rate in real time.
可选的，该计算模块104为离线计算模块104，其可以参考安全壳试验的原始数据或者安全壳试验的当前试验数据计算安全壳的整体泄漏率和不确定度。Optionally, the calculation module 104 is an offline calculation module 104, which can calculate the overall leakage rate and uncertainty of the containment with reference to the original data of the containment test or the current test data of the containment test.
进一步地，如图2所示，该安全壳整体泄漏率测量模块10还包括：数据仿真模块105和数据显示模块106。数据仿真模块105用于对安全壳整体泄漏率测量模块10的功能进行模拟仿真，获得仿真数据。通过所获得的仿真数据可以验证泄漏率测量系统及测量网络的稳定性及其精度是否满足试验要求。 数据显示模块106用于对安全壳的状态信息和工作信息进行显示。其中，安全壳的状态信息包括：实时整体泄漏率、不确定度、仿真数据、升降压实时数据(升压速度/速率，降压速度/速率)、各个传感器的实时测量数据。工作信息包括：安全壳的当前工作状态。Further, as shown in FIG. 2 , the whole containment leakage rate measurement module 10 further includes: a data simulation module 105 and a data display module 106 . The data simulation module 105 is used for simulating the function of the overall leakage rate measurement module 10 of the containment to obtain simulation data. The obtained simulation data can verify whether the stability and accuracy of the leak rate measurement system and measurement network meet the test requirements. The data display module 106 is used for displaying the status information and working information of the containment vessel. Among them, the status information of the containment includes: real-time overall leak rate, uncertainty, simulation data, real-time buck-boost data (boost speed/rate, buck speed/rate), and real-time measurement data of each sensor. The working information includes: the current working status of the containment.
进一步地，一些实施例中，该安全壳整体泄漏率测量模块10还包括：存储与打印模块107；存储与打印模块107用于对安全壳的实时整体泄漏率和不确定度进行存储并打印输出。Further, in some embodiments, the overall leakage rate measurement module 10 of the containment further includes: a storage and printing module 107; the storage and printing module 107 is configured to store and print out the real-time overall leakage rate and uncertainty of the containment .
具体的，数据仿真模块105主要用于模拟整个安全壳整体泄漏率采集的功能，同时也具有离线数据仿真功能。数据显示模块106以数据和/或图表的方式实时显示当前数据及变化趋势。存储与打印模块107将实时数据按照规定格式存储于数据库中并打印出相应的报表。Specifically, the data simulation module 105 is mainly used to simulate the function of collecting the overall leakage rate of the entire containment, and also has an offline data simulation function. The data display module 106 displays current data and change trends in real time in the form of data and/or graphs. The storage and printing module 107 stores the real-time data in the database according to the specified format and prints out the corresponding report.
可选的，本发明实施例中，该安全壳整体泄漏率测量模块10为基于PXI(多路复用器)的安全壳泄漏率测量模块。Optionally, in this embodiment of the present invention, the entire containment leak rate measurement module 10 is a containment leak rate measurement module based on a PXI (multiplexer).
本发明实施例中，安全壳整体泄漏率的计算可基于绝对法，即通过计算安全壳内干空气质量的变化来推导泄漏率。In the embodiment of the present invention, the calculation of the overall leakage rate of the containment can be based on the absolute method, that is, the leakage rate is derived by calculating the change of the dry air quality in the containment.
具体的，根据理想气体状态方程，安全壳内干空气总质量为：Specifically, according to the ideal gas equation of state, the total mass of dry air in the containment is:
Figure PCTCN2022087188-appb-000001
Figure PCTCN2022087188-appb-000001
式中：M为安全壳内干空气的质量，kg；P为安全壳内的绝对压力，MPa；H为安全壳内的水蒸气分压，MPa；V为安全壳的自由容积，m3；R为干空气的理想气体常数，R＝287.14J/(kg·K)；T为安全壳内平均温度，K。Where: M is the mass of dry air in the containment, kg; P is the absolute pressure in the containment, MPa; H is the partial pressure of water vapor in the containment, MPa; V is the free volume of the containment, m3; R is the ideal gas constant of dry air, R=287.14J/(kg·K); T is the average temperature in the containment, K.
对式(1)进行转换，安全壳整体泄漏率的表达式为：Converting formula (1), the expression of the overall leakage rate of the containment is:
Figure PCTCN2022087188-appb-000002
Figure PCTCN2022087188-appb-000002
式中：△M为安全壳内干空气的质量的变化量，kg；M0为试验初始阶段的安全壳干空气质量，kg；△P为安全壳内的绝对压力的变化值，MPa；(P－H)0为安全壳内的干空气分压，MPa；△H为安全壳内的水蒸气分压的变化值，MPa；△T为安全壳内平均温度的变化值，K；T0为试验初始阶段的安 全壳平均温度，K。In the formula: △M is the change in the mass of the dry air in the containment, kg; M0 is the dry air mass of the containment at the initial stage of the test, kg; △P is the change in the absolute pressure in the containment, MPa; (P -H)0 is the dry air partial pressure in the containment, MPa; △H is the change value of the water vapor partial pressure in the containment, MPa; △T is the change of the average temperature in the containment, K; T0 is the test The average temperature of the containment at the initial stage, K.
由上式可知，通过分别计算温度、湿度、压力的变化率，可以确定安全壳的整体泄漏率。该计算方式可以方便分析试验过程中每一个参数对于最终结果的影响。It can be seen from the above formula that the overall leakage rate of the containment can be determined by calculating the rate of change of temperature, humidity and pressure respectively. This calculation method can facilitate the analysis of the influence of each parameter in the test process on the final result.
进一步地，一些实施例中，不确定度包括：A类不确定度和B类不确定度。其中，B类不确定度可以通过经验及仪特性分析得到，在些不再详述。Further, in some embodiments, the uncertainty includes: Type A uncertainty and Type B uncertainty. Among them, the uncertainty of type B can be obtained by experience and analysis of instrument characteristics, and will not be described in detail here.
可选的，A类不确定度包括：温度标准不确定度、湿度标准不确定度以及压力标准不确定度。Optionally, Type A uncertainty includes: temperature standard uncertainty, humidity standard uncertainty, and pressure standard uncertainty.
其中，温度标准不确定度可通过下式计算得到：Among them, the temperature standard uncertainty can be calculated by the following formula:
Figure PCTCN2022087188-appb-000003
Figure PCTCN2022087188-appb-000003
式中：uT1为温度标准不确定度，K/h；n为探头总数；σ为温度的标准差，K/h；πT为总体温度变化率，K/h；πTi为第i个探头的温度变化梯度，K/h。In the formula: uT1 is the temperature standard uncertainty, K/h; n is the total number of probes; σ is the standard deviation of the temperature, K/h; πT is the overall temperature change rate, K/h; πTi is the temperature of the ith probe Change gradient, K/h.
湿度标准不确定度可通过下式计算得到：The humidity standard uncertainty can be calculated by the following formula:
Figure PCTCN2022087188-appb-000004
Figure PCTCN2022087188-appb-000004
式中：uH1为A类湿度不确定度，Pa/h；πHi为第i个探头的湿度变化梯度，Pa/h；πH为平均湿度变化梯度，Pa/h；n为探头的总数量。In the formula: uH1 is the type A humidity uncertainty, Pa/h; πHi is the humidity gradient of the ith probe, Pa/h; πH is the average humidity gradient, Pa/h; n is the total number of probes.
压力标准不确定度可通过下式计算得到：The pressure standard uncertainty can be calculated by the following formula:
Figure PCTCN2022087188-appb-000005
Figure PCTCN2022087188-appb-000005
式中：uP1为压力的统计不确定度，Pa/h；πP1为第1个压力传感器的变化梯度，Pa/h；πP2为第2个压力传感器的变化梯度，Pa/h；π为平均压力变化梯度，Pa/h；n为传感器数量，式中n＝2。Where: uP1 is the statistical uncertainty of pressure, Pa/h; πP1 is the gradient of the first pressure sensor, Pa/h; πP2 is the gradient of the second pressure sensor, Pa/h; π is the average pressure Change gradient, Pa/h; n is the number of sensors, where n=2.
具体的，在安全壳试验过程中，传感器的位置决定了每一个传感器所能代表的体积，因此，在计算过程中须考虑每一个传感器的体积权重。在试验过程中，传感器的布置存在明显的区域特征，即可按照安全壳内构筑物的分 层进行布置，根据容器内温度分布的原理，稳定状态下，同一标高的温度值接近，因此，在试验过程中，温度数据也呈现明显的分层现象。本发明实施例中，温度标准不确定度、湿度标准不确定度和压力标准不确定度采用分区域拟合法计算。通过采用分区域拟合法计算，可以在安全壳试验前，不用单独计算每一个温度传感器的体积权重，只需将安全壳内的体积按照层级进行分配即可。Specifically, during the containment test, the position of the sensors determines the volume that each sensor can represent. Therefore, the volume weight of each sensor must be considered in the calculation process. During the test, the arrangement of the sensors has obvious regional characteristics, which can be arranged according to the layers of the structures in the containment. According to the principle of temperature distribution in the container, in a stable state, the temperature values at the same elevation are close. Therefore, in the test During the process, the temperature data also showed obvious layering phenomenon. In the embodiment of the present invention, the standard uncertainty of temperature, the standard uncertainty of humidity, and the standard uncertainty of pressure are calculated by using the sub-regional fitting method. By using the subregional fitting method, it is not necessary to calculate the volume weight of each temperature sensor separately before the containment test, but only to allocate the volume in the containment according to the level.
具体的，采用分区域拟合法计算的具体过程如下：Specifically, the specific calculation process using the subregional fitting method is as follows:
先计算第j层的平均温度变化率以及不确定度：First calculate the average temperature change rate and uncertainty of the jth layer:
Figure PCTCN2022087188-appb-000006
Figure PCTCN2022087188-appb-000006
Figure PCTCN2022087188-appb-000007
Figure PCTCN2022087188-appb-000007
式中：
Figure PCTCN2022087188-appb-000008
为第j层的总体温度变化率，K/h；nj为第j层的探头数量，K/h；uTj为第j层的温度标准不确定度，K/h。 where:
Figure PCTCN2022087188-appb-000008
is the overall temperature change rate of the jth layer, K/h; nj is the number of probes of the jth layer, K/h; uTj is the temperature standard uncertainty of the jth layer, K/h.
则安全壳内平均温度的变化率及不确定度为：Then the rate of change and uncertainty of the average temperature in the containment are:
Figure PCTCN2022087188-appb-000009
Figure PCTCN2022087188-appb-000009
Figure PCTCN2022087188-appb-000010
Figure PCTCN2022087188-appb-000010
式中：
Figure PCTCN2022087188-appb-000011
为安全壳整体温度的变化率，K/h；Vj为安全壳第j层的的自由容积。 where:
Figure PCTCN2022087188-appb-000011
is the change rate of the overall temperature of the containment, K/h; Vj is the free volume of the jth layer of the containment.
以某核电机组1号机为例，将安全壳内的温度传感器分布基本按照标高形成了特定的五个区域，并按照分层法进行安全壳整体泄漏率计算。其中，安全壳内部空间分区示意图如图3所示。其中，图中的T01～T70代表各个序号的温度传感器。Taking the No. 1 unit of a nuclear power unit as an example, the temperature sensors in the containment are distributed basically according to the elevation to form specific five areas, and the overall leakage rate of the containment is calculated according to the layered method. The schematic diagram of the internal space partition of the containment is shown in FIG. 3 . Among them, T01 to T70 in the figure represent the temperature sensors of each serial number.
进一步地，本发明实施例中，安全壳整体泄漏率测量模块10和安全壳强度监测模块60可以通过自由容积法测量安全壳内自由容积，并根据安全壳内的传感器所在区域对传感器进行权重分配。其中，所分配的权重可用于计算安全壳泄漏率和评价安全壳强度。Further, in this embodiment of the present invention, the containment overall leakage rate measurement module 10 and the containment strength monitoring module 60 may measure the free volume in the containment by the free volume method, and assign weights to the sensors according to the regions where the sensors are located in the containment. . Among them, the assigned weights can be used to calculate the containment leakage rate and evaluate the containment strength.
具体的，由于核电厂安全壳的整体泄漏率不能直接测量，而是需要对安 全壳壳内压力、温度、湿度等参数进行连续测量，因此，通过理想气体状态方程PV＝nRT计算得到。Specifically, since the overall leakage rate of the nuclear power plant containment cannot be directly measured, but continuous measurement of parameters such as pressure, temperature, and humidity in the containment is required, it is calculated through the ideal gas equation of state PV=nRT.
在安全壳打压试验期间，安全壳到达泄漏率测量压力平台后，根据RCC-G等标准要求，需维持压力平台到空气参数稳定后再进行泄漏率测量试验。在这段时间内，不同参数的气体充分对流，热量充分交换，温度高、湿度高的气体上浮至安全壳上部，温度低、湿度低的气体下沉至安全壳下部。图4是某安全壳打压试验期间内部气体在4.2bar.g压力平台下稳定20小时后，湿度仪表测量数据与其标高的关系，图5是温度仪表测量数据与其标高的关系，图中的直线为温度随标高线性回归结果。During the containment pressure test, after the containment reaches the leak rate measurement pressure platform, according to the requirements of RCC-G and other standards, it is necessary to maintain the pressure platform until the air parameters are stable before conducting the leak rate measurement test. During this period, the gases with different parameters are fully convective and the heat is fully exchanged. The gas with high temperature and high humidity floats to the upper part of the containment, and the gas with low temperature and low humidity sinks to the lower part of the containment. Figure 4 shows the relationship between the measurement data of the humidity instrument and its elevation after the internal gas is stabilized under a pressure platform of 4.2 bar.g for 20 hours during the pressure test of a containment vessel. Figure 5 shows the relationship between the measurement data of the temperature instrument and its elevation. The straight line in the figure is Linear regression results of temperature versus elevation.
从图4与图5可以看出，在空气参数稳定后，安全壳内温度场、湿度场在垂直方向上表现出较好的线性相关性，对其进行线性回归后，湿度随标高的线性回归相关系数R 2＝0.92，温度随标高的线性回归相关系数R 2＝0.89。实际上，由于长时间静止，安全壳内不同参数间的气体充分对流交换，在局部范围内其他方向上也是呈线性分布的。因此，对于一个微小空气单元V，到仪表Si的最优路径为Pi(i＝1,2……n，为仪表编号，n为仪表总数)，即Pi＝min(P)(P是V到各个仪表的路径集合)，则可认为仪表Si所测温度是最能代表空气单元V的温度。即Si所测温度为空气单元V的温度。 It can be seen from Figure 4 and Figure 5 that after the air parameters are stabilized, the temperature field and humidity field in the containment show a good linear correlation in the vertical direction. After linear regression, the linear regression of humidity with elevation The correlation coefficient R 2 =0.92, and the linear regression correlation coefficient of temperature with elevation R 2 =0.89. In fact, due to the long-term rest, the gas in the containment is fully convectively exchanged between different parameters, and it is also linearly distributed in other directions in the local range. Therefore, for a tiny air unit V, the optimal path to the meter Si is Pi (i=1,2...n, is the number of the meter, n is the total number of meters), that is, Pi=min(P) (P is V to The path set of each meter), the temperature measured by the meter Si can be considered to be the temperature that best represents the air unit V. That is, the temperature measured by Si is the temperature of the air unit V.
进一步地，本发明实施例中，最优路径指气休温度、湿度交换对流时的最短路径，而非空间直线距离，如图6所示，黑色粗线为墙体，V为空气微单元，S1、、S2为测量仪表，P1、P4分别表示V到S1、S2的直线路径，P2+P3为V绕过墙体到S2的最短路径。可以看出，虽然P1>P4，但P3+P2>P1，因此离V最优路径最短的仪表为S1而非S2。在进行计算时，可以用优化后的A*算法或蚂蚁算法来寻找最优路径。Further, in the embodiment of the present invention, the optimal path refers to the shortest path when the air temperature and humidity exchange convection, rather than the straight-line distance in space. As shown in FIG. 6 , the thick black line is the wall, and V is the air micro-unit. S1, S2 are measuring instruments, P1, P4 represent the straight line path from V to S1, S2 respectively, P2+P3 is the shortest path from V around the wall to S2. It can be seen that although P1>P4, P3+P2>P1, so the instrument with the shortest optimal path from V is S1 instead of S2. During the calculation, the optimized A* algorithm or the ant algorithm can be used to find the optimal path.
如图7所示，为安全壳打压试验时温度传感器T18、T19和T30的布置图，其中，黑色粗线条为墙体。T18与T30的直线距离为2.28m，T18与T19的直线距离为7.99m。在此次试验中，这三个传感器温度曲线见图8。由图7和图8可以看出，虽然T18距T30的直线距离更小，但由于两点之间有墙体隔离，温度、湿度交换对流不充分，T19处的温度比T30更接近于T18。这个 现象可以通过“最优路径”来解释：T18到T19的最优路径小于到T30的最优路径。As shown in Figure 7, it is the layout diagram of temperature sensors T18, T19 and T30 during the containment pressure test, in which the thick black line is the wall. The straight-line distance between T18 and T30 is 2.28m, and the straight-line distance between T18 and T19 is 7.99m. In this test, the temperature curves of these three sensors are shown in Figure 8. It can be seen from Figures 7 and 8 that although the straight-line distance between T18 and T30 is smaller, due to the wall isolation between the two points, the exchange and convection of temperature and humidity are insufficient, and the temperature at T19 is closer to T18 than T30. This phenomenon can be explained by the "optimal path": the optimal path from T18 to T19 is smaller than the optimal path to T30.
因此，在计算得到最优路径后，在进行安全壳整体泄漏率计算时，某点的空气温度或温度可采用最优路径最短的仪表测量值。Therefore, after calculating the optimal path, when calculating the overall leakage rate of the containment, the air temperature or temperature at a certain point can be measured by the instrument with the shortest optimal path.
进一步地，计算模块104包括：安全壳参数处理模块、安全壳监测数据处理模块、最优路径计算模块104、体积权重分配模块以及数据输出模块。Further, the calculation module 104 includes: a containment parameter processing module, a containment monitoring data processing module, an optimal path calculation module 104, a volume weight allocation module and a data output module.
安全壳参数处理模块根据安全壳墙体尺寸数据进行建模、网格划分，获得自由空间网格数据；安全壳监测数据处理模块根据温度传感器的位置数据和湿度传感器的位置数据进行仪表坐标网格化，获得仪表网格数据；最优路径计算模块104根据自由空间网格数据和仪表网格数据进行计算，获得每个仪表所代表区域的最优路径；体积权重分配模块根据最优路径进行计算，获得每个仪表体积权重；数据输出模块输出每个仪表体积权重。可以理解地，当某一传感器出现故障时，可采用自动或者手动方式将该传感器代表权重分配至其周围一个或者数个传感器中。即当安全壳温度传感器、湿度传感器及压力传感器发生故障时，将该传感器体积权重进行剔除，并根据最优路径将其权重分配到与其相邻的两个或多个传感器上。The containment parameter processing module conducts modeling and meshing according to the containment wall size data to obtain free space grid data; the containment monitoring data processing module performs an instrument coordinate grid based on the position data of the temperature sensor and the position data of the humidity sensor The optimal path calculation module 104 calculates according to the free space grid data and the meter grid data to obtain the optimal path of the area represented by each meter; the volume weight distribution module calculates according to the optimal path , obtain the volume weight of each meter; the data output module outputs the volume weight of each meter. It can be understood that when a certain sensor fails, the representative weight of the sensor can be allocated to one or several surrounding sensors in an automatic or manual manner. That is, when the containment temperature sensor, humidity sensor and pressure sensor fail, the volume weight of the sensor is eliminated, and its weight is distributed to two or more adjacent sensors according to the optimal path.
进一步地，一些实施例中，该安全壳整体泄漏率测量模块10还包括：贯穿件测量模块108。该贯穿件测量模块108用于对安全壳的贯穿件的密封性进行测量，以获得安全壳的贯穿件的密封性测试结果。Further, in some embodiments, the entire containment leakage rate measurement module 10 further includes: a penetration measurement module 108 . The penetration measurement module 108 is used to measure the tightness of the penetration of the containment, so as to obtain the test result of the sealing of the penetration of the containment.
如图9所示，该贯穿件测量模块108包括：承压箱、单片机1081、显示模组1082、设置在承压箱中的贯穿件测量单元1083和执行器1084。As shown in FIG. 9 , the penetration measurement module 108 includes: a pressure-bearing box, a single-chip microcomputer 1081 , a display module 1082 , a penetration-piece measurement unit 1083 and an actuator 1084 arranged in the pressure box.
贯穿件测量单元1083进行数据采集并获得测量数据；单片机1081根据试验指令以及测量数据控制执行器1084；执行器1084根据单片机1081的控制执行工作；显示模组1082对安全壳的贯穿件的密封性测试结果进行显示。The penetration measurement unit 1083 collects data and obtains measurement data; the single-chip microcomputer 1081 controls the actuator 1084 according to the test instructions and the measurement data; the actuator 1084 performs work according to the control of the single-chip microcomputer 1081; the display module 1082 seals the penetration of the containment shell The test results are displayed.
一些实施例中，如图10所示，贯穿件测量单元1083包括：压力传感器、温度传感器、小流量传感器、中流量传感器以及大流量传感器。In some embodiments, as shown in FIG. 10 , the penetration measurement unit 1083 includes: a pressure sensor, a temperature sensor, a small flow sensor, a medium flow sensor, and a large flow sensor.
一些实施例中，如图10所示，该执行器1084包括：设置在输入管道上的第一电磁阀V1、设置在第一输入支管道上的第二电磁阀V2、设置在第二 输入支管道上的第三电磁阀V3、设置在第一输出支管道上的第七电磁阀V7、设置在第二输出支管道上的第八电磁阀V8、设置在第一子管道上的第四电磁阀V4、设置在第二子管道上的第五电磁阀V5、设置在第三子管道上的第六电磁阀V6以及设置在输出管道上的第九电磁阀V9。In some embodiments, as shown in FIG. 10 , the actuator 1084 includes: a first solenoid valve V1 arranged on the input pipeline, a second solenoid valve V2 arranged on the first input branch pipeline, and a second input branch pipeline. The third solenoid valve V3 on the pipeline, the seventh solenoid valve V7 set on the first output branch pipeline, the eighth solenoid valve V8 set on the second output branch pipeline, and the fourth solenoid valve set on the first sub-pipeline The valve V4, the fifth solenoid valve V5 provided on the second sub-pipeline, the sixth solenoid valve V6 provided on the third sub-pipeline, and the ninth solenoid valve V9 provided on the output pipe.
其中，第一子管道、第二子管道以及第三子管道并行设置，且第一子管道、第二子管道以及第三子管道设置在第一输入支管道和第一输出支管道之间；压力传感器和温度传感器设置在第二输入支管道和第二输出支管道之间，用于测量管道内气体的温度，解决了原方案无法直接测量高压管道内空气的问题。Wherein, the first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged in parallel, and the first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged between the first input branch pipe and the first output branch pipe; The pressure sensor and the temperature sensor are arranged between the second input branch pipe and the second output branch pipe, and are used to measure the temperature of the gas in the pipe, which solves the problem that the original solution cannot directly measure the air in the high-pressure pipe.
进一步地，如图10所示，该贯穿件测量模块108还包括：设置在输入管道上且位于承压箱外的气体干燥过滤器1085；气体干燥过滤器1085用于对输入承压箱内的气体进行干燥过滤。Further, as shown in FIG. 10 , the penetration measurement module 108 further includes: a gas drying filter 1085 disposed on the input pipeline and located outside the pressure-bearing box; the gas drying filter 1085 is used for The gas is dried and filtered.
可选的，该承压箱采用不锈钢材质制成。通过采用不锈钢材质制作承压箱，可以保证其强度。Optionally, the pressure box is made of stainless steel. By using stainless steel to make the pressure box, its strength can be guaranteed.
该实施例中，温度传感器的精度为±0.5℃，小流量传感器、中流量传感器以及大流量传感器的测量精度为1％FS，压力传感器的测量精度为1‰。In this embodiment, the accuracy of the temperature sensor is ±0.5°C, the measurement accuracy of the small flow sensor, the medium flow sensor and the large flow sensor is 1%FS, and the measurement accuracy of the pressure sensor is 1‰.
进一步地，本发明实施例中，压力传感器、温度传感器以及体积传感器(小流量传感器、中流量传感器、大流量传感器)均可预留维护接口及模块校准接口。Further, in the embodiment of the present invention, a maintenance interface and a module calibration interface can be reserved for a pressure sensor, a temperature sensor, and a volume sensor (a small flow sensor, a medium flow sensor, and a large flow sensor).
进一步地，承压箱的外壳411使用贯穿件软件密封设计，以将电缆从外壳411内引出与单片机1081相连并防止其泄漏，其中，承压箱通过快速接头与外部管道连接，其中，快速接头及卸压阀与外壳411为G1/4螺纹连接，确保其密封性及方便拆卸组装。同时，为了保证高压气体下使用的安全性，可利用有限元进行外壳411强度模拟分析，在保证安全的基础上确定外壳411最优尺寸，确保使用便携及安全。Further, the casing 411 of the pressure-bearing box is designed to be sealed with a penetration piece software, so as to lead the cable out of the casing 411 to connect with the microcontroller 1081 and prevent it from leaking, wherein the pressure-bearing box is connected to the external pipeline through a quick connector, wherein the quick connector And the pressure relief valve and the shell 411 are connected with G1/4 thread to ensure its tightness and easy disassembly and assembly. At the same time, in order to ensure the safety of use under high-pressure gas, finite element analysis can be used to simulate the strength of the casing 411, and the optimal size of the casing 411 can be determined on the basis of ensuring safety to ensure portability and safety.
参考图11，为单片机1081控制工作逻辑图。Referring to FIG. 11 , it is a logic diagram of the control operation of the microcontroller 1081 .
如图11所示，试验时，试验人员根据待测隔离阀进行试压方法选择，若为内侧阀门，则点击直接流量法按钮。单片机1081控制关闭第三电磁阀V3 和第八电磁阀V8，打开第一电磁阀V1、第二电磁阀V2以及第七电磁阀V7，气体经过单片机1081，单片机1081通过内置体积传感器测量其体积和气体温度。单片机1081根据气体流量选择通过路径，若为气体体积在小量程范围内，则单片机1081控制打开第四电磁阀V4，关闭第五电磁阀V5和第六电磁阀V6。若在中量程范围内，则单片机控制打开第五电磁阀V5，关闭第四电磁阀V4和第六电磁阀V6，使用中流量传感器。否则，单片机1081控制打开第六电磁阀V6，关闭第四电磁阀V4和第五电磁阀V5，使用大流量传感器。其中，在电磁阀打开的同时，计时器开始计时，15分钟后，单片机1081读取通过温度传感器读取气体温度，然后根据体积传感器测量结果及气体温度将转换后的结果显示在显示模组1082上。As shown in Figure 11, during the test, the tester selects the pressure test method according to the isolation valve to be tested. If it is an inner valve, click the direct flow method button. The single-chip 1081 controls and closes the third solenoid valve V3 and the eighth solenoid valve V8, and opens the first solenoid valve V1, the second solenoid valve V2, and the seventh solenoid valve V7. The gas passes through the single-chip 1081, and the single-chip 1081 measures its volume and volume through the built-in volume sensor. gas temperature. The microcontroller 1081 selects the passage path according to the gas flow. If the gas volume is within the small range, the microcontroller 1081 controls to open the fourth solenoid valve V4 and close the fifth solenoid valve V5 and the sixth solenoid valve V6. If it is within the mid-range range, the single-chip microcomputer controls to open the fifth solenoid valve V5, close the fourth solenoid valve V4 and the sixth solenoid valve V6, and use the medium flow sensor. Otherwise, the microcontroller 1081 controls to open the sixth solenoid valve V6, close the fourth solenoid valve V4 and the fifth solenoid valve V5, and use a large flow sensor. Among them, when the solenoid valve is opened, the timer starts to count. After 15 minutes, the single-chip microcomputer 1081 reads the gas temperature through the temperature sensor, and then displays the converted result on the display module 1082 according to the measurement result of the volume sensor and the gas temperature. superior.
若为外侧阀门，则点击压降法按钮。单片机1081关闭第二电磁阀V2和第八电磁阀V8，打开第三电磁阀V3。试验人员点击读取温度和压力按钮作为初始压力和初始温度，同时计时器开始计时，待试验结束时，再次点击读取温度和压力按钮，此时，单片机1081读取温度和压力数据作为结束温度和压力，并计算出实时泄漏率，通过显示模组1082对实时泄漏率进行显示。For an outside valve, click the Pressure Drop Method button. The microcontroller 1081 closes the second solenoid valve V2 and the eighth solenoid valve V8, and opens the third solenoid valve V3. The tester clicks the read temperature and pressure button as the initial pressure and initial temperature, and the timer starts timing. When the test is over, click the read temperature and pressure button again. At this time, the microcontroller 1081 reads the temperature and pressure data as the end temperature. and pressure, and calculate the real-time leakage rate, and display the real-time leakage rate through the display module 1082.
如图12所示，一些实施例中，该安全壳音响测漏模块20包括：声音采集模块201、声音监测模块202以及定向传输模块203。该安全壳音响测量模块20还包括振动监测模块。As shown in FIG. 12 , in some embodiments, the containment sound leak detection module 20 includes: a sound acquisition module 201 , a sound monitoring module 202 and a directional transmission module 203 . The containment acoustic measurement module 20 also includes a vibration monitoring module.
声音采集模块201用于对安全壳的声音信号进行实时监测并采集，获得声音采集信号；声音监测模块202用于对声音采集信号进行监测并输出安全壳音响测漏测量结果；定向传输模块203用于输出安全壳音响测漏测量结果和安全壳泄漏位置及区域。振动监测模块用于监测固定管道的振动数值以及阀门的工作状态。The sound acquisition module 201 is used to monitor and collect the sound signal of the containment in real time to obtain the sound acquisition signal; the sound monitoring module 202 is used to monitor the sound acquisition signal and output the sound leak detection measurement result of the containment; the directional transmission module 203 uses To output containment audio leak detection measurement results and containment leak location and area. The vibration monitoring module is used to monitor the vibration value of the fixed pipeline and the working state of the valve.
一些实施例中，如图13所示，该声音监测模块202包括：信号采集模块2021、信号分析模块2022以及声音放大模块2023。In some embodiments, as shown in FIG. 13 , the sound monitoring module 202 includes: a signal acquisition module 2021 , a signal analysis module 2022 and a sound amplification module 2023 .
信号采集模块2021用于对声音采集信号进行采集并传送给信号分析模块2022；信号分析模块2022用于对声音采集信号进行分析过滤，以获得过滤声音信号，并将过滤声音信号发送给声音放大模块2023；声音放大模块2023用 于对过滤声音信号进行放大处理，获得安全壳音响测漏测量结果。The signal collection module 2021 is used to collect the sound collection signal and transmit it to the signal analysis module 2022; the signal analysis module 2022 is used to analyze and filter the sound collection signal to obtain a filtered sound signal, and send the filtered sound signal to the sound amplification module 2023; the sound amplifying module 2023 is used for amplifying the filtered sound signal to obtain the sound leak detection measurement result of the containment.
其中，安全壳音响测漏测量结果包括：声音采集模块201地址和声音数据。The measurement result of the containment sound leak detection includes: the address of the sound acquisition module 201 and sound data.
进一步地，如图13所示，该声音监测模块202还包括：存储电路2025和声音传输模块2024。存储电路2025用于对声音数据进行存储；声音传输模块2024用于将声音采集模块201地址和声音数据输出，以获得安全壳泄漏位置及区域。可选的，该定向传输模块203包括：定向传输电缆；定向传输电线缆接收安全壳音响测漏测量结果并传输至安全壳外。Further, as shown in FIG. 13 , the sound monitoring module 202 further includes: a storage circuit 2025 and a sound transmission module 2024 . The storage circuit 2025 is used to store the sound data; the sound transmission module 2024 is used to output the address and the sound data of the sound acquisition module 201 to obtain the leak location and area of the containment vessel. Optionally, the directional transmission module 203 includes: a directional transmission cable; the directional transmission electric cable receives the sound leak detection measurement result of the containment and transmits it to the outside of the containment.
进一步地，一些实施例中，该声音传输模块2024包括：无线发射模块和无线接收模块；无线发射模块用于接收声音采集模块201地址和声音数据并发送给无线接收模块；无线接收模块用于接收声音采集模块201地址和声音数据并输出。可选的，本发明实施例中，无线发射模块和无线接收模块采用Zigbee无线传输技术，其中，无线发射模块可通过Zigbee路由器实现，无线接收要中通过Zigbee协调器实现，通过Zigbee路由器可对声音放大模块2023输出的数据进行采集，并通过Zigbee协调器将所有数据采集汇总，然后，再通过安全壳内定向传输线缆传输到安全壳外(一般可传输到安全壳外安全的POE交换机，然后由POE交换机传输至泄漏监测上位机，其中，POE交换机在接收数据的同时，也通过电气贯穿件为安装在安全壳内的Zigbee协调器和Zigbee路由器提供电源)。Further, in some embodiments, the sound transmission module 2024 includes: a wireless transmission module and a wireless reception module; the wireless transmission module is used to receive the address and sound data of the sound acquisition module 201 and send them to the wireless reception module; the wireless reception module is used to receive The address of the sound collection module 201 and the sound data are output. Optionally, in this embodiment of the present invention, the wireless transmitting module and the wireless receiving module adopt the Zigbee wireless transmission technology, wherein the wireless transmitting module can be realized by a Zigbee router, the wireless receiving is realized by a Zigbee coordinator, and a Zigbee router can be used for sound transmission. The data output by the amplification module 2023 is collected, and all data collection is summarized through the Zigbee coordinator, and then transmitted to the outside of the containment through the directional transmission cable in the containment (generally, it can be transmitted to a safe POE switch outside the containment, and then It is transmitted from the POE switch to the leakage monitoring host computer, where the POE switch also provides power for the Zigbee coordinator and Zigbee router installed in the containment through the electrical penetrations while receiving data).
进一步地，该声音监测模块202还包括：振动传感器2026；振动传感器2026用于监测声音监测模块202的振动位移并在声音监测模块202的振动位移大于预设值时，将声音监测模块202的地址发送给无线发射模块。Further, the sound monitoring module 202 also includes: a vibration sensor 2026; the vibration sensor 2026 is used to monitor the vibration displacement of the sound monitoring module 202 and when the vibration displacement of the sound monitoring module 202 is greater than a preset value, the address of the sound monitoring module 202 is sent to the wireless transmitter module.
具体的，本发明实施例中，声音采集模块201可包括多个声音传感器。具体的，安全壳打压试验前，可将声音传感器分别安装在所有安全壳隔离阀的管壁上、0m/8m人员闸门过渡舱内、设备闸门与安全壳钢内衬螺栓513连接处，并将上述约120个声音传感器按照贯穿件编号、人员闸门标高编号定义其传感器地址，以确保试验期间发生泄漏可第一时间确定泄漏位置。试验期间，声音监测模块202处于休眠状态，当声音传感器测量到的声音大于50 分贝时，声音监测模块202从休眠中启动，声音采集模块201将测量到的声音数据传送至信号分析模块2022，若信号分析模块2022分析声音频率大于1000HZ，则送至声音放大模块2023，声音放大模块2023将传感器地址及放大后的声音进行存储，同时将压缩存储后的传感器地址和声音数据通过无线发射模块传送至无线接收模块，然后通过电气贯穿件传出安全壳外。当信号采集模块2021采集到的声音频率小于1000HZ时，则本数据直接舍弃。Specifically, in this embodiment of the present invention, the sound collection module 201 may include multiple sound sensors. Specifically, before the containment pressure test, sound sensors can be installed on the pipe walls of all containment isolation valves, in the transition cabin of the 0m/8m personnel gate, and at the connection between the equipment gate and the containment steel lining bolts 513, and the The above-mentioned about 120 sound sensors define their sensor addresses according to the number of the penetration part and the elevation number of the personnel gate, so as to ensure that the leak location can be determined at the first time when a leak occurs during the test. During the test, the sound monitoring module 202 is in a dormant state. When the sound measured by the sound sensor is greater than 50 decibels, the sound monitoring module 202 starts from dormancy, and the sound acquisition module 201 transmits the measured sound data to the signal analysis module 2022. If The signal analysis module 2022 analyzes the sound frequency greater than 1000HZ, and then sends it to the sound amplification module 2023. The sound amplification module 2023 stores the sensor address and the amplified sound, and transmits the compressed and stored sensor address and sound data to the wireless transmission module. The wireless receiving module is then transmitted out of the containment through the electrical penetration. When the sound frequency collected by the signal collection module 2021 is less than 1000 Hz, the data is directly discarded.
进一步地，通过在声音监测模块202中设置振动传感器2026，可通过振动传感器2026监测声音监测模块202的位移情况，当振动传感器2026测量到声音监测模块202的振动位移大于300μm时，则直接将本模块的地址通过无线发射模块传送至无线接收模块，然后通过电气贯穿件传出安全壳外。Further, by setting the vibration sensor 2026 in the sound monitoring module 202, the displacement of the sound monitoring module 202 can be monitored by the vibration sensor 2026. When the vibration sensor 2026 measures that the vibration displacement of the sound monitoring module 202 is greater than 300 μm, this The address of the module is transmitted to the wireless receiving module through the wireless transmitting module, and then sent out of the containment through the electrical penetration.
通过该方法，在安全壳试验期间，无须人员承压进岛，在到达1bar.g平台后，经过1小时的空气静置和吸收后，利用本系统对安全壳内进行声响测漏。当某个声音传感器测量到泄漏声响后，向上位机输出高电平信号，此时上位机通过该传感器地址确定其位置，并进一步第一时间确认泄漏位置，然后从安全壳外部隔离阀进行人工二次确认并处理泄漏。Through this method, during the containment test, there is no need for personnel to enter the island under pressure. After reaching the 1 bar.g platform, after 1 hour of air standing and absorption, the system is used to conduct acoustic leak detection in the containment. When a sound sensor measures the sound of leakage, it outputs a high-level signal to the upper computer. At this time, the upper computer determines its position through the sensor address, and further confirms the leakage position at the first time, and then manually conducts manual operation from the isolation valve outside the containment Double check and deal with leaks.
进一步地，如图1所示，该核电站安全壳试验系统还包括：安全壳外观检查模块30。Further, as shown in FIG. 1 , the nuclear power plant containment test system further includes: a containment appearance inspection module 30 .
如图14所示，该安全壳外观检查模块30包括：爬壁机器人301、地面站单元306、图像获取单元302、图像采集处理单元303、外观数据传输单元304以及防坠落装置305。该安全壳外观检查模块30还包括：位置确认装置和喷涂装置。As shown in FIG. 14 , the containment appearance inspection module 30 includes a wall climbing robot 301 , a ground station unit 306 , an image acquisition unit 302 , an image acquisition and processing unit 303 , an appearance data transmission unit 304 and a fall prevention device 305 . The containment appearance inspection module 30 further includes: a position confirmation device and a spraying device.
爬壁机器人301用于根据控制指令执行在安全壳壁面的行走动作；地面站单元306用于收集安全壳的外观缺陷图像几何信息并对图像信息进行分析处理；图像获取单元302用于对安全壳壁面进行扫描和拍照以获得安全壳壁面的图像数据；图像采集处理单元303用于对图像数据进行采集和分析，获得安全壳的外观缺陷图像几何信息；外观数据传输单元304用于将安全壳的外观缺陷图像几何信息发送给地面站单元306；防坠落装置305用于防止爬壁机器人301坠落。喷涂装置用于对检测到的缺陷信息进行标记。位置确认装 置用于在机器人完成缺陷标记后记录并存储该缺陷的位置信息。The wall-climbing robot 301 is used to perform the walking action on the wall of the containment according to the control instructions; the ground station unit 306 is used to collect the geometric information of the appearance defect image of the containment and analyze and process the image information; the image acquisition unit 302 is used to The wall surface is scanned and photographed to obtain image data of the containment wall; the image acquisition and processing unit 303 is used to collect and analyze the image data to obtain the geometric information of the appearance defect image of the containment; the appearance data transmission unit 304 is used to The geometric information of the appearance defect image is sent to the ground station unit 306; the anti-fall device 305 is used to prevent the wall-climbing robot 301 from falling. The spraying device is used to mark the detected defect information. The position confirmation device is used to record and store the position information of the defect after the robot completes the defect marking.
本发明通过在爬壁机器人301上搭载高分辨率摄像机完成混凝土缺陷识别及缺陷测量，通过无线传输模块将远程图像数据传回地面站单元306，由地面站单完成后端的数据处理。从而降低传统混凝土缺陷检测人员的劳动强度和作业风险，同时提高缺陷检测作业的效率，通过高精密测量也降低了传统目视检查的读数误差和随机性，提高了混凝土缺陷检测的质量，也解决了高寒大风等恶劣天气作业受限的问题。The present invention completes concrete defect identification and defect measurement by carrying a high-resolution camera on the wall-climbing robot 301, and transmits the remote image data back to the ground station unit 306 through a wireless transmission module, and the ground station completes the back-end data processing. Thereby reducing the labor intensity and operation risk of traditional concrete defect inspection personnel, and at the same time improving the efficiency of defect inspection operations. Through high-precision measurement, the reading error and randomness of traditional visual inspection are also reduced, and the quality of concrete defect inspection is improved. It solves the problem of limited operation in severe weather such as high cold and strong wind.
具体的，爬壁机器人301作为移动平台，可搭载摄像机吸附在混凝土表面完成垂直劈面行走，同时，承载图像获取单元302及外观数据传输单元304，爬壁机器人301本体还集成了测量所需的必要装置，包括但不限于海拔仪、喷涂装置、防坠落装置305、倾角仪等。防坠落装置305作为一种安全设备，在设备故障等异常情况下，可避免机器人高空坠落风险，保护设备及人员安全。可选的，防坠落装置305可以通过在爬壁机器人301上方悬挂安全绳来实现，其中，安全绳的另一端可由试验人员牵引，也可由卷扬机牵引。Specifically, as a mobile platform, the wall-climbing robot 301 can be equipped with a camera to be adsorbed on the concrete surface to complete vertical split-plane walking. At the same time, it carries an image acquisition unit 302 and an appearance data transmission unit 304. The body of the wall-climbing robot 301 also integrates the necessary measurement requirements. Devices, including but not limited to altitude meters, spraying devices, anti-fall devices 305, inclinometers, etc. As a kind of safety equipment, the anti-fall device 305 can avoid the risk of the robot falling from high altitude and protect the safety of equipment and personnel under abnormal conditions such as equipment failure. Optionally, the anti-fall device 305 can be implemented by suspending a safety rope above the wall-climbing robot 301 , wherein the other end of the safety rope can be pulled by a test person or a hoist.
进一步地，本发明实施例中，爬壁机器人301具备优良的壁面吸附能力及承载力，其中，壁面吸附力既要为机器人行进提供足够的正压力，又要能够承受6级或者以上大风的干扰，承载力不小于1公斤，用于搭载摄像机及无线传输设备。Further, in the embodiment of the present invention, the wall-climbing robot 301 has excellent wall surface adsorption capacity and bearing capacity, wherein the wall surface adsorption force should not only provide sufficient positive pressure for the robot to travel, but also be able to withstand the interference of strong winds of level 6 or above. , The carrying capacity is not less than 1 kg, and it is used to carry cameras and wireless transmission equipment.
其中，喷涂装置设置在爬壁机器人301上，进而使得爬壁机器人301具有喷涂功能，其喷涂功能用于对现场的缺陷进行标记。喷涂功能的设计是通过凸轮驱动机构按压安装在机器人本体上的喷漆罐实现，其中，喷涂指令可由地面站单元306发出。位置确认装置设置在爬壁机器人301上，使其具备定位功能，其中，爬壁机器人301的定位功能用于提供缺陷位置信息，该位置信息也用于后续的缺陷数据表的编制及缺陷展开图的绘制。由于安全壳筒壁为圆柱形，因此，其位置信息由水平角度和垂直高度组成。水平角度数据由试验人员，垂直高度需机器人通过海拔计提供。可选的，海拔计精度可达到0.1m，同时，为了减少外界风压对海拔计测量精度的影响，该海拔计可设计在爬壁机器人301内部。Wherein, the spraying device is arranged on the wall-climbing robot 301, so that the wall-climbing robot 301 has a spraying function, and the spraying function is used to mark defects on site. The design of the spraying function is realized by pressing the paint spraying can installed on the robot body by the cam drive mechanism, wherein the spraying instruction can be issued by the ground station unit 306 . The position confirmation device is arranged on the wall-climbing robot 301, so that it has a positioning function, wherein the positioning function of the wall-climbing robot 301 is used to provide defect position information, and the position information is also used for the subsequent compilation of defect data sheets and defect expansion diagrams drawing. Since the wall of the containment vessel is cylindrical, its position information consists of horizontal angle and vertical height. The horizontal angle data is provided by the test personnel, and the vertical height needs to be provided by the robot through the altimeter. Optionally, the accuracy of the altimeter can reach 0.1 m, and at the same time, in order to reduce the influence of external wind pressure on the measurement accuracy of the altimeter, the altimeter can be designed inside the wall-climbing robot 301 .
一些实施例中，如图15所示，该图像采集处理单元303包括：接收和发送驱动模块3031、底层通讯模块3032、上位机界面模块3033、后台运行数据库模块3034、后台服务系统模块3035以及子功能模块3036。In some embodiments, as shown in FIG. 15 , the image acquisition and processing unit 303 includes: a receiving and sending drive module 3031, a bottom communication module 3032, a host computer interface module 3033, a background operation database module 3034, a background service system module 3035, and a sub-system. Function module 3036.
接收和发送驱动模块3031用于将收发数据进行转换并传送；底层通讯模块3032用于对底层数据进行调用分配暂存；上位机界面模块3033用于对外观缺陷图像几何信息进行显示以及接收用户输入的操作信息；后台运行数据库模块3034用于对安全壳壁面的图像数据进行存储以及对用户信息进行管理；后台服务系统用于控制协调子功能模块3036的运行。The receiving and sending drive module 3031 is used to convert and transmit the received and received data; the underlying communication module 3032 is used to call, allocate and temporarily store the underlying data; the host computer interface module 3033 is used to display the geometric information of the appearance defect image and receive user input The background operation database module 3034 is used to store the image data of the containment wall and manage user information; the background service system is used to control the operation of the coordination sub-function module 3036.
可选的，该子功能模块3036包括：控制模块、定位模块、视频系统模块、图像系统模块、工具模块、菜单模块、文档标记模块、检索模块、缺陷绘制模块、存储模块以及算法模块。Optionally, the sub-function module 3036 includes: a control module, a positioning module, a video system module, an image system module, a tool module, a menu module, a document marking module, a retrieval module, a defect drawing module, a storage module, and an algorithm module.
控制模块用于对控制命令进行整合及传递；定位模块用于对爬壁机器人301的位置信息进行定位并转换为与位置信息对应的坐标；视频系统模块用于将无线传送至地面站单元306的外观缺陷图像几何信息中的视频信息进行编码并转换为视频流；图像系统模块用于对带有外观缺陷的图像进行拍照放大及分析；工具模块用于提供外观检查工具；菜单模块用于与控制指令和/或转换指令结合；文档标记模块用于将缺陷数据进行整合；检索模块用于进行数据检索及数据调配；缺陷绘制模块用于将外观缺陷图像几何信息进行二维图像重绘；存储模块用于对外观缺陷图像几何信息进行存储；算法模块用于对安全壳壁面的图像数据进行分析计算，获得安全壳的外观缺陷图像几何信息。可选的，外观检查工具包括但不限于裂缝尺、宽度尺、视频播放控件、曲线、直线、面积等。文档标记模块将裂缝长度、宽度、位置坐标、时间等信息进行整合，可自动生成易识别的文档标记数据格式。检索模块负责整个缺陷检测系统内总的数据检索服务和数据调配服务，相当于一个数据接口。缺陷绘制模块在完成或者部分完成安全壳缺陷检测任务时，可以自动将安全壳外柱机上的裂缝和破损信息进行二维图形重绘，便于安全壳检查和历史数据查看。The control module is used to integrate and transmit control commands; the positioning module is used to locate and convert the position information of the wall-climbing robot 301 into coordinates corresponding to the position information; the video system module is used to wirelessly transmit the information to the ground station unit 306. The video information in the geometric information of the appearance defect image is encoded and converted into a video stream; the image system module is used to take pictures, enlarge and analyze the image with appearance defects; the tool module is used to provide appearance inspection tools; the menu module is used to control and control The combination of instructions and/or conversion instructions; the document marking module is used to integrate defect data; the retrieval module is used to perform data retrieval and data allocation; the defect drawing module is used to redraw the two-dimensional image geometric information of the appearance defect image; storage module It is used to store the geometric information of the appearance defect image; the algorithm module is used to analyze and calculate the image data of the containment wall surface to obtain the geometric information of the appearance defect image of the containment vessel. Optionally, visual inspection tools include but are not limited to crack rulers, width rulers, video playback controls, curves, straight lines, areas, and the like. The document markup module integrates information such as crack length, width, location coordinates, time, etc., and can automatically generate an easily identifiable document markup data format. The retrieval module is responsible for the overall data retrieval service and data allocation service in the entire defect detection system, which is equivalent to a data interface. When the defect drawing module completes or partially completes the containment defect detection task, it can automatically redraw the two-dimensional graphics of the cracks and damage information on the containment outer column machine, which is convenient for containment inspection and historical data viewing.
可以理解地，各个子功能模块3036均内置于爬壁机器人301中。Understandably, each sub-function module 3036 is built into the wall-climbing robot 301 .
进一步地，一些实施例中，如图1所示，该核电站安全壳试验系统还包括：火灾监测模块40。该火灾监测模块40用于对安全壳进行火灾监测并输出火灾监测信息。Further, in some embodiments, as shown in FIG. 1 , the nuclear power plant containment test system further includes: a fire monitoring module 40 . The fire monitoring module 40 is used to perform fire monitoring on the containment and output fire monitoring information.
如图16所示，该火灾监测模块40包括：多个热像仪401、设置在安全壳上的电气贯穿件402以及传输线缆。该火灾监测模块40还包括：气体传感器、烟雾传感器。As shown in FIG. 16 , the fire monitoring module 40 includes: a plurality of thermal imagers 401 , an electrical penetration piece 402 disposed on the containment, and a transmission cable. The fire monitoring module 40 further includes: a gas sensor and a smoke sensor.
多个热像仪401用于对安全壳内的温度进行监测并输出火灾监测信息。传输线缆接收火灾监测信息、气体信息和烟雾信息并通过电气贯穿件传输至安全壳外，以及将热像仪和气体传感器电源由安全壳外传输至安全壳内，变化量小于1ppm/月，确保试验期间供电的稳定性及安全壳内没有电源，防止引起火灾。A plurality of thermal imagers 401 are used to monitor the temperature in the containment and output fire monitoring information. The transmission cable receives fire monitoring information, gas information and smoke information and transmits it to the outside of the containment through electrical penetrations, and transmits the thermal imager and gas sensor power from outside the containment to the inside of the containment. The variation is less than 1ppm/month, Ensure the stability of the power supply during the test and that there is no power supply in the containment to prevent fire.
气体传感器用于监测安全壳内的气体信息。其中，气体信息包括：O 2、CO 2、SO 2、CO等气体变化趋势；其在安全壳内信号传输依靠并联在安全壳泄漏率测量网络备用传感器的分支进行。 Gas sensors are used to monitor gas information within the containment. Among them, the gas information includes: O 2 , CO 2 , SO 2 , CO and other gas trends; its signal transmission in the containment relies on the branch of the backup sensor connected in parallel to the containment leak rate measurement network.
烟雾传感器用于监测安全壳内的烟雾信息。可选的，烟雾传感器响应时间小于2s，精度100ppm。其中，烟雾传感器通过气体引漏管进行测量。Smoke sensors are used to monitor smoke information inside the containment. Optionally, the response time of the smoke sensor is less than 2s, and the accuracy is 100ppm. Among them, the smoke sensor measures through the gas leakage pipe.
为了满足试验期间厂房内的高压环境，每一个热像仪401内置于防护罩4011中，防护罩4011为不锈钢防护罩4011。其中，该不锈钢防护罩4011最大可承受压力达到10bar.g，同时，为了防止电缆线芯漏气，可采用专门的贯穿件设计，固定端固定在格兰头内，使用高温密封胶进行缝隙密封，杜绝电缆线芯漏气。In order to meet the high pressure environment in the workshop during the test, each thermal imager 401 is built in a protective cover 4011 , and the protective cover 4011 is a stainless steel protective cover 4011 . Among them, the stainless steel protective cover 4011 can withstand a maximum pressure of 10bar.g. At the same time, in order to prevent the cable core from leaking, a special penetration design can be used, the fixed end is fixed in the gland head, and high temperature sealant is used to seal the gap. , to prevent air leakage of the cable core.
具体的，该防护罩4011包括外壳411以及设置在外壳411底部的密封性试验接口412；热像仪401内置于外壳411中并通过密封性试验接口412进行密封性试验。其中，该密封性试验接口412为G1/4螺纹。使用该密封性接口进行密封性试验时，向保防护罩4011内部充压至5bar.g，在接口处连接压力表进行24小时密封性测试，压降小于30mbar判断为合格。测试合格后再将热像仪401安装在防护罩4011内，内部使用支撑结构，确保热像仪401的稳定性，面板415使用锗玻璃，红外透过率达到99％，使热像仪401的性能发 挥到最大且确保不被高压空气损坏。Specifically, the protective cover 4011 includes a casing 411 and a tightness test interface 412 disposed at the bottom of the casing 411 ; the thermal imager 401 is built in the casing 411 and conducts a tightness test through the tightness test interface 412 . Wherein, the sealing test interface 412 is a G1/4 thread. When using this sealing interface for the sealing test, charge the inside of the protective cover 4011 to 5 bar.g, connect a pressure gauge at the interface for a 24-hour sealing test, and judge it as qualified if the pressure drop is less than 30 mbar. After passing the test, install the thermal imager 401 in the protective cover 4011, and use a support structure inside to ensure the stability of the thermal imager 401. The panel 415 uses germanium glass, and the infrared transmittance reaches 99%, which makes the thermal imager 401 more stable. Performance is maximized and guaranteed not to be damaged by high pressure air.
具体的，如图17所示，为防护罩4011的结构示意图。Specifically, as shown in FIG. 17 , it is a schematic structural diagram of the protective cover 4011 .
如图17所示，在防护罩4011内部可匹配热像仪401的外形进行设计，同时设置限位扣416，可起到固定热像仪401的作用。As shown in FIG. 17 , the interior of the protective cover 4011 can be designed to match the shape of the thermal imager 401 , and at the same time, a limit buckle 416 is provided, which can play the role of fixing the thermal imager 401 .
如图17所示，在接口处，采用固定件413固定密封，其中，固定件413用耐高温密封胶灌满，以达到密封的目的，同时也满足方便拆卸的目的，同时加设公制外螺纹平面密封O型硅橡胶圈，用螺丝，固定，达到密封作用。如图12所示，防护罩4011的底部与侧边通过特制的连接件414密封连接，该特制的连接件414采用类似于高压锅防气压设计，硅橡胶采用E字槽，再加设12个受力均匀的螺丝稳固，以保证密封的强度和稳定性。As shown in Figure 17, at the interface, the fixing member 413 is used to fix and seal, wherein, the fixing member 413 is filled with high temperature resistant sealant to achieve the purpose of sealing and also to facilitate disassembly. At the same time, a metric external thread is added. Flat sealing O-type silicone rubber ring, fixed with screws to achieve sealing effect. As shown in Figure 12, the bottom of the protective cover 4011 is sealed with the side through a special connector 414. The special connector 414 adopts a pressure-proof design similar to a pressure cooker, and the silicone rubber adopts an E-shaped groove. The screw with uniform force is stable to ensure the strength and stability of the seal.
进一步地，如图17所示，面板415上部与防护罩4011之间通过垫圈417固定密封，其中，可采用两个硅橡胶O型热圈，以此达到双层防护的目的，同时保护锗玻璃光学镜片。进一步地，垫圈417为防水垫圈417，可达到耐高温、耐酸、耐碱作用。Further, as shown in FIG. 17 , the upper part of the panel 415 and the protective cover 4011 are fixed and sealed by a gasket 417, wherein two silicone rubber O-rings can be used to achieve the purpose of double-layer protection and protect the germanium glass at the same time. Optical lenses. Further, the gasket 417 is a waterproof gasket 417, which can achieve high temperature resistance, acid resistance and alkali resistance.
进一步地，面板415可以采用10mm超厚设计的锗玻璃光学镜片，从而使热像仪401的红外透过率达到99％或者以上，抗压强度可达到10bar以上。Further, the panel 415 can use a germanium glass optical lens with an ultra-thick design of 10 mm, so that the infrared transmittance of the thermal imager 401 can reach 99% or more, and the compressive strength can reach more than 10 bar.
进一步地，一些实施例中，如图1所示，该核电站安全壳试验系统还包括：主回路逆止阀泄漏率监测模块50。该主回路逆止阀泄漏率监测模块50用于对主回路逆止阀泄漏率进行监测并输出主回路逆止阀泄漏率监测结果，其结果用于修正安全壳整体泄漏率。Further, in some embodiments, as shown in FIG. 1 , the nuclear power plant containment test system further includes: a main loop check valve leakage rate monitoring module 50 . The main loop check valve leakage rate monitoring module 50 is used for monitoring the main loop check valve leakage rate and outputting the main loop check valve leakage rate monitoring results, and the results are used to correct the overall leakage rate of the containment.
该主回路逆止阀泄漏率监测模块50包括：逆止阀封堵装置。逆止阀封堵装置包括阀腔501，密封气囊508、轴向平衡装置5081、充压单元以及监测单元。The main circuit check valve leakage rate monitoring module 50 includes a check valve blocking device. The check valve blocking device includes a valve cavity 501, a sealing airbag 508, an axial balance device 5081, a charging unit and a monitoring unit.
充压单元用于向逆止阀的阀腔501内充压或者密封气囊508充压；轴向平衡装置5081用于平衡阀腔501内的轴向力；监测单元用于监测逆止阀的充压数据，根据充压数据计算逆止阀的泄漏率；根据逆止阀的泄漏率输出主回路逆止阀泄漏率监测结果。The charging unit is used to charge the valve cavity 501 of the check valve or the sealing airbag 508; the axial balance device 5081 is used to balance the axial force in the valve cavity 501; the monitoring unit is used to monitor the charging of the check valve. According to the pressure data, the leakage rate of the check valve is calculated according to the charging data; according to the leakage rate of the check valve, the leakage rate monitoring result of the check valve of the main circuit is output.
可选的，该充压单元包括：第一充压装置和第二充压装置；第一充压装 置用于向逆止阀的阀腔501内充压并采集阀腔501的压力数据；第二充压装置用于向密封气囊508充压并采集密封气囊508的压力数据。Optionally, the charging unit includes: a first charging device and a second charging device; the first charging device is used to pressurize the valve cavity 501 of the check valve and collect pressure data of the valve cavity 501; The second inflating device is used to inflate the airtight airbag 508 and collect pressure data of the airtight airbag 508 .
其中，充压数据包括：阀腔501的压力数据和密封气囊508的压力数据；Wherein, the charging data includes: the pressure data of the valve cavity 501 and the pressure data of the sealing airbag 508;
如图18所示，该逆止阀封堵装置还包括：阀体51，位于阀腔501开口处以使阀腔501形成密闭空间。如图18所示，阀体51自带螺栓513，当阀盖506安装在阀腔501开口处时，通过阀体51自带的螺栓513将阀盖506固定在阀腔501开口处。As shown in FIG. 18 , the check valve blocking device further includes: a valve body 51 located at the opening of the valve cavity 501 so that the valve cavity 501 forms a closed space. As shown in FIG. 18 , the valve body 51 has its own bolts 513 . When the valve cover 506 is installed at the opening of the valve cavity 501 , the valve cover 506 is fixed at the opening of the valve cavity 501 through the bolts 513 of the valve body 51 .
如图18所示，该第一充压装置包括：第一充气气囊502、第一阀门503以及第一压力表。该第一充压装置还包括阀体51充压管线509，其中，阀体51充压管线509一端通过第一快速接头511与第一充气气囊502连接，另一端插入阀盖506的阀体充压口5101。方便拆装及维护。第二充压装置包括：第二充气气囊504、第二阀门505以及第二压力表。该第二充压装置还包括：气囊充压管线510，该气囊充压管线510通过一端第二快速接头512与第二充气气囊504连接，另一端穿过阀盖506的气囊充压口5102并伸入阀腔501内与密封气囊508连接。通过采用快速接头的方式可以方便拆装与维护。As shown in FIG. 18 , the first inflation device includes: a first inflation air bag 502 , a first valve 503 and a first pressure gauge. The first charging device further includes a charging pipeline 509 of the valve body 51 , wherein one end of the charging pipeline 509 of the valve body 51 is connected to the first inflating air bag 502 through the first quick connector 511 , and the other end is inserted into the valve body of the valve cover 506 for charging Pressure port 5101. Easy to disassemble and maintain. The second inflation device includes: a second inflation air bag 504 , a second valve 505 and a second pressure gauge. The second inflating device further includes: an airbag inflating line 510, the airbag inflating line 510 is connected to the second inflating airbag 504 through a second quick connector 512 at one end, and the other end passes through the airbag inflating port 5102 of the valve cover 506 and is It extends into the valve cavity 501 and is connected to the sealing airbag 508 . It can be easily disassembled and maintained by using the quick connector.
第一充气气囊502用于向阀腔501内充压；第一压力表用于在第一充气气囊502充压过程中采集阀腔501的压力数据；第一阀门503在第一充气气囊502充压时打开；第二充气气囊504用于向密封气囊508充压；第二压力表用于在第二充气气囊504充压过程中采集密封气囊508的压力数据；第二阀门505在第二充气气囊504充压时打开。需要说明的是第一压力表和第二压力表未在图18中示出。The first inflatable airbag 502 is used to inflate the valve cavity 501; the first pressure gauge is used to collect the pressure data of the valve cavity 501 during the inflation of the first inflatable airbag 502; The second inflatable airbag 504 is used to inflate the sealing airbag 508; the second pressure gauge is used to collect the pressure data of the sealing airbag 508 during the inflation of the second inflatable airbag 504; the second valve 505 is used for the second inflation The bladder 504 opens when inflated. It should be noted that the first pressure gauge and the second pressure gauge are not shown in FIG. 18 .
进一步地，如图18所示，该密封气囊508中还设有不锈钢防护网5082，通过在密封气囊508中设置该不锈钢防护网5082，可以使密封气囊508在未冲压时形成圆柱状，从而方便气囊安装。Further, as shown in FIG. 18 , the sealing airbag 508 is also provided with a stainless steel protective net 5082. By arranging the stainless steel protective net 5082 in the sealing airbag 508, the sealing airbag 508 can be formed into a cylindrical shape when it is not stamped, so as to facilitate the Airbag installation.
试验时，使用气囊充压及监测装置对气囊进行充压及压力监测，压力低于1.5bar.g时对其补充压力，使密封气囊508与管道内壁良好密封，用于对管道实现反向密封。密封气囊508作为试验密闭空间的一部分，与试验专用阀 盖506共同建立试验密闭空间，轴向平衡装置5081用于平衡阀腔501气体压力引起的轴向力，防止试验期间，阀腔501内的高压气体产生的轴向压力将密封气囊508压入系统管线中。试验期间，通过阀盖506上的压力表对被测逆止阀密封性进行测量。其中，该逆止阀封堵装置位于逆止阀出口管线侧，密封气囊508与阀盖506之间采用快速接头连接，具有连接方便，密封性良好，具备实时监测自身密封性、平衡轴向能力和安装轻便的特点。During the test, the air bag inflation and monitoring device is used to inflate and monitor the air bag. When the pressure is lower than 1.5 bar.g, the pressure is supplemented, so that the air bag 508 is well sealed with the inner wall of the pipeline, which is used to achieve reverse sealing of the pipeline. . As a part of the test closed space, the sealing airbag 508 and the test-specific valve cover 506 jointly establish the test closed space. The axial balance device 5081 is used to balance the axial force caused by the gas pressure in the valve cavity 501, so as to prevent the internal pressure of the valve cavity 501 during the test. The axial pressure created by the high pressure gas forces the sealing bladder 508 into the system lines. During the test, the tightness of the check valve under test is measured by the pressure gauge on the valve cover 506 . Among them, the check valve blocking device is located on the side of the check valve outlet pipeline, and the sealing airbag 508 and the valve cover 506 are connected by a quick joint, which has the advantages of convenient connection, good sealing performance, and real-time monitoring of self-sealing performance and axial balance. and easy installation.
具体的试验过程如下：The specific test process is as follows:
将密封气囊508置于管道内，从第二阀门505充压至1.5bar.g；稳定5分钟后，若压降小于0.05bar，安装上阀盖506；从第一阀门503向管道内充压至设计压力P 0，记录时当前时刻t1；当持续时间满足预设时间后，记录当前时刻t2和当前压力表读数P 1，根据公式：
Figure PCTCN2022087188-appb-000012
进行计算，其中t为t2与t2的差值，V为阀腔501体积，Q为泄漏率，△P为压差，P为当前压力P 1。 Place the air-tight airbag 508 in the pipeline, and pressurize it from the second valve 505 to 1.5 bar.g; after 5 minutes of stabilization, if the pressure drop is less than 0.05 bar, install the valve cover 506; pressurize the pipeline from the first valve 503 To the design pressure P 0 , record the current time t1; when the duration meets the preset time, record the current time t2 and the current pressure gauge reading P 1 , according to the formula:
Figure PCTCN2022087188-appb-000012
Calculate, where t is the difference between t2 and t2, V is the volume of the valve cavity 501, Q is the leakage rate, ΔP is the pressure difference, and P is the current pressure P 1 .
进一步地，一些实施例中，如图1所示，该核电站安全壳试验系统还包括：安全壳强度监测模块60。该安全壳强度监测模块60用于对安全壳强度进行监测并输出强度监测数据。Further, in some embodiments, as shown in FIG. 1 , the nuclear power plant containment test system further includes: a containment strength monitoring module 60 . The containment strength monitoring module 60 is used to monitor the containment strength and output strength monitoring data.
如图19所示，该安全壳强度监测模块60包括：强度监测数据采集装置601、EAU自动读数模块602以及无线通信模块604。As shown in FIG. 19 , the containment strength monitoring module 60 includes: a strength monitoring data acquisition device 601 , an EAU automatic reading module 602 and a wireless communication module 604 .
强度监测数据采集装置601用于对安全壳的强度数据进行采集，获得安全壳强度监测数据；EAU自动读数模块602用于对安全壳强度监测数据进行读取并输出；无线通信模块604用于对安全壳强度监测数据进行传输。The strength monitoring data collection device 601 is used to collect the strength data of the containment to obtain the strength monitoring data of the containment; the EAU automatic reading module 602 is used to read and output the monitoring data of the strength of the containment; the wireless communication module 604 is used to read and output the strength monitoring data of the containment. Containment strength monitoring data is transmitted.
一些实施例中，强度监测数据采集装置601包括但不限于：热电偶、声频应变计、水准盒以及铅垂线监测设备。进一步地，强度监测数据采集模块601还可包括：测力计和变位计。其中，测力计主要对安全壳预应力进行测量；变位计对安全壳筒体实际沉降进行修正测量。In some embodiments, the intensity monitoring data acquisition device 601 includes, but is not limited to, thermocouples, audio strain gauges, level boxes, and plumb line monitoring equipment. Further, the intensity monitoring data acquisition module 601 may further include: a force gauge and a displacement gauge. Among them, the dynamometer mainly measures the prestress of the containment; the displacement meter corrects and measures the actual settlement of the containment cylinder.
热电偶用于采集热电偶数据对试验期间混凝土应变进行修正，同时也用于校准声频应变计的安装位置是否与设计位置一致；声频应变计用于采集安 全壳的形变应力并获得形变应力数据；水准盒用于采集安全壳筏基的变形位移并获得筏基变形位移数据；铅垂线监测设备用于监测安全壳的筒体形变并获得铅垂线数据。The thermocouple is used to collect the thermocouple data to correct the concrete strain during the test, and it is also used to calibrate whether the installation position of the acoustic strain gauge is consistent with the design position; the acoustic strain gauge is used to collect the deformation stress of the containment and obtain the deformation stress data; The level box is used to collect the deformation and displacement of the raft foundation of the containment and obtain the deformation and displacement data of the raft foundation; the plumb line monitoring equipment is used to monitor the cylinder deformation of the containment and obtain the plumb line data.
一些实施例中，该安全壳强度监测模块60还包括：铅垂线数据采集模块603。铅垂线数据采集模块603用于接收铅垂线监测设备采集的铅垂线数据并输出。进一步地，该安全壳强度监测模块60还包括：变位计和测力计。变位计连接水准盒和地形基点，以获得大地基准点和安全壳筏基之间在试验期间的相对变化数据，从而实现对安全壳进行沉降监测。测力计可对安全壳进行应力监测。In some embodiments, the containment strength monitoring module 60 further includes: a plumb line data collection module 603 . The plumb line data collection module 603 is configured to receive and output plumb line data collected by the plumb line monitoring equipment. Further, the containment strength monitoring module 60 further includes: a displacement gauge and a dynamometer. The displacement meter is connected with the level box and the terrain base point to obtain the relative change data between the geodetic reference point and the containment raft foundation during the test, so as to realize the settlement monitoring of the containment. The dynamometer provides stress monitoring of the containment.
一些实施例中，EAU(安全壳永久仪表系统)自动读数模块包括：EAU自动读数箱、三通适配箱以及EAU自动读数装置。In some embodiments, the EAU (Containment Permanent Instrumentation) automatic reading module includes: an EAU automatic reading box, a three-way adapter box, and an EAU automatic reading device.
EAU自动读数箱读取热电偶采集的热电偶数据、声频应变计采集的形变应力数据以及水准盒采集的变形位移数据，并将热电偶数据、形变应力数据和变形位移数据发送给三通适配箱；三通适配箱接收协调水准盒采集的变形位移数据，并将热电偶数据、形变应力数据和变形位移数据并传送至EAU自动读数装置；EAU自动读数装置接收水准盒采集的变形位移数据，并将热电偶数据、形变应力数据和变形位移数据并进行转换处理后发送给无线通信模块604。The EAU automatic reading box reads the thermocouple data collected by the thermocouple, the deformation stress data collected by the audio strain gauge and the deformation displacement data collected by the level box, and sends the thermocouple data, deformation stress data and deformation displacement data to the tee adapter box; the three-way adapter box receives the deformation displacement data collected by the coordination level box, and transmits the thermocouple data, deformation stress data and deformation displacement data to the EAU automatic reading device; the EAU automatic reading device receives the deformation displacement data collected by the level box. , and send the thermocouple data, deformation stress data and deformation displacement data to the wireless communication module 604 after conversion processing.
如图19所示，声频应变计、水准盒、变位计以及热电偶采集到的形变应力数据、变形位移数据以及热电偶数据可由EAU自动读数箱读取并传送给三通适配箱，由三通适配箱发送至多通道切换模块进行通道切换后，由NI振弦采集模块和NI热电偶采集模块采集获得相应的振弦信号和热电偶信号，再由NI控制模块控制调节后通过转换模块进行转换后发送至无线通信模块604，由无线通信模块604发送给服务器。铅垂线监测设备采集的铅垂线数据由铅垂线数据采集模块603采用并通过RS485总线传输至无线通信模块604，再由无线通信模块604发送给服务器。其中转换模块为将RS232数据转换为RS485数据。进一步地，EAU自动读数装置还包括：供电模块，用于提供电能。可选的，该供电模块包括动力聚合物锂电池(可选用12V/80Ah)以及电 源适配器(AC220转12V/5V)。As shown in Figure 19, the deformation stress data, deformation displacement data and thermocouple data collected by the audio frequency strain gauge, level box, displacement gauge and thermocouple can be read by the EAU automatic reading box and transmitted to the three-way adapter box. After the three-way adapter box is sent to the multi-channel switching module for channel switching, the corresponding vibrating wire signal and thermocouple signal are acquired by the NI vibrating wire acquisition module and NI thermocouple acquisition module, and then controlled and adjusted by the NI control module and then passed through the conversion module. After conversion, it is sent to the wireless communication module 604, and then sent to the server by the wireless communication module 604. The plumb line data collected by the plumb line monitoring equipment is adopted by the plumb line data acquisition module 603 and transmitted to the wireless communication module 604 through the RS485 bus, and then sent to the server by the wireless communication module 604 . The conversion module converts RS232 data into RS485 data. Further, the EAU automatic reading device further includes: a power supply module for providing electrical energy. Optionally, the power supply module includes a power polymer lithium battery (optional 12V/80Ah) and a power adapter (AC220 to 12V/5V).
进一步地，服务器接收到无线通信模块604发送的振弦信号、热电偶信号以及铅垂线数据后，将模拟信号(振弦信号、热电偶信号以及铅垂线数据)转化为数字信号后，进行实时计算得出计算结果1，同时结合安全壳敏感区域截椎体、扶壁柱、穹顶、设备闸门加腋区、人员闸门外扩区及蒸汽发生器管道的外观检查数据，对上述敏感区域进行杨氏模量和泊松比拟合计算得出计算结果2，以及建造阶段混凝土样块的平均杨氏模量和泊松比，将上述结果进行数据拟合处理，从而得到安全壳打压试验期间安全壳的整体变形、形变、应变及沉降，根据计算结果显示当前安全壳最大变形位置、最大应变及最大沉降所在角度，并将相同区域的热电偶与声频应变计温度及趋势之间形成对比，相同区域声频应变计测得的应变与铅垂线、水准盒测得的位移形成对比，保证测量真实有效，从而使安全壳强度有更直观、更准确的评价。Further, after receiving the vibrating wire signal, the thermocouple signal and the plumb line data sent by the wireless communication module 604, the server converts the analog signal (the vibrating wire signal, the thermocouple signal and the plumb line data) into a digital signal, and then performs the process. Calculation result 1 is obtained by real-time calculation. At the same time, combined with the visual inspection data of the truncated cone, buttress column, dome, equipment gate and axillary area, personnel gate outer expansion area and steam generator pipeline in the sensitive area of the containment, the above sensitive areas are carried out. The Young's modulus and Poisson's ratio are fitted and calculated to obtain calculation result 2, as well as the average Young's modulus and Poisson's ratio of the concrete samples during the construction stage. The above results are subjected to data fitting processing to obtain the overall containment during the containment compression test. Deformation, deformation, strain and settlement. According to the calculation results, the maximum deformation position, maximum strain and maximum settlement angle of the current containment are displayed, and the temperature and trend of the thermocouple in the same area and the audio frequency strain gauge are compared, and the audio frequency strain in the same area is compared. The strain measured by the gauge is compared with the displacement measured by the plumb line and the level box to ensure that the measurement is true and effective, so that the strength of the containment can be evaluated more intuitively and accurately.
其中，本发明实施例中，声频应变计可包括52路，水准盒可包括13路、热电偶可包括28路。因此，在后期的数据处理中，可支持移除传感器损坏或者结果错误的读数，移除一个或者多个传感器数据之后，剩余传感器重新加入到计算过程中并显示相应的计算结果。Among them, in the embodiment of the present invention, the audio frequency strain gauge may include 52 channels, the level box may include 13 channels, and the thermocouple may include 28 channels. Therefore, in the later data processing, it can support the removal of readings with damaged sensors or wrong results. After removing one or more sensor data, the remaining sensors are re-added to the calculation process and the corresponding calculation results are displayed.
该安全壳强度监测模块60所监测得到的数据通过无线通信模块604发送给服务器后，服务器基于参考电站试验数据、安全壳建设阶段EAU测量数据、预应力张拉数据并结合实时读取的无线通信模块604传输的试验数据进行实时计算。After the data monitored by the containment strength monitoring module 60 is sent to the server through the wireless communication module 604, the server is based on the reference power station test data, the EAU measurement data during the containment construction phase, and the prestressed tension data combined with real-time read wireless communication The test data transmitted by the module 604 is calculated in real time.
具体的，如图20所示，基于铅垂线数据计算安全壳径向形变，显示最大变形位置及角度，并可生成安全壳形变随压力实时变化曲线；基于声频应变计的测量数据计算各个位置所受应变，显示最大应变位置，并生成安全壳各应变随压力变化曲线；基于热电偶的测量数据计算各个位置温度、显示最大温度，并生成安全壳实时温度变化曲线；基于水准盒的测量数据计算筏其各区域沉降，并生成筏其沉降随压力变化曲线；基于收敛计的测量数据计算筒体沉降，并生成筒体沉降随压力变化曲线；基于测力计的测量数据计算预应力环廊沉降数据，并生成沉降随压力变化曲线；基于预应力张拉数据得到的 泊松比及杨氏模量计算出安全壳试验期间各部分形变的期望值。Specifically, as shown in Figure 20, the radial deformation of the containment is calculated based on the plumb line data, the maximum deformation position and angle are displayed, and the real-time curve of the deformation of the containment with the pressure can be generated; each position is calculated based on the measurement data of the acoustic strain gauge Strain, display the maximum strain position, and generate the curve of each strain of the containment with the pressure; calculate the temperature at each position based on the measurement data of the thermocouple, display the maximum temperature, and generate the real-time temperature change curve of the containment; based on the measurement data of the level box Calculate the settlement of each area of the raft, and generate the curve of the settlement of the raft with the pressure; calculate the settlement of the cylinder based on the measurement data of the convergence meter, and generate the curve of the settlement of the cylinder with the pressure; calculate the prestressed ring gallery based on the measurement data of the dynamometer Settlement data, and generate a curve of settlement versus pressure; based on the Poisson's ratio and Young's modulus obtained from the prestressed tensile data, the expected value of the deformation of each part during the containment test was calculated.
接着将安全壳形变随压力实时变化曲线和安全壳各应变随压力变化曲线互为对比，生成实时安全壳筒体应变与形变的曲线图，判断应变及形变变化趋势是否相同以确定测量系统的可用性。将安全壳各应变随压力变化曲线和安全壳实时温度变化曲线互为对比，生成实时各区域温度对比曲线图，根据趋势判断测量系统的有效性。基于筏基沉降随压力变化曲线和筒体沉降随压力变化曲线，生成实时安全壳筒体竖向变形曲线图。将安全壳各应变随压力变化曲线和筏基沉降随压力变化曲线互为对比，生成实时安全壳筏其形变与应力对比曲线图，并根据二者变化趋势判断测量系统的有效性。Then, compare the real-time variation curve of containment deformation with pressure and the variation curve of each strain of the containment with pressure to generate a real-time curve graph of the strain and deformation of the containment cylinder, and determine whether the variation trend of strain and deformation is the same to determine the availability of the measurement system . Comparing the variation curve of each strain with pressure of the containment and the real-time temperature variation curve of the containment, a real-time temperature comparison curve of each area is generated, and the effectiveness of the measurement system is judged according to the trend. Based on the curve of raft foundation settlement with pressure and the curve of cylinder settlement with pressure, a real-time vertical deformation curve of the containment shell is generated. The variation curves of the strain of the containment with the pressure and the curve of the settlement of the raft foundation with the pressure are compared with each other, and the real-time deformation and stress comparison curves of the containment raft are generated, and the effectiveness of the measurement system is judged according to the change trend of the two.
最后，基于安全壳形变随压力实时变化曲线、安全壳各应变随压力变化曲线、筏基沉降随压力变化曲线、筒体沉降随压力变化曲线、沉降随压力变化曲线与CTT期间各部分形变的期望值进行差别分析，分析安全壳混凝土钢筋是否出现现象，得出安全壳实测杨氏模量及泊松比，与参考电站试验数据进行对比，结合外观检查得出强度评价。Finally, based on the real-time variation curve of containment deformation with pressure, the variation curve of each strain of containment with pressure, the variation curve of raft foundation settlement with pressure, the variation curve of cylinder settlement with pressure, the variation curve of settlement with pressure and the expected value of the deformation of each part during CTT The difference analysis is carried out to analyze whether the concrete reinforcement of the containment has any phenomenon, and the measured Young's modulus and Poisson's ratio of the containment are obtained.
进一步地，如图1所示，该核电站安全壳试验系统还包括：外层安全壳测量模块70。该外层安全壳测量模块70对外层安全壳密封性进行测量并输出密封性测量结果。Further, as shown in FIG. 1 , the nuclear power plant containment test system further includes: an outer containment measurement module 70 . The outer containment measuring module 70 measures the tightness of the outer containment and outputs the tightness measurement result.
如图21所示，该外层安全壳测量模块70包括：安全壳监测模块701、流量控制器702、采集器703以及工控机704。As shown in FIG. 21 , the outer containment measurement module 70 includes: a containment monitoring module 701 , a flow controller 702 , a collector 703 and an industrial computer 704 .
安全壳监测模块701用于采集外层安全壳的气体信息；流量控制器702用于控制注入流量并采集流量数据；采集器703对外层安全壳数据和流量数据进行采集并发送给工控机704；工控机704对外层安全壳数据、流量数据进行分析处理，并输出密封性测量结果。其中，外层安全壳的气体信息包括但不限于气体温度、气体湿度、压力、风量、体积等。The containment monitoring module 701 is used to collect the gas information of the outer containment; the flow controller 702 is used to control the injection flow and collect the flow data; the collector 703 collects the outer containment data and the flow data and sends it to the industrial computer 704; The industrial computer 704 analyzes and processes the outer containment data and flow data, and outputs the sealing measurement result. The gas information of the outer containment vessel includes, but is not limited to, gas temperature, gas humidity, pressure, air volume, volume, and the like.
进一步地，一些实施例中，该外层安全壳测量模块70还包括：显示器705；显示器705接收密封性测量结果并显示。Further, in some embodiments, the outer containment measurement module 70 further includes: a display 705; the display 705 receives and displays the sealing measurement result.
具体的，EPR核电机组采用双层安全壳设计，内层安全壳是后张拉预应力混凝土结构并有6mm厚的钢衬里，筒体墙厚1300mm。外层安全壳是钢筋 混凝土结构，厚1300mm。外层安全壳外露部分及外围的燃料厂房和安全厂房的外墙厚1800mm。内、外安全壳之间形成一个宽1800mm的环形廊道，环廊通过环廊通风系统(EDE)维持负压。在事故工况下，安全壳泄漏监测系统(EPP)能收集来自人员闸门、设备闸门、燃料传输通道隔离阀等处泄漏的微量放射性物质至负压环廊的地坑内，经EDE系统的高效过滤器和碘吸附器过滤后排放至烟囱，以限制放射性物质向环境释放。因此，在调试期间需要对外层安全壳进行密封性测试。Specifically, the EPR nuclear power unit adopts a double-layer containment design. The inner containment is a post-tensioned prestressed concrete structure with a 6mm-thick steel lining, and the cylinder wall thickness is 1300mm. The outer containment is a reinforced concrete structure with a thickness of 1300mm. The thickness of the outer wall of the exposed part of the outer containment and the surrounding fuel workshop and safety workshop is 1800mm. A ring corridor with a width of 1800mm is formed between the inner and outer containment, and the ring corridor maintains negative pressure through the ring corridor ventilation system (EDE). Under accident conditions, the containment leakage monitoring system (EPP) can collect trace amounts of radioactive substances leaked from personnel gates, equipment gates, fuel transfer channel isolation valves, etc. Filters and iodine adsorbers are filtered and discharged to the chimney to limit the release of radioactive materials to the environment. Therefore, the outer containment vessel needs to be tested for tightness during commissioning.
进一步地，由于外层安全壳的特殊性，因此，本发明实施例中，外层安全壳的泄漏率的测量采用在非稳态工况下大体积密闭空间进行测量。即外层安全壳试验前将环廊负压抽至－2000Pa以上，达到试验压力后停运抽压风机，隔离外层安全壳环廊，在泄漏过程中动态测量环廊内的气体参数。通过大量的数据拟合得到泄漏量与压差的函数关系，进而得到设计压力下的泄漏率。Further, due to the particularity of the outer containment, in the embodiment of the present invention, the leakage rate of the outer containment is measured by using a large-volume confined space under unsteady working conditions. That is, before the outer containment test, the negative pressure of the ring gallery is pumped to above -2000Pa. After reaching the test pressure, the pumping fan is stopped to isolate the outer containment ring gallery, and the gas parameters in the ring gallery are dynamically measured during the leakage process. By fitting a large amount of data, the functional relationship between the leakage and the differential pressure is obtained, and then the leakage rate under the design pressure is obtained.
如图22所示，为外层安全壳泄漏来源示意图。As shown in Figure 22, it is a schematic diagram of the leakage source of the outer containment.
如图22所示，一定压差(ΔP)下外层安全壳泄漏率Qpei，为总泄漏量Qeee与注入流量Qinj之差。As shown in Figure 22, the leakage rate Qpei of the outer containment under a certain pressure difference (ΔP) is the difference between the total leakage Qeee and the injection flow rate Qinj.
外层安全壳试验试验过程中，一个抽负压与内外压力平衡的过程称为一个压力循环。外层安全壳试验试验期间需进行数个向环廊内注入定量干空气的压力循环。注入的干空气作为试验期间的参考泄漏。每次注入的流量为10～20m 3/h之间的一个定值。试验需要进行至少1个不注入干空气的压力循环和至少2个注入干空气的压力循环作为验证对比。 During the outer containment test, a process in which the negative pressure is drawn and the internal and external pressures are balanced is called a pressure cycle. During the outer containment test, several pressure cycles are required to inject quantitative dry air into the ring gallery. The injected dry air served as the reference leak during the test. The flow rate of each injection is a fixed value between 10 and 20 m 3 /h. The test requires at least 1 pressure cycle without dry air injection and at least 2 pressure cycles with dry air injection as a verification comparison.
进一步地，本发明实施例中，采用“匀速压降稳态”判定原则进行判定。具体的，在测量数据分析过程中，若同时满足下列两个条件，则可认为60分钟时间段内环廊泄漏率可以使用气体参数梯度法(气体状态满足“匀束压降稳态”)进行计算：Further, in the embodiment of the present invention, the determination principle of "constant pressure drop at a constant speed" is used for determination. Specifically, in the process of measurement data analysis, if the following two conditions are met at the same time, it can be considered that the leakage rate of the ring corridor in the 60-minute period can be determined by using the gas parameter gradient method (the gas state satisfies the "homogeneous beam pressure drop steady state") calculate:
(1)环廊气体满足“均匀变化”要求，即30分钟内气体温度、压力数据对时间进行线性拟合时线性拟合优度r 2≥0.95。 (1) The gas in the corridor meets the requirement of "uniform change", that is, the linear fitting degree r 2 ≥ 0.95 when the gas temperature and pressure data are linearly fitted to the time within 30 minutes.
(2)环廊气体满足“稳定性”要求，泰勒展开中的常数C远小于泄漏率，即不能因为忽略泰勒展开过程中高次项导致的理论误差大于2％。(2) The gas in the ring gallery meets the requirements of "stability", and the constant C in the Taylor expansion is much smaller than the leakage rate, that is, the theoretical error caused by ignoring the high-order term in the Taylor expansion process cannot be greater than 2%.
进一步地，如图1所示，该核电站安全壳试验系统还包括：安全壳鼓包测量模块80。该安全壳鼓包测量模块80用于对安全壳内的鼓包进行测量并输出鼓包测量结果。Further, as shown in FIG. 1 , the nuclear power plant containment test system further includes: a containment bulge measurement module 80 . The containment bulge measurement module 80 is used to measure the bulge in the containment and output the bulge measurement result.
如图23所示，该安全壳鼓包测量模块80包括：安全壳鼓包测量单元801、安全壳鼓包数据传输单元802以及安全壳鼓包数据处理单元803。该安全壳鼓包测量模块80还包括：安全壳鼓包定位单元。As shown in FIG. 23 , the containment wrapping measurement module 80 includes: a containment wrapping measure unit 801 , a containment wrapping data transmission unit 802 and a containment wrapping data processing unit 803 . The containment bulge measurement module 80 further includes: a containment bulge positioning unit.
其中，安全壳鼓包定位单元用于对安全壳鼓包缺陷位置进行定位及标记。Wherein, the containment bulge positioning unit is used to locate and mark the defect position of the containment bulge.
安全壳鼓包测量单元801用于对安全壳鼓包进行采集并输出鼓包采集信号；安全壳缺陷数据传输单元接收并传输鼓包采集信号；安全壳鼓包数据处理单元803对鼓包采集信号进行处理并输出鼓包测量结果。The containment bulge measurement unit 801 is used to collect the containment bulge and output the bulge acquisition signal; the containment defect data transmission unit receives and transmits the bulge acquisition signal; the containment bulge data processing unit 803 processes the bulge acquisition signal and outputs the bulge measurement result.
一些实施例中，安全壳鼓包测量单元801包括：滑轨811、支架812、云台813、设置在云台813上的激光距离传感器814以及测距编码器815。该安全壳鼓包测量单元801还包括：定位装置。其中，激光距离传感器814用于测量钢内衬到滑轨811之间的距离(即鼓包曲线的y坐标)，测距编码器815用于测量激光距离传感器814的x坐标(即鼓包曲线的x坐标)。优选的，激光距离传感器814测量周期低于0.02s，测量距离精度优于0.3mm。测距编码器815测量周期低于0.01s，测量角度精度为0.5°。该定位装置设置在云台上，其可由海拔计和倾角计组成，用于记录标记鼓包所在安全壳钢内衬的位置。In some embodiments, the containment bulge measurement unit 801 includes: a slide rail 811 , a bracket 812 , a pan/tilt 813 , a laser distance sensor 814 and a ranging encoder 815 arranged on the pan/tilt 813 . The containment bulge measurement unit 801 further includes: a positioning device. The laser distance sensor 814 is used to measure the distance between the steel lining and the slide rail 811 (that is, the y-coordinate of the bulge curve), and the ranging encoder 815 is used to measure the x-coordinate of the laser distance sensor 814 (that is, the x-coordinate of the bulge curve). coordinate). Preferably, the measurement period of the laser distance sensor 814 is lower than 0.02s, and the measurement distance accuracy is better than 0.3mm. The measurement period of the ranging encoder 815 is less than 0.01s, and the measurement angle accuracy is 0.5°. The positioning device is set on the PTZ, which can be composed of an altimeter and an inclinometer, and is used to record the position of the steel lining of the containment shell where the marked bulge is located.
如图24所示，支架812包括第一支撑柱8121和第二支撑柱8122，第一支撑柱8121的第一端固定在安全壳一端，第一支撑柱8121的第二端与滑轨811的第一端连接；第二支撑柱8122的第一端固定在安全壳另一端，第二支撑柱8122的第二端与滑轨811的第二端连接；云台813滑动设置在滑轨811上。As shown in FIG. 24 , the bracket 812 includes a first support column 8121 and a second support column 8122 . The first end of the first support column 8121 is fixed at one end of the containment shell, and the second end of the first support column 8121 is connected to the sliding rail 811 . The first end is connected; the first end of the second support column 8122 is fixed on the other end of the containment, the second end of the second support column 8122 is connected with the second end of the slide rail 811 ; the pan/tilt 813 is slidably arranged on the slide rail 811 .
一些实施例中，该安全壳鼓包数据传输单元802包括：数据通讯模块821以及供电单元822。数据通讯模块821与安全壳鼓包测量单元801连接以 接收鼓包采集信号并传送给安全壳鼓包数据处理单元803；供电单元822用于给激光距离传感器814、测距编码器815和安全壳鼓包数据处理单元803供电。可选的，数据通讯模块821由MAX485串口模块和单片机的UART2单元构成，以实现传感器与单片机之间的通讯。In some embodiments, the safe shell data transmission unit 802 includes: a data communication module 821 and a power supply unit 822 . The data communication module 821 is connected with the containment bulge measurement unit 801 to receive the bulge acquisition signal and transmit it to the containment bulge data processing unit 803; the power supply unit 822 is used to process the laser distance sensor 814, the distance encoder 815 and the containment bulge data Unit 803 is powered. Optionally, the data communication module 821 is composed of a MAX485 serial port module and a UART2 unit of the microcontroller, so as to realize the communication between the sensor and the microcontroller.
一些实施例中，该安全壳鼓包数据处理单元803包括：对比模块831、对比分析补偿模块832、结果输出模块833；对比模块831用于对鼓包采集信号进行对比处理，输出鼓包测量数据；对比分析补偿模块832用于结合补偿数据对鼓包测量数据进行计算，获得鼓包测量结果。可选的，该安全壳鼓包数据处理单元803可以为单片机，可选的，该单片机还可以设置测试接口以供测试用，以及ISP接口以进行ISP数据传输。In some embodiments, the containment bulge data processing unit 803 includes: a comparison module 831, a comparison analysis compensation module 832, and a result output module 833; the comparison module 831 is used to perform comparison processing on the bulge acquisition signal, and output bulge measurement data; comparative analysis The compensation module 832 is configured to calculate the measurement data of the bulge in combination with the compensation data to obtain the measurement result of the bulge. Optionally, the safety shell data processing unit 803 may be a single chip microcomputer. Optionally, the single chip chip may also be provided with a test interface for testing, and an ISP interface for ISP data transmission.
一些实施例中，该安全壳缺陷测量模块还包括：显示单元804；显示单元804用于对鼓包测量结果进行显示。可选的，该显示单元804包括液晶显示屏和/或数码显示管。该安全壳缺陷测量模块还包括：传输单元，该传输单元将鼓包测量结果发送给所述安全壳强度监测模块用于修正安全壳强度监测。In some embodiments, the containment defect measurement module further includes: a display unit 804; the display unit 804 is used to display the measurement result of the bulge. Optionally, the display unit 804 includes a liquid crystal display screen and/or a digital display tube. The containment defect measurement module further includes: a transmission unit, which sends the bulge measurement result to the containment strength monitoring module for correcting containment strength monitoring.
本发明实施例的核电站安全壳试验系统解决了安全壳外观检查试验误差大，高空坠落风险高的问题；高压黑暗环境下火灾监控不及时，无法定位火灾位置和火灾规模的问题；安全壳内观检查鼓包测量精度低、抗干扰能力差、对操作人员要求高等问题；双层安全壳环廊泄漏率因内外压差过小无法直接测量的问题；内层安全壳泄漏率算法误差大的问题；逆止阀密封性试验受制于机组状态的问题；机械贯穿件试验因温度无法直测引起的泄漏率误差问题；现有试验充卸压期间，充卸压速率无法直接控制的问题；现有试验方案，强度评价需求数据采集速率低，无法实时测量，强度评价不直观，无法跟踪安全壳试验期间安全壳结构性能演变的问题。现有方案人员承压进岛造成存在人员受伤的风险的问题。The nuclear power plant containment test system of the embodiment of the present invention solves the problems of large error in the appearance inspection test of the containment and high risk of falling from high altitude; the fire monitoring is not timely in the high-pressure dark environment, and the fire location and fire scale cannot be located; the internal view of the containment Check the problems of low measurement accuracy of the bulge, poor anti-interference ability, and high requirements for operators; the leakage rate of the double-layer containment enclosure cannot be directly measured due to the too small internal and external pressure difference; the problem of large error in the algorithm of the leakage rate of the inner containment; The sealing test of the check valve is subject to the problem of the state of the unit; the leakage rate error of the mechanical penetration test due to the inability to directly measure the temperature; the problem that the charging and discharging rate cannot be directly controlled during the charging and discharging of the existing test; the existing test In the scheme, the data acquisition rate of the strength evaluation requirements is low, real-time measurement is impossible, the strength evaluation is not intuitive, and it is impossible to track the evolution of the containment structure performance during the containment test. In the existing scheme, there is a risk of personal injury due to the pressure of personnel entering the island.
通过该核电站安全壳试验系统，可实现安全壳外观缺陷的自动识别处理，优化了逆止阀试验方法及其所需特定窗口，提高了钢内衬鼓包测量精度，改进了安全壳泄漏率及其不确定测量的算法，进一步地，还改进了安全 壳体积权重分配及泄漏率计算方法，并解决了高压环境下核岛厂房火灾监控不及时的问题，提高试验的安全性及效率。Through the nuclear power plant containment test system, the automatic identification and processing of the appearance defects of the containment can be realized, the test method of the check valve and the required specific window are optimized, the measurement accuracy of the steel lining bulge is improved, and the leakage rate of the containment and its required specific window are improved. The algorithm of uncertain measurement further improves the weight distribution of the containment volume and the calculation method of the leakage rate, and solves the problem of untimely fire monitoring in the nuclear island powerhouse under the high pressure environment, improving the safety and efficiency of the test.
以上实施例只为说明本发明的技术构思及特点，其目的在于让熟悉此项技术的人士能够了解本发明的内容并据此实施，并不能限制本发明的保护范围。凡跟本发明权利要求范围所做的均等变化与修饰，均应属于本发明权利要求的涵盖范围。The above embodiments are only intended to illustrate the technical concept and characteristics of the present invention, and the purpose is to enable those skilled in the art to understand the content of the present invention and implement accordingly, and cannot limit the protection scope of the present invention. All equivalent changes and modifications made with the scope of the claims of the present invention shall fall within the scope of the claims of the present invention.

Claims (44)

  1. 一种核电站安全壳试验系统，其特征在于，包括：安全壳整体泄漏率测量模块、安全壳音响测漏模块、报警模块以及显示模块；A nuclear power plant containment test system is characterized by comprising: a containment overall leak rate measurement module, a containment sound leak detection module, an alarm module and a display module;
    所述安全壳整体泄漏率测量模块用于对安全壳内的总体泄漏率进行测量并对测量数据进行计算，获得安全壳的实时整体泄漏率和不确定度；The containment overall leakage rate measurement module is used to measure the overall leakage rate in the containment and calculate the measurement data to obtain the real-time overall leakage rate and uncertainty of the containment;
    所述安全壳音响测漏模块用于对安全壳的声音信号进行监测并对所监测到的声音信号进行分析处理后，输出安全壳音响测漏测量结果，以获得到安全壳泄漏位置及区域；The containment sound leak detection module is used to monitor the sound signal of the containment and analyze and process the monitored sound signal, and then output the sound leak detection measurement result of the containment, so as to obtain the leakage position and area of the containment;
    所述报警模块用于在所述实时整体泄漏率、所述不确定度、所述安全壳音响泄漏时，输出相应的报警信号；The alarm module is configured to output a corresponding alarm signal when the real-time overall leakage rate, the uncertainty, and the containment sound leak;
    所述显示模块用于对所述实时整体泄漏率、所述不确定度和所述安全壳音响测漏测量结果进行显示。The display module is configured to display the real-time overall leak rate, the uncertainty and the measurement result of the containment acoustic leak detection.
  2. 根据权利要求1所述的核电站安全壳试验系统，其特征在于，所述安全壳整体泄漏率测量模块包括：泄漏率测量装置、压力调节模块、压力运行模块以及计算模块；The nuclear power plant containment test system according to claim 1, wherein the overall containment leakage rate measurement module comprises: a leakage rate measurement device, a pressure regulation module, a pressure operation module and a calculation module;
    所述泄漏率测量装置用于对安全壳泄漏信号参数进行实时采集，基于所述安全壳泄漏信号参数获得泄漏数据，并对所述泄漏数据进行实时计算以获得计算结果，以及在所述计算结果满足气体稳定条件后计算实时泄漏率及其不确定度；The leakage rate measuring device is used to collect the parameters of the containment leakage signal in real time, obtain leakage data based on the parameters of the containment leakage signal, and perform real-time calculation on the leakage data to obtain a calculation result, and in the calculation result Calculate the real-time leak rate and its uncertainty after satisfying the gas stability conditions;
    所述压力调节模块用于对泄漏采集信号进行实时拟合计算处理，获得实时升压速度和实时降压速度，以及在所述实时升压速度和实时降压速度大于预设数值时，控制升降压电动调节阀开度；The pressure regulation module is used to perform real-time fitting and calculation processing on the leakage acquisition signal, obtain the real-time pressure increase speed and the real-time pressure reduction speed, and control the pressure increase when the real-time pressure increase speed and the real-time pressure reduction speed are greater than the preset values. The opening of the step-down electric regulating valve;
    所述压力运行模块用于在压力达到阈值时，控制关闭升降压电动调节阀，对安全壳内的所有参量进行监测并进行实时计算；The pressure operation module is used to control and close the buck-boost electric regulating valve when the pressure reaches the threshold value, and monitor all parameters in the containment and perform real-time calculation;
    所述计算模块用于根据所述泄漏采集信号进行计算，获得安全壳的实时整体泄漏率和不确定度。The calculation module is configured to perform calculation according to the leak acquisition signal to obtain the real-time overall leak rate and uncertainty of the containment.
  3. 根据权利要求2所述的核电站安全壳试验系统，其特征在于，所述安 全壳整体泄漏率测量模块还包括：数据仿真模块和数据显示模块；The nuclear power plant containment test system according to claim 2, wherein the containment overall leakage rate measurement module further comprises: a data simulation module and a data display module;
    所述数据仿真模块用于在安全壳试验前对所述安全壳整体泄漏率测量模块的功能进行模拟仿真，获得仿真数据；The data simulation module is used for simulating the function of the overall leakage rate measurement module of the containment to obtain simulation data before the containment test;
    所述数据显示模块用于对所述安全壳的状态信息和工作信息进行显示。The data display module is used for displaying the state information and working information of the safety shell.
  4. 根据权利要求3所述的核电站安全壳试验系统，其特征在于，所述安全壳整体泄漏率测量模块还包括：存储与打印模块；The nuclear power plant containment test system according to claim 3, wherein the overall containment leakage rate measurement module further comprises: a storage and printing module;
    所述存储与打印模块用于对所述安全壳的实时整体泄漏率和不确定度进行存储并打印输出。The storage and printing module is used for storing and printing out the real-time overall leakage rate and uncertainty of the containment vessel.
  5. 根据权利要求1所述的核电站安全壳试验系统，其特征在于，所述不确定度包括：A类不确定度和B类不确定度；所述A类不确定度包括：温度标准不确定度、湿度标准不确定度以及压力标准不确定度；所述温度标准不确定度采用分区域拟合法计算；The nuclear power plant containment test system according to claim 1, wherein the uncertainty comprises: a type A uncertainty and a type B uncertainty; the type A uncertainty comprises: a temperature standard uncertainty , humidity standard uncertainty and pressure standard uncertainty; the temperature standard uncertainty is calculated by subregional fitting method;
    所述湿度标准不确定度和所述压力标准不确定度采用分区拟合算法计算。The humidity standard uncertainty and the pressure standard uncertainty are calculated using a partition fitting algorithm.
  6. 根据权利要求2-5任一项所述的核电站安全壳试验系统，其特征在于，所述安全壳整体泄漏率测量模块还包括：贯穿件测量模块；The nuclear power plant containment test system according to any one of claims 2-5, wherein the containment overall leakage rate measurement module further comprises: a penetration measurement module;
    所述贯穿件测量模块用于对所述安全壳的贯穿件的密封性进行测量，以获得所述安全壳的贯穿件的密封性测试结果。The penetration measurement module is used for measuring the tightness of the penetration of the containment, so as to obtain the sealing test result of the penetration of the containment.
  7. 根据权利要求6所述的核电站安全壳试验系统，其特征在于，所述贯穿件测量模块包括：承压箱、单片机、显示器、设置在所述承压箱中的贯穿件测量单元和执行器；The nuclear power plant containment test system according to claim 6, wherein the penetration measurement module comprises: a pressure-bearing box, a single-chip microcomputer, a display, a penetration measurement unit and an actuator arranged in the pressure-bearing box;
    所述贯穿件测量单元进行数据采集并获得测量数据；The penetration measurement unit performs data acquisition and obtains measurement data;
    所述单片机根据试验指令以及测量数据控制所述执行器；The single-chip microcomputer controls the actuator according to the test instruction and the measurement data;
    所述执行器根据所述单片机的控制执行工作；The executor performs work according to the control of the single-chip microcomputer;
    所述显示器对所述安全壳的贯穿件的密封性测试结果进行显示。The display displays the result of the tightness test of the penetration of the containment.
  8. 根据权利要求7所述的核电站安全壳试验系统，其特征在于，所述贯穿件测量单元包括：压力传感器、温度传感器、小流量传感器、中流量传感器以及大流量传感器；所述执行器包括：设置在输入管道上的第一电磁阀、 设置在第一输入支管道上的第二电磁阀、设置在第二输入支管道上的第三电磁阀、设置在第一输出支管道上的第七电磁阀、设置在第二输出支管道上的第八电磁阀、设置在第一子管道上的第四电磁阀、设置在第二子管道上的第五电磁阀、设置在第三子管道上的第六电磁阀以及设置在输出管道上的第九电磁阀；The nuclear power plant containment test system according to claim 7, wherein the penetration measurement unit comprises: a pressure sensor, a temperature sensor, a small flow sensor, a medium flow sensor and a large flow sensor; the actuator comprises: a setting The first solenoid valve on the input pipeline, the second solenoid valve set on the first input branch pipeline, the third solenoid valve set on the second input branch pipeline, and the seventh solenoid valve set on the first output branch pipeline valve, an eighth solenoid valve arranged on the second output branch pipe, a fourth solenoid valve arranged on the first sub-pipeline, a fifth solenoid valve arranged on the second sub-pipeline, and a solenoid valve arranged on the third sub-pipeline a sixth solenoid valve and a ninth solenoid valve arranged on the output pipeline;
    所述第一子管道、所述第二子管道以及所述第三子管道并行设置，且所述第一子管道、所述第二子管道以及所述第三子管道设置在所述第一输入支管道和所述第一输出支管道之间；The first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged in parallel, and the first sub-pipeline, the second sub-pipeline and the third sub-pipeline are arranged in the first sub-pipeline between the input branch pipe and the first output branch pipe;
    所述压力传感器和所述温度传感器设置在所述第二输入支管道和所述第二输出支管道之间。The pressure sensor and the temperature sensor are arranged between the second input branch pipe and the second output branch pipe.
  9. 根据权利要求8所述的核电站安全壳试验系统，其特征在于，所述贯穿件测量模块还包括：设置在所述输入管道上且位于所述承压箱外的气体干燥过滤器；The nuclear power plant containment test system according to claim 8, wherein the penetration measurement module further comprises: a gas drying filter disposed on the input pipeline and located outside the pressure-containing box;
    所述气体干燥过滤器用于对输入所述承压箱内的气体进行干燥过滤。The gas drying filter is used for drying and filtering the gas input into the pressure-holding box.
  10. 根据权利要求2所述的核电站安全壳试验系统，其特征在于，所述安全壳整体泄漏率测量模块和安全壳强度监测模块通过自由容积法测量安全壳内自由容积，并根据安全壳内的传感器所在区域对传感器进行权重分配。The nuclear power plant containment test system according to claim 2, wherein the containment overall leakage rate measurement module and the containment strength monitoring module measure the free volume in the containment by the free volume method, and measure the free volume in the containment according to the sensor in the containment. The weights are assigned to the sensors in the region where they are located.
  11. 根据权利要求10所述的核电站安全壳试验系统，其特征在于，所述计算模块包括：安全壳参数处理模块、安全壳监测数据处理模块、最优路径计算模块、体积权重分配模块以及数据输出模块；The nuclear power plant containment test system according to claim 10, wherein the calculation module comprises: a containment parameter processing module, a containment monitoring data processing module, an optimal path calculation module, a volume weight distribution module and a data output module ;
    所述安全壳参数处理模块根据安全壳墙体尺寸数据进行建模、网格划分，获得自由空间网格数据；The containment parameter processing module performs modeling and grid division according to the containment wall size data to obtain free space grid data;
    所述安全壳监测数据处理模块根据温度传感器的位置数据和湿度传感器的位置数据进行仪表坐标网格化，获得仪表网格数据；The containment monitoring data processing module performs grid coordinate gridization of the instrument according to the position data of the temperature sensor and the position data of the humidity sensor, and obtains the grid data of the instrument;
    所述最优路径计算模块根据所述自由空间网格数据和所述仪表网格数据进行计算，获得每个仪表所代表区域的最优路径；The optimal path calculation module calculates according to the free space grid data and the meter grid data to obtain the optimal path of the area represented by each meter;
    所述体积权重分配模块根据所述最优路径进行计算，获得每个仪表体积权重；The volume weight allocation module calculates according to the optimal path to obtain the volume weight of each meter;
    所述数据输出模块输出所述每个仪表体积权重。The data output module outputs the weight of each meter volume.
  12. 根据权利要求1所述的核电站安全壳试验系统，其特征在于，所述安全壳音响测漏模块包括：声音采集模块、声音监测模块、振动监测模块以及定向传输模块；The nuclear power plant containment test system according to claim 1, wherein the containment sound leak detection module comprises: a sound acquisition module, a sound monitoring module, a vibration monitoring module and a directional transmission module;
    所述声音采集模块用于对安全壳的声音信号进行实时监测并采集，获得声音采集信号；The sound collection module is used for real-time monitoring and collection of the sound signal of the containment to obtain the sound collection signal;
    所述声音监测模块用于对所述声音采集信号进行监测并输出安全壳音响测漏测量结果；The sound monitoring module is used for monitoring the sound collection signal and outputting the sound leak detection measurement result of the containment;
    所述振动监测模块用于监测固定管道的振动数值以及阀门的工作状态；The vibration monitoring module is used to monitor the vibration value of the fixed pipeline and the working state of the valve;
    所述定向传输模块用于输出所述安全壳音响测漏测量结果和安全壳泄漏位置及区域。The directional transmission module is used for outputting the measurement result of the containment acoustic leak detection and the containment leak location and area.
  13. 根据权利要求12所述的核电站安全壳试验系统，其特征在于，所述声音监测模块包括：信号采集模块、信号分析模块以及声音放大模块；The nuclear power plant containment test system according to claim 12, wherein the sound monitoring module comprises: a signal acquisition module, a signal analysis module and a sound amplification module;
    所述信号采集模块用于对所述声音采集信号进行采集并传送给所述信号分析模块；The signal acquisition module is used to collect the sound acquisition signal and transmit it to the signal analysis module;
    所述信号分析模块用于对所述声音采集信号进行分析过滤，以获得过滤声音信号，并将所述过滤声音信号发送给所述声音放大模块；The signal analysis module is configured to analyze and filter the sound acquisition signal to obtain a filtered sound signal, and send the filtered sound signal to the sound amplification module;
    所述声音放大模块用于对所述过滤声音信号进行放大处理，获得安全壳音响测漏测量结果。The sound amplifying module is used for amplifying the filtered sound signal to obtain the sound leak detection measurement result of the containment vessel.
  14. 根据权利要求13所述的核电站安全壳试验系统，其特征在于，所述安全壳音响测漏测量结果包括：声音采集模块地址和声音数据；The nuclear power plant containment test system according to claim 13, wherein the containment sound leak detection measurement result comprises: sound acquisition module address and sound data;
    所述声音监测模块还包括：存储电路和声音传输模块；The sound monitoring module further includes: a storage circuit and a sound transmission module;
    所述存储电路用于对所述声音数据进行存储；the storage circuit is used for storing the sound data;
    所述声音传输模块用于将所述声音采集模块地址和所述声音数据输出，以获得所述安全壳泄漏位置及区域。The sound transmission module is used for outputting the address of the sound acquisition module and the sound data to obtain the leak location and area of the containment vessel.
  15. 根据权利要求14所述的核电站安全壳试验系统，其特征在于，所述声音传输模块包括：无线发射模块和无线接收模块；The nuclear power plant containment test system according to claim 14, wherein the sound transmission module comprises: a wireless transmitting module and a wireless receiving module;
    所述无线发射模块用于接收所述声音采集模块地址和所述声音数据并发 送给所述无线接收模块；Described wireless transmitting module is used for receiving described sound collecting module address and described sound data and sending to described wireless receiving module;
    所述无线接收模块用于接收所述声音采集模块地址和所述声音数据并输出。The wireless receiving module is used for receiving and outputting the address of the sound collecting module and the sound data.
  16. 根据权利要求15所述的核电站安全壳试验系统，其特征在于，所述声音监测模块还包括：振动传感器；The nuclear power plant containment test system according to claim 15, wherein the sound monitoring module further comprises: a vibration sensor;
    所述振动传感器用于监测所述声音监测模块的振动位移并在所述声音监测模块的振动位移大于预设值时，将声音监测模块的地址发送给所述无线发射模块。The vibration sensor is used to monitor the vibration displacement of the sound monitoring module and send the address of the sound monitoring module to the wireless transmitting module when the vibration displacement of the sound monitoring module is greater than a preset value.
  17. 根据权利要求12所述的核电站安全壳试验系统，其特征在于，所述定向传输模块包括：定向传输电缆；The nuclear power plant containment test system according to claim 12, wherein the directional transmission module comprises: a directional transmission cable;
    所述定向传输电线缆接收所述安全壳音响测漏测量结果并传输至安全壳外。The directional transmission cable receives the containment acoustic leak detection measurement and transmits it to the outside of the containment.
  18. 根据权利要求1所述的核电站安全壳试验系统，其特征在于，还包括：安全壳外观检查模块；The nuclear power plant containment test system according to claim 1, further comprising: a containment appearance inspection module;
    所述安全壳外观检查模块包括：爬壁机器人、地面站单元、图像获取单元、图像采集处理单元、外观数据传输单元、位置确认装置、喷涂装置以及防坠落装置；The containment appearance inspection module includes: a wall climbing robot, a ground station unit, an image acquisition unit, an image acquisition and processing unit, an appearance data transmission unit, a position confirmation device, a spraying device and an anti-fall device;
    所述爬壁机器人用于根据控制指令执行在安全壳壁面的行走动作；The wall-climbing robot is used to perform the walking action on the wall of the containment according to the control instruction;
    所述地面站单元用于收集所述安全壳的外观缺陷图像信息并对所述图像信息进行分析处理；The ground station unit is used for collecting the image information of the appearance defect of the containment and analyzing and processing the image information;
    所述图像获取单元用于对所述安全壳壁面进行扫描和拍照以获得所述安全壳壁面的图像数据；The image acquisition unit is configured to scan and photograph the containment wall to obtain image data of the containment wall;
    所述图像采集处理单元用于对所述图像数据进行采集和分析，获得所述安全壳的外观缺陷图像几何信息；The image acquisition and processing unit is configured to collect and analyze the image data to obtain the geometric information of the appearance defect image of the containment vessel;
    所述外观数据传输单元用于将所述安全壳的外观缺陷图像信息发送给所述地面站单元；The appearance data transmission unit is configured to send the appearance defect image information of the containment vessel to the ground station unit;
    所述喷涂装置用于对检测到的缺陷信息进行标记；The spraying device is used to mark the detected defect information;
    位置确认装置用于在机器人完成缺陷标记后记录并存储该缺陷的位置信 息；The position confirmation device is used to record and store the position information of the defect after the robot completes the defect marking;
    所述防坠落装置用于防止所述爬壁机器人坠落。The anti-fall device is used to prevent the wall-climbing robot from falling.
  19. 根据权利要求18所述的核电站安全壳试验系统，其特征在于，所述图像采集处理单元包括：接收和发送驱动模块、底层通讯模块、上位机界面模块、后台运行数据库模块、后台服务系统模块以及子功能模块；The nuclear power plant containment test system according to claim 18, wherein the image acquisition and processing unit comprises: a receiving and sending drive module, a bottom communication module, a host computer interface module, a background operation database module, a background service system module and sub-function module;
    所述接收和发送驱动模块用于将收发数据进行转换并传送；The receiving and sending drive modules are used to convert and transmit the received and received data;
    所述底层通讯模块用于对底层数据进行调用分配暂存；The underlying communication module is used for calling, distributing and temporarily storing underlying data;
    所述上位机界面模块用于对所述外观缺陷图像信息进行显示以及接收用户输入的操作信息；The host computer interface module is used for displaying the appearance defect image information and receiving the operation information input by the user;
    所述后台运行数据库模块用于对所述安全壳壁面的图像数据进行存储以及对用户信息进行管理；The background operation database module is used to store the image data of the containment wall and manage user information;
    所述后台服务系统用于控制协调所述子功能模块的运行。The background service system is used for controlling and coordinating the operation of the sub-function modules.
  20. 根据权利要求19所述的核电站安全壳试验系统，其特征在于，所述子功能模块包括：控制模块、定位模块、视频系统模块、图像系统模块、工具模块、菜单模块、文档标记模块、检索模块、缺陷绘制模块、存储模块以及算法模块；The nuclear power plant containment test system according to claim 19, wherein the sub-function modules include: a control module, a positioning module, a video system module, an image system module, a tool module, a menu module, a document marking module, and a retrieval module , defect drawing module, storage module and algorithm module;
    所述控制模块用于对控制命令进行整合及传递；The control module is used to integrate and transmit control commands;
    所述定位模块用于对所述爬壁机器人的位置信息进行定位并转换为与所述位置信息对应的坐标；The positioning module is used for positioning and converting the position information of the wall-climbing robot into coordinates corresponding to the position information;
    所述视频系统模块用于将无线传送至所述地面站单元的外观缺陷图像信息中的视频信息进行编码并转换为视频流；The video system module is used to encode and convert the video information in the appearance defect image information wirelessly transmitted to the ground station unit into a video stream;
    所述图像系统模块用于对带有外观缺陷的图像进行拍照放大及分析；The image system module is used for photographing, magnifying and analyzing images with appearance defects;
    所述工具模块用于提供外观检查工具；The tool module is used to provide a visual inspection tool;
    所述菜单模块用于与控制指令和/或转换指令结合；The menu module is used to combine with control instructions and/or conversion instructions;
    所述文档标记模块用于将缺陷数据进行整合；The document marking module is used to integrate defect data;
    所述检索模块用于进行数据检索及数据调配；The retrieval module is used for data retrieval and data allocation;
    所述缺陷绘制模块用于将外观缺陷图像信息进行二维图像重绘；The defect drawing module is used to redraw the two-dimensional image of the appearance defect image information;
    所述存储模块用于对所述外观缺陷图像信息进行存储；The storage module is used for storing the appearance defect image information;
    所述算法模块用于对所述安全壳壁面的图像数据进行缺陷识别分析计算，获得所述安全壳的外观缺陷图像几何信息。The algorithm module is used to perform defect identification, analysis and calculation on the image data of the containment wall surface, and obtain the geometric information of the appearance defect image of the containment vessel.
  21. 根据权利要求1所述的核电站安全壳试验系统，其特征在于，还包括：火灾监测模块；The nuclear power plant containment test system according to claim 1, further comprising: a fire monitoring module;
    所述火灾监测模块用于对安全壳进行火灾监测并输出火灾监测信息。The fire monitoring module is used for carrying out fire monitoring on the containment and outputting fire monitoring information.
  22. 根据权利要求21所述的核电站安全壳试验系统，其特征在于，所述火灾监测模块包括：多个热像仪、气体传感器、烟雾传感器、设置在安全壳上的电气贯穿件以及传输线缆；The nuclear power plant containment test system according to claim 21, wherein the fire monitoring module comprises: a plurality of thermal imagers, gas sensors, smoke sensors, electrical penetrations provided on the containment, and transmission cables;
    所述多个热像仪用于对安全壳内的温度进行监测并输出火灾监测信息；The plurality of thermal imagers are used for monitoring the temperature in the containment and outputting fire monitoring information;
    所述气体传感器用于监测安全壳内的气体信息；The gas sensor is used for monitoring gas information in the containment;
    所述烟雾传感器用于监测安全壳内的烟雾信息；The smoke sensor is used for monitoring smoke information in the containment;
    所述传输线缆接收所述火灾监测信息、气体信息和烟雾信息并通过所述电气贯穿件传输至所述安全壳外，以及将所述热像仪和气体传感器电源由安全壳外传输至安全壳内。The transmission cable receives the fire monitoring information, gas information and smoke information and transmits it to the outside of the containment through the electrical penetration, and transmits the thermal imager and gas sensor power from outside the containment to the safety inside the shell.
  23. 根据权利要求22所述的核电站安全壳试验系统，其特征在于，每一个所述热像仪内置于防护罩中，所述防护罩为不锈钢防护罩；所述烟雾传感器通过气体引漏管进行测量。The nuclear power plant containment test system according to claim 22, wherein each of the thermal imaging cameras is built in a protective cover, and the protective cover is a stainless steel protective cover; the smoke sensor measures through a gas leakage pipe .
  24. 根据权利要求23所述的核电站安全壳试验系统，其特征在于，所述防护罩包括外壳以及设置在所述外壳底部的密封性试验接口；所述热像仪内置于所述外壳中并通过所述密封性试验接口进行密封性试验。The nuclear power plant containment test system according to claim 23, wherein the protective cover comprises an outer shell and a sealing test interface arranged at the bottom of the outer shell; the thermal imager is built in the outer shell and passes through all the Carry out the tightness test on the tightness test interface described above.
  25. 根据权利要求1所述的核电站安全壳试验系统，其特征在于，还包括：主回路逆止阀泄漏率监测模块；The nuclear power plant containment test system according to claim 1, further comprising: a main loop check valve leakage rate monitoring module;
    所述主回路逆止阀泄漏率监测模块用于对主回路逆止阀泄漏率进行监测并输出主回路逆止阀泄漏率监测结果。The main loop check valve leakage rate monitoring module is used for monitoring the main loop check valve leakage rate and outputting the main loop check valve leakage rate monitoring results.
  26. 根据权利要求25所述的核电站安全壳试验系统，其特征在于，所述主回路逆止阀泄漏率监测模块包括：逆止阀封堵装置；所述逆止阀封堵装置包括阀腔、密封气囊、充压单元以及监测单元；The nuclear power plant containment test system according to claim 25, wherein the main loop check valve leakage rate monitoring module comprises: a check valve plugging device; the check valve plugging device comprises a valve cavity, a seal Airbag, charging unit and monitoring unit;
    所述充压单元用于向所述逆止阀的阀腔内充压或者所述密封气囊充压；The charging unit is used for charging the valve cavity of the check valve or the sealing airbag;
    所述监测单元用于监测所述逆止阀的充压数据，根据所述充压数据计算所述逆止阀的泄漏率；The monitoring unit is used to monitor the charging data of the check valve, and calculate the leakage rate of the check valve according to the charging data;
    根据所述逆止阀的泄漏率输出主回路逆止阀泄漏率监测结果。According to the leakage rate of the check valve, the leakage rate monitoring result of the check valve of the main circuit is output.
  27. 根据权利要求26所述的核电站安全壳试验系统，其特征在于，所述充压单元包括：第一充压装置和第二充压装置；The nuclear power plant containment test system according to claim 26, wherein the charging unit comprises: a first charging device and a second charging device;
    所述第一充压装置用于向所述逆止阀的阀腔内充压并采集阀腔的压力数据；The first pressurizing device is used to pressurize the valve cavity of the check valve and collect pressure data of the valve cavity;
    所述第二充压装置用于向所述密封气囊充压并采集密封气囊的压力数据。The second inflating device is used for inflating the sealing airbag and collecting pressure data of the sealing airbag.
  28. 根据权利要求27所述的核电站安全壳试验系统，其特征在于，所述充压数据包括：所述阀腔的压力数据和所述密封气囊的压力数据；The nuclear power plant containment test system according to claim 27, wherein the charging data comprises: pressure data of the valve cavity and pressure data of the airtight airbag;
    所述第一充压装置包括：第一充气气囊、第一阀门以及第一压力表；所述第二充压装置包括：第二充气气囊、第二阀门以及第二压力表；The first inflating device includes: a first inflatable air bag, a first valve and a first pressure gauge; the second inflatable device includes: a second inflatable air bag, a second valve and a second pressure gauge;
    所述第一充气气囊用于向所述阀腔内充压；the first inflatable air bag is used to inflate the valve cavity;
    所述第一压力表用于在所述第一充气气囊充压过程中采集所述阀腔的压力数据；the first pressure gauge is used to collect pressure data of the valve cavity during the inflation of the first inflatable airbag;
    所述第一阀门在所述第一充气气囊充压时打开；the first valve is opened when the first inflatable air bag is inflated;
    所述第二充气气囊用于向所述密封气囊充压；the second inflatable airbag is used to inflate the sealing airbag;
    所述第二压力表用于在所述第二充气气囊充压过程中采集所述密封气囊的压力数据；The second pressure gauge is used to collect pressure data of the sealed airbag during the inflation of the second inflatable airbag;
    所述第二阀门在所述第二充气气囊充压时打开。The second valve opens when the second inflation bladder is inflated.
  29. 根据权利要求27所述的核电站安全壳试验系统，其特征在于，所述逆止阀封堵装置还包括：位于所述阀腔开口处以使所述阀腔形成密闭空间的阀盖。The nuclear power plant containment test system according to claim 27, wherein the check valve blocking device further comprises: a valve cover located at the opening of the valve cavity so that the valve cavity forms a closed space.
  30. 根据权利要求27所述的核电站安全壳试验系统，其特征在于，所述逆止阀封堵装置还包括：位于所述阀腔内以平衡阀腔内的轴向力的轴向平衡装置。The nuclear power plant containment test system according to claim 27, wherein the check valve blocking device further comprises: an axial balance device located in the valve cavity to balance the axial force in the valve cavity.
  31. 根据权利要求1所述的核电站安全壳试验系统，其特征在于，还包 括：安全壳强度监测模块；The nuclear power plant containment test system according to claim 1, further comprising: a containment strength monitoring module;
    所述安全壳强度监测模块用于对所述安全壳强度进行监测并输出强度监测数据。The containment strength monitoring module is used for monitoring the strength of the containment and outputting strength monitoring data.
  32. 根据权利要求31所述的核电站安全壳试验系统，其特征在于，所述安全壳强度监测模块包括：强度监测数据采集装置、EAU自动读数模块以及无线通信模块；The nuclear power plant containment test system according to claim 31, wherein the containment strength monitoring module comprises: a strength monitoring data acquisition device, an EAU automatic reading module and a wireless communication module;
    所述强度监测数据采集装置用于对安全壳的强度数据进行采集，获得安全壳强度监测数据；The strength monitoring data acquisition device is used for collecting the strength data of the containment to obtain the strength monitoring data of the containment;
    所述EAU自动读数模块用于对所述安全壳强度监测数据进行读取并输出；The EAU automatic reading module is used to read and output the containment strength monitoring data;
    所述无线通信模块用于对所述安全壳强度监测数据进行传输。The wireless communication module is used for transmitting the monitoring data of the containment strength.
  33. 根据权利要求32所述的核电站安全壳试验系统，其特征在于，所述强度监测数据采集装置包括：热电偶、声频应变计、水准盒、变位计以及铅垂线监测设备；The nuclear power plant containment test system according to claim 32, wherein the strength monitoring data acquisition device comprises: a thermocouple, an audio frequency strain gauge, a level box, a displacement gauge and a plumb line monitoring device;
    所述热电偶用于采集热电偶数据；The thermocouple is used to collect thermocouple data;
    所述声频应变计用于采集安全壳的形变应力并获得形变应力数据；The audio frequency strain gauge is used to collect the deformation stress of the containment and obtain the deformation stress data;
    所述水准盒用于采集安全壳的变形位移并获得变形位移数据；The level box is used to collect the deformation displacement of the containment and obtain the deformation displacement data;
    所述变位计连接所述水准盒和地形基准点，用于获得大地基准点和安全壳筏基之间在试验期间的相对变化数据；The displacement gauge is connected to the level box and the terrain reference point, and is used to obtain relative change data between the geodetic reference point and the containment raft during the test;
    所述铅垂线监测设备用于监测安全壳的铅垂线形变并获得铅垂线数据。The plumb line monitoring device is used to monitor plumb line deformation of the containment and obtain plumb line data.
  34. 根据权利要求32所述的核电站安全壳试验系统，其特征在于，所述安全壳强度监测模块还包括：铅垂线数据采集模块；The nuclear power plant containment test system according to claim 32, wherein the containment strength monitoring module further comprises: a plumb line data acquisition module;
    所述铅垂线数据采集模块用于接收所述铅垂线监测设备采集的铅垂线数据并输出。The plumb line data acquisition module is used for receiving and outputting plumb line data collected by the plumb line monitoring equipment.
  35. 根据权利要求33所述的核电站安全壳试验系统，其特征在于，所述EAU自动计数模块包括：EAU自动读数箱、三通适配箱以及EAU自动读数装置；The nuclear power plant containment test system according to claim 33, wherein the EAU automatic counting module comprises: an EAU automatic reading box, a three-way adapter box and an EAU automatic reading device;
    所述EAU自动读数箱读取所述热电偶采集的热电偶数据、所述声频应变 计采集的形变应力数据以及所述水准盒采集的变形位移数据，并将所述热电偶数据、所述形变应力数据和所述变形位移数据发送给所述三通适配箱；The EAU automatic reading box reads the thermocouple data collected by the thermocouple, the deformation stress data collected by the audio frequency strain gauge, and the deformation displacement data collected by the level box, and converts the thermocouple data, the deformation The stress data and the deformation displacement data are sent to the three-way adapter box;
    所述三通适配箱接收协调所述水准盒采集的变形位移数据，并将所述热电偶数据、所述形变应力数据和所述变形位移数据并传送至所述EAU自动读数装置；The three-way adapter box receives and coordinates the deformation displacement data collected by the level box, and transmits the thermocouple data, the deformation stress data and the deformation displacement data to the EAU automatic reading device;
    所述EAU自动读数装置接收所述水准盒采集的变形位移数据，并将所述热电偶数据、所述形变应力数据和所述变形位移数据并进行转换处理后发送给所述无线通信模块。The EAU automatic reading device receives the deformation displacement data collected by the level box, and sends the thermocouple data, the deformation stress data and the deformation displacement data to the wireless communication module after conversion processing.
  36. 根据权利要求1所述的核电站安全壳试验系统，其特征在于，还包括：外层安全壳测量模块；The nuclear power plant containment test system according to claim 1, further comprising: an outer containment measurement module;
    所述外层安全壳测量模块对外层安全壳密封性进行测量并输出密封性测量结果。The outer containment measuring module measures the tightness of the outer containment and outputs the tightness measurement result.
  37. 根据权利要求36所述的核电站安全壳试验系统，其特征在于，所述外层安全壳测量模块包括：安全壳监测模块、流量控制器、采集器以及工控机；The nuclear power plant containment test system according to claim 36, wherein the outer containment measurement module comprises: a containment monitoring module, a flow controller, a collector and an industrial computer;
    所述安全壳监测模块用于采集外层安全壳的气体信息；The containment monitoring module is used for collecting gas information of the outer containment;
    所述流量控制器用于控制注入流量并采集流量数据；The flow controller is used to control the injection flow and collect flow data;
    所述采集器对所述外层安全壳数据和所述流量数据进行采集并发送给所述工控机；The collector collects the outer containment data and the flow data and sends the data to the industrial computer;
    所述工控机对所述外层安全壳数据、所述流量数据进行分析处理，并输出所述密封性测量结果。The industrial computer analyzes and processes the outer containment data and the flow data, and outputs the tightness measurement result.
  38. 根据权利要求37所述的核电站安全壳试验系统，其特征在于，所述外层安全壳测量模块还包括：显示器；The nuclear power plant containment test system according to claim 37, wherein the outer containment measurement module further comprises: a display;
    所述显示器接收所述密封性测量结果并显示。The display receives and displays the tightness measurement.
  39. 根据权利要求31所述的核电站安全壳试验系统，其特征在于，还包括：安全壳鼓包测量模块；The nuclear power plant containment test system according to claim 31, further comprising: a containment bulge measurement module;
    所述安全壳鼓包测量模块用于对安全壳内的鼓包进行测量并输出鼓包测量结果。The containment bulge measurement module is used to measure the bulge in the containment and output the bulge measurement result.
  40. 根据权利要求39所述的核电站安全壳试验系统，其特征在于，所述安全壳鼓包测量模块包括：安全壳鼓包定位单元、安全壳鼓包测量单元、安全壳鼓包数据传输单元以及安全壳鼓包数据处理单元；The nuclear power plant containment test system according to claim 39, wherein the containment bulge measurement module comprises: a containment bulge positioning unit, a containment bulge measurement unit, a containment bulge data transmission unit, and a containment bulge data processing unit unit;
    所述安全壳鼓包定位单元用于对安全壳鼓包缺陷位置进行定位及标记；The containment bulge positioning unit is used to locate and mark the defect position of the containment bulge;
    所述安全壳鼓包测量单元用于对安全壳鼓包进行采集并输出鼓包采集信号；The containment bulge measurement unit is used to collect the containment bulge and output the bulge acquisition signal;
    所述安全壳缺陷数据传输单元接收并传输所述鼓包采集信号；The containment defect data transmission unit receives and transmits the bulge acquisition signal;
    所述安全壳鼓包数据处理单元对所述鼓包采集信号进行处理并输出鼓包测量结果。The containment bulge data processing unit processes the bulge acquisition signal and outputs the bulge measurement result.
  41. 根据权利要求40所述的核电站安全壳试验系统，其特征在于，所述安全壳鼓包测量单元包括：定位装置、滑轨、支架、云台、设置在所述云台上的激光距离传感器以及测距编码器；The nuclear power plant containment test system according to claim 40, wherein the containment bulge measurement unit comprises: a positioning device, a slide rail, a bracket, a pan/tilt, a laser distance sensor provided on the pan/tilt, and a measuring unit. distance encoder;
    所述支架包括第一支撑柱和第二支撑柱，所述第一支撑柱的第一端固定在所述安全壳一端，所述第一支撑柱的第二端与所述滑轨的第一端连接；所述第二支撑柱的第一端固定在所述安全壳另一端，所述第二支撑柱的第二端与所述滑轨的第二端连接；所述云台滑动设置在所述滑轨上；The bracket includes a first support column and a second support column, the first end of the first support column is fixed at one end of the containment, and the second end of the first support column is connected to the first end of the slide rail. The first end of the second support column is fixed on the other end of the containment shell, and the second end of the second support column is connected with the second end of the slide rail; the pan/tilt is slidably arranged at the on the slide rail;
    所述定位装置设置在所述云台上。The positioning device is arranged on the pan/tilt.
  42. 根据权利要求41所述的核电站安全壳试验系统，其特征在于，所述安全壳鼓包数据传输单元包括：数据通讯模块以及供电单元；The nuclear power plant containment test system according to claim 41, wherein the containment bulge data transmission unit comprises: a data communication module and a power supply unit;
    所述数据通讯模块与所述安全壳鼓包测量单元连接以接收所述鼓包采集信号并传送给所述安全壳鼓包数据处理单元；The data communication module is connected with the containment bulge measurement unit to receive the bulge acquisition signal and transmit it to the containment bulge data processing unit;
    所述供电单元用于给所述激光距离传感器、所述测距编码器和所述安全壳鼓包数据处理单元供电。The power supply unit is used for supplying power to the laser distance sensor, the distance measuring encoder and the safety shell bulging data processing unit.
  43. 根据权利要求42所述的核电站安全壳试验系统，其特征在于，所述安全壳鼓包数据处理单元包括：对比模块、对比分析补偿模块、结果输出模块；The nuclear power plant containment test system according to claim 42, wherein the containment bulge data processing unit comprises: a comparison module, a comparison analysis compensation module, and a result output module;
    所述对比模块用于对所述鼓包采集信号进行对比处理，输出鼓包测量数据；The comparison module is used to compare and process the bulge acquisition signal, and output the bulge measurement data;
    所述对比分析补偿模块用于结合补偿数据对所述鼓包测量数据进行计算，获得鼓包测量结果。The comparative analysis and compensation module is used to calculate the bulge measurement data in combination with the compensation data to obtain the bulge measurement result.
  44. 根据权利要求43所述的核电站安全壳试验系统，其特征在于，所述安全壳缺陷测量模块还包括：显示单元及传输单元；The nuclear power plant containment test system according to claim 43, wherein the containment defect measurement module further comprises: a display unit and a transmission unit;
    所述显示单元用于对所述鼓包测量结果进行显示；The display unit is used to display the measurement result of the bulge;
    所述传输单元将所述鼓包测量结果发送给所述安全壳强度监测模块用于修正安全壳强度监测。The transmission unit sends the bulge measurement result to the containment strength monitoring module for correcting containment strength monitoring.
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