CN104464851A - Device and method for monitoring thermal fatigue prototype of loop high-temperature pipeline in nuclear power plant - Google Patents
Device and method for monitoring thermal fatigue prototype of loop high-temperature pipeline in nuclear power plant Download PDFInfo
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- CN104464851A CN104464851A CN201410788725.1A CN201410788725A CN104464851A CN 104464851 A CN104464851 A CN 104464851A CN 201410788725 A CN201410788725 A CN 201410788725A CN 104464851 A CN104464851 A CN 104464851A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a device and a method for monitoring a thermal fatigue prototype of a loop high-temperature pipeline in a nuclear power plant, which can be used for monitoring thermal fatigue behaviors of the high-temperature pipeline in the nuclear power plant. A background server of the monitoring device is electrically connected with one or more exterior data storage servers, each exterior data storage server is electrically connected with one or more data acquisition modules, each data acquisition module is electrically connected with a plurality of data acquisition sensors, and a transmission cable is applied to reinforcement and shielding protection. The monitoring device assists in measuring temperature change data and in-pipe fluid flow of the loop high-temperature pipeline in the nuclear power plant during a running stage, and is also capable of transmitting and storing the data into a monitoring center, thereby providing data support for following thermal stress calculation, fatigue damage evaluation and life extension analysis of the pipeline.
Description
Technical field
The present invention relates to a kind of for one loop of nuclear power station high-temperature pipe heat fatigue prototype monitoring device and monitoring method thereof, can be used for the Real-Time Monitoring of operation phase nuclear power station high-temperature pipe thermal fatigue behavior in place.
Background technology
Power industry is the important industry involved the interests of the state and the people.Along with the cost of conventional power generation usage pattern increases and environmental impact, nuclear energy will increase in the proportion of energy structure as a stable clean energy resource.The security of nuclear power station and economy are most important two aim parameters.The pipeline of one loop of nuclear power station works for a long time under the complex environment of high temperature, high pressure, strong irradiation and high vibration, and when the valve of nuclear power station starts suddenly or leakage phenomenon occurs, in high-temperature pipe, the temperature of fluid, flow velocity and pressure can have greatly changed.Can there is the phenomenon such as thermal shock or thermally stratified layer in the unexpected change of this temperature, also in the branch pipe(tube) be connected with main pipeline, turbulent flow penetration phenomenon may occur in the duct simultaneously.The phenomenons such as thermal shock, thermally stratified layer and turbulent flow intrusion all can make to produce in the time in the region that pipeline is less and shorter very large temperature fluctuation, thus form larger thermal stress fluctuation.At temperature and stress long term, the microstructure of pipeline material, mechanical property, heat resistance, physical property all can change lentamente, and form the Thermal Fatigue Damage of pipeline, the phenomenon of Cracking Failure finally may appear in pipeline.
For the heat fatigue phenomenon of one loop of nuclear power station high-temperature pipe, scientific research institution both domestic and external and production unit have carried out a large amount of research work, have accumulated some significant achievements in research.But be substantially all based in laboratory in existing research and carry out model investigation, or use software to carry out numerical simulation study, these methods often all cannot reflect the actual response of structure under real working condition.
Summary of the invention
In order to overcome the defect of prior art, the invention provides a kind of for one loop of nuclear power station high-temperature pipe heat fatigue prototype monitoring device and monitoring method thereof, this monitoring device, by laying temperature sensor monitors pipeline outer wall temperature variation in the rational position of pipeline outer wall, utilizes the fluctuations in discharge of each main pipeline of flowmeter survey and lateral.Judge based on prototype monitoring data the phenomenon type causing pipeline thermal fatigue, calculated true temperature field and the stress field of pipeline by certain method, for pipeline thermal Fatigue Damage Assessment and life extension analysis provide Data support.
The present invention adopt technical scheme be: a kind of be used for one loop of nuclear power station high-temperature pipe heat fatigue prototype monitoring device, comprise background server, External data storage server, data acquisition module and data sampling sensor, described background server is electrically connected one or several External data storage server by data transmission cable with bus form or distribution form, each External data storage server is electrically connected one or more data acquisition module by data transmission cable with bus form or distribution form, each data acquisition module is electrically connected multiple data sampling sensor by transmission cable with bus form or distribution form, transmission cable carries out reinforcing and shielding protection, described data sampling sensor adopts the thermocouple temperature sensor being arranged on pipe temperature measuring point surface and the flow sensor be arranged on pipeline flow measuring point, installs 2-8 thermocouple temperature sensor on each pipe temperature measuring point surface.
A kind of monitoring method implementation step for one loop of nuclear power station high-temperature pipe heat fatigue prototype monitoring device comprises:
(1) type selecting of monitoring sensor
The model of temperature sensor is selected to meet measurement range, measuring accuracy and long-time stability requirement, and select armoured thermocouple temperature sensor, pipeline fluid flow utilizes the existing flowmeter of primary Ioops high-temperature pipe;
(2) installation site of monitoring sensor on one loop of nuclear power station high-temperature pipe
According to the numerical simulation result of one loop of nuclear power station pipeline thermal fluid flow operating mode, specify emphasis monitoring position, avoid weld seam and heavy wall labyrinth region according to the actual conditions at scene simultaneously, find temperature compensation point in its vicinity, thus determine the final installation site of temperature sensor on pipeline;
(3) monitoring sensor is at the cloth point mode of high-temperature pipe outer wall
Adopt pipeline outer wall to lay the measuring method of temperature sensor, according to carrying out practically situation, simultaneously in conjunction with the numerical simulation result of fluid, determine the heat flow behavior type causing pipeline thermal fatigue, determine that monitoring sensor is layouted number;
(4) data acquisition of monitoring sensor and transmission form
The temperature sensor being arranged in pipeline outer wall, in real time by the data acquisition module near transmitting measured values to measuring point, is distributed in on-the-spot one or more data acquisition modules and sends data to External data storage server by bus form or distribution form;
(5) Integrated Solution of monitoring sensor
Multiple temperature sensor and flowmeter are integrated in a set of monitoring system simultaneously, and the temperature data be kept in External data storage server shows in real time, carry out synchronously integrated with background server;
(6) thermal stress of Monitoring Data calculates and stores
Pipeline outer wall temperature measurement result is utilized to combine the traffic behavior information of monitoring pipeline, calculate thermal stress and the behavior of thermal stress time variations of pipeline key point fast, adopt background server to store for outside wall temperature, pipeline flow and the inner wall temperature calculated, inner surface heat stress, the thermal stress data of storage carry out Fatigue Damage Assessment and life extension analysis for primary Ioops.
Above-mentioned technical scheme ultimate principle is: in nuclear power station operational process under some special operation conditions, need to inject a large amount of hot water (cold water) being formed in the pipeline under homeostasis, if two kinds of liquid temperature differentials are very large and injection rate is very fast, the temperature of inner-walls of duct can change rapidly, and thermal shock phenomenon occurs.Thermal shock makes pipeline surfaces externally and internally produce the very large temperature difference, make the stress value on inner-walls of duct surface close to or exceed the initial yield limit of material.When there is the crossing of two kinds of fluids in pipeline, due to the fluid density difference that temperature difference causes on gravity direction, cause cold fluid to be in below, the flowing lamination that hot fluid is in top is just thermally stratified layer.Thermally stratified layer will produce larger thermograde in the region that inner-walls of duct is less, forms high thermal stress region.In three-way pipeline, if branch pipe(tube) is bend pipe, the cold fluid stagnant flow simultaneously in branch pipe(tube), then the hot fluid flowed in main pipeline will form turbulent flow in interface area, invade in the fluid of branch pipe(tube) stagnant flow the temperature field producing into gradient distribution.When this heat distribution is penetrated into the horizontal segment of arm, thermally stratified layer can be produced at horizontal segment.By installing prototype monitoring device on one loop of nuclear power station high-temperature pipe, the temperature variation of measuring channel key position tube wall and the fluctuations in discharge of tube fluid, can realize causing three kinds of thermal behaviors of heat fatigue to carry out on-line monitoring.
The invention has the beneficial effects as follows: can while nuclear power station is normally produced, ensure to carry out real-time prototype monitoring to operating high-temperature pipe, the temperature of each pipeline key position of timely reflection and fluctuations in discharge situation, deepen understanding to heat fatigue mechanism of production, and calculate the temperature field of pipeline key position, stress field and fatigue damage degree according to Monitoring Data for follow-up technical support is provided.
Accompanying drawing explanation
Fig. 1 is the process flow diagram of monitoring device design proposal.
Fig. 2 is the installation site of monitoring device on one loop of nuclear power station high-temperature pipe.
Fig. 3 is three kinds of types of attachment of pipeline.
Fig. 4 is the laying mode of temperature sensor at pipeline outer wall.
Fig. 5 is monitoring device collection, transmission and integrated one-piece construction figure.
Embodiment
Below in conjunction with drawings and Examples, the specific embodiment of the present invention is described in further detail.
Fig. 1 is the process flow diagram of monitoring device design proposal.This flow process is divided into 6 parts, comprise Choice of Sensors, installation site chosen, patten's design of layouting, data acquisition and transmission form, multiple-sensor integration scheme, Monitoring Data thermal stress calculate and storage means.
The type selecting of sensor because be aimed at high-temperature pipe cause the thermal behavior of heat fatigue to carry out monitoring, the temperature variation of pipeline is the key element of whole monitoring.Because the safety standard standard of nuclear power field high-temperature pipe is high, do not allow the installation carrying out sensor at inner-walls of duct.Meanwhile, the inside of high-temperature pipe is generally all faced with the complex environments such as high temperature, high pressure, high radiation and strong vibration, and temperature sensor is difficult to keep long-continued work, and the sensor being installed on pipe interior also cannot carry out safeguarding and replacing.Therefore the sensor of monitor temperature can only be arranged on pipeline outer wall, carries out indirect inspection to inner wall temperature.Industrial temperature sensor generally has thermopair and thermal resistance two kinds, and relative to the medial temperature in thermoelectricity resistance type sensor measurement space, what thermocouple sensor was measured is " point " temperature, the solid surface temperature that more suitable measuring channel outer wall is such.The repdocutbility of N-type thermopair long-time stability and short term thermal circulation is good, resistance to nuclear radiation and resistance to low temperature, meets Nuclear piping environment and uses.Simultaneously armoured thermocouple can bend, high pressure resistant, thermal response time is fast and sturdy and durable.Therefore monitoring sensor selects N-type armoured thermocouple temperature sensor.In order to carry out deep research to the thermal behavior of high-temperature pipe, while monitor temperature change, also need the fluctuations in discharge situation considering fluids within pipes.The security implication of installation to high-temperature pipe of flowmeter is large, near the valve of original pipeline, generally all flowmeter is installed simultaneously, therefore pipeline fluid flow utilizes the original flowmeter of primary Ioops high-temperature pipe to measure, enter integrated for flowmeter in whole heat fatigue monitoring system, become a part for monitoring device.
Due to the restriction of economic factors and nuclear power special dimension, in all positions, mounting temperature sensor is unpractical.So need to choose the abundantest key position of temperature information, and arrange that minimum temperature sensor carrys out the temperature variation situation of reacting pipe as far as possible, reach best recognition effect to make layouting of sensor.The installation site of monitoring device is chosen at and causes the thermal behavior of heat fatigue that position or neighbouring compensated position occur.Heat fluctuation may have thermally stratified layer, thermal shock or turbulent flow intrusion to cause.According to the connection arrangement of one loop of nuclear power station high-temperature pipe, and the difference of heat fluctuation Producing reason, choose different installation sites.The experience accumulated for many years according to nuclear power station and numerical simulation result, heat fatigue monitoring location great majority are positioned at position near the nozzle position of the pipelines such as primary Ioops main pipeline, Pressurizer surge line, feed pipe and shower or valve.
Fig. 2 is the sensor mounting location of certain one loop of nuclear power station high-temperature pipe connected mode and design.In Fig. 2, Roman number mark is the major equipment of one loop of nuclear power station, I be nuclear reactor, II is wherein voltage stabilizer, III is steam generator, IV is cooling medium pump.In Fig. 2 arabic numeral mark some the branch pipe(tube) titles being primary Ioops main pipeline and being connected, wherein 1 for cold section of main pipeline, 2 for main pipe hot leg, 3 for fluctuation pipeline, 4 for coolant lines, 5 for Safety Injection pipeline, 6 for pressure accumulation inject pipeline, 7 for Residual heat removal pipeline, 8 on fill pipeline, 9 for letdown line, 10 for auxiliary spray line, 11 for spray pipe, 12 for vapour line, 13 for water-supply line, 14 be auxiliary feedwater pipeline.In figure, the position of circle mark is the feature locations (welded seam area and heavy wall labyrinth region are avoided in actual installation position) of listed monitoring point, and main region includes near the intersectional region of each nozzle position of main pipeline and Surge line piping, each branch pipe(tube) and main pipeline, each branch pipe(tube) valve location.
Fig. 3 is three kinds of types of attachment of pipeline.(a) figure in Fig. 3 is generally the mode that main pipeline is connected with high pressure branch road, under the long term of high pressure, if valve generation seepage, the heat fatigue then occurred in a-quadrant is comparatively serious, and (a-quadrant is 5 < L/D < 20, wherein D is the diameter of branch pipe(tube), L is the degree of depth of a mouth of pipe to valve direction, and L is no more than valve).(b) figure in Fig. 3 is the connected mode of main pipeline with branch pipe(tube) level, heat fatigue mainly occurs in B region, and (B region is 5 < L/D < 20, wherein D is the diameter of branch pipe(tube), and L is the degree of depth of a mouth of pipe to valve direction, and L is no more than valve).(c) figure in Fig. 3 is generally the mode that main pipeline is connected with low pressure branch pipe(tube), under the effect that long-term turbulent flow invades, the heat fatigue occurred in C region is comparatively serious, and (C region is L/D < 20, wherein D is the diameter of branch pipe(tube), L is the degree of depth of a mouth of pipe to valve direction, and L is no more than valve).
Fig. 4 is the laying mode of temperature sensor at pipeline outer wall.Sensor is fixed by a set of special fixture and is close to pipe under test outer wall.Multiple temperature sensor (list 7 sensors in figure, can lay 1-8 according to pipeline thermal behavior in actual installation, point position is determined by calculating) is arranged in pipeline outer wall one side position uniformly.When heat fluctuation behaviors such as pipe interior generation valve opening, valve leaks, turbulent flow intrusion, thermally stratified layers, the change of temperature field situation of pipe interior fluid after the temperature of the point position that temperature sensor is corresponding is calculated by certain method, substantially can be depicted.When pipe interior generation thermal shock behavior, only need two sensors can monitor thermal shock behavior.
Fig. 5 is the collection of monitoring system and monitoring device, transmission and integrated one-piece construction figure.Monitoring device comprises 4 parts, and the Ith part is background server, and the IIth part is External data storage server, and the IIIth part is data acquisition module, and the IVth part is data sampling sensor.Wherein background server is electrically connected one or several External data storage server by data transmission cable with bus form or distribution form, each External data storage server is electrically connected one or more data acquisition module by data transmission cable with bus form or distribution form, and each data acquisition module is electrically connected multiple data sampling sensor by transmission cable with bus form or distribution form.
The data acquisition module of temperature data real-time Transmission near measuring point that the temperature sensor being arranged in pipeline outer wall will collect, on-the-spot data acquisition module has the function that signal is changed and data are tentatively preserved.Be distributed in on-the-spot one or more data acquisition modules by bus form or distribution form, Simultaneous Transmission of Data to External data storage server to be carried out classifying and preserving.Due to the environment more complicated (radiation, high temperature, vibration) at scene, need to reinforce and shielding protection to transmission cable.
By designing the Integrated Solution of one loop of nuclear power station high-temperature pipe heat fatigue prototype monitoring device, realizing multisensor and jointly measuring in real time, transmit and preserve.Each sensor temperature data be kept in External data storage server also can carry out by integrated real-time display of classifying, can also carry out synchronously integrated with background server, the aim parameter that the site operation personnels such as the thermal stress of fast and easy calculating pipeline and For The Degree of Thermal Fatigue Damage pay close attention to more simultaneously.
The pipeline outer wall temperature measurement result that monitoring device collects combines the traffic behavior of monitoring pipeline, adopts back analysis algorithm, calculates the thermal stress of pipeline key point and the time variations of thermal stress fast.Background server stores for outside wall temperature, pipeline flow and the inner wall temperature calculated, built-in thermal stress.
While nuclear power station is normally produced, can carry out real-time prototype monitoring to operating high-temperature pipe by the present invention, the temperature variations of each pipeline key position of reflection, deepens the understanding to heat fatigue mechanism of production in time.The temperature data monitored and data on flows, in conjunction with the temperature field calculated, stress field, can for carrying out Fatigue Damage Assessment and life extension analysis to one loop of nuclear power station high-temperature pipe.
Claims (2)
1. one kind for one loop of nuclear power station high-temperature pipe heat fatigue prototype monitoring device, comprise background server, External data storage server, data acquisition module and data sampling sensor, it is characterized in that: described background server is electrically connected one or several External data storage server by data transmission cable with bus form or distribution form, each External data storage server is electrically connected one or more data acquisition module by data transmission cable with bus form or distribution form, each data acquisition module is electrically connected multiple data sampling sensor by transmission cable with bus form or distribution form, transmission cable carries out reinforcing and shielding protection, described data sampling sensor adopts the thermocouple temperature sensor being arranged on pipe temperature measuring point surface and the flow sensor be arranged on pipeline flow measuring point, installs 2-8 thermocouple temperature sensor on each pipe temperature measuring point surface.
2. a kind of monitoring method for one loop of nuclear power station high-temperature pipe heat fatigue prototype monitoring device according to claim 1, is characterized in that: described monitoring method implementation step comprises:
(1) type selecting of monitoring sensor
The model of temperature sensor is selected to meet measurement range, measuring accuracy and long-time stability requirement, and select armoured thermocouple temperature sensor, pipeline fluid flow utilizes the existing flowmeter of primary Ioops high-temperature pipe;
(2) installation site of monitoring sensor on one loop of nuclear power station high-temperature pipe
According to the numerical simulation result of one loop of nuclear power station pipeline thermal fluid flow operating mode, specify emphasis monitoring position, avoid weld seam and heavy wall labyrinth region according to the actual conditions at scene simultaneously, find temperature compensation point in its vicinity, thus determine the final installation site of temperature sensor on pipeline;
(3) monitoring sensor is at the cloth point mode of high-temperature pipe outer wall
Adopt pipeline outer wall to lay the measuring method of temperature sensor, according to carrying out practically situation, simultaneously in conjunction with the numerical simulation result of fluid, determine the heat flow behavior type causing pipeline thermal fatigue, determine that monitoring sensor is layouted number;
(4) data acquisition of monitoring sensor and transmission form
The temperature sensor being arranged in pipeline outer wall, in real time by the data acquisition module near transmitting measured values to measuring point, is distributed in on-the-spot one or more data acquisition modules and sends data to External data storage server by bus form or distribution form;
(5) Integrated Solution of monitoring sensor
Multiple temperature sensor and flowmeter are integrated in a set of monitoring system simultaneously, and the temperature data be kept in External data storage server shows in real time, carry out synchronously integrated with background server;
(6) thermal stress of Monitoring Data calculates and stores
Pipeline outer wall temperature measurement result is utilized to combine the traffic behavior information of monitoring pipeline, calculate thermal stress and the behavior of thermal stress time variations of pipeline key point fast, adopt background server to store for outside wall temperature, pipeline flow and the inner wall temperature calculated, inner surface heat stress, the thermal stress data of storage carry out Fatigue Damage Assessment and life extension analysis for primary Ioops.
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| CN106680001A (en) * | 2016-10-25 | 2017-05-17 | 核动力运行研究所 | Pipeline three-way area on-line fatigue life monitoring device and method |
| CN108268675A (en) * | 2016-12-30 | 2018-07-10 | 北京金风科创风电设备有限公司 | Fatigue damage determination method and fatigue damage determination device |
| CN109979622A (en) * | 2017-12-27 | 2019-07-05 | 核动力运行研究所 | Nuclear power plant's voltage-stablizer fatigue life monitors assessment system and method on-line |
| WO2020006915A1 (en) * | 2018-07-03 | 2020-01-09 | 中广核研究院有限公司 | Nuclear reactor loop temperature measurement heat pipe and temperature measurement device |
| CN110828011A (en) * | 2019-11-04 | 2020-02-21 | 广东核电合营有限公司 | Nuclear power plant pipeline thermal fatigue monitoring system |
| CN111141400A (en) * | 2019-12-04 | 2020-05-12 | 深圳中广核工程设计有限公司 | Method for measuring temperature of pipe wall of thermal fatigue sensitive area of bent pipe of nuclear power station |
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| CN108268675A (en) * | 2016-12-30 | 2018-07-10 | 北京金风科创风电设备有限公司 | Fatigue damage determination method and fatigue damage determination device |
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| CN109979622A (en) * | 2017-12-27 | 2019-07-05 | 核动力运行研究所 | Nuclear power plant's voltage-stablizer fatigue life monitors assessment system and method on-line |
| CN109979622B (en) * | 2017-12-27 | 2021-02-09 | 核动力运行研究所 | Nuclear power plant voltage stabilizer fatigue life online monitoring and evaluating system and method |
| WO2020006915A1 (en) * | 2018-07-03 | 2020-01-09 | 中广核研究院有限公司 | Nuclear reactor loop temperature measurement heat pipe and temperature measurement device |
| GB2581407A (en) * | 2018-07-03 | 2020-08-19 | China Nuclear Power Technology Res Inst Co Ltd | Nuclear reactor loop temperature measurement heat pipe and temperature measurement device |
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| CN112649460B (en) * | 2019-10-10 | 2023-10-20 | 国核电站运行服务技术有限公司 | Thermal stratification test method for surge tube of voltage stabilizer |
| CN110828011B (en) * | 2019-11-04 | 2021-11-23 | 广东核电合营有限公司 | Nuclear power plant pipeline thermal fatigue monitoring system |
| CN110828011A (en) * | 2019-11-04 | 2020-02-21 | 广东核电合营有限公司 | Nuclear power plant pipeline thermal fatigue monitoring system |
| CN111141400A (en) * | 2019-12-04 | 2020-05-12 | 深圳中广核工程设计有限公司 | Method for measuring temperature of pipe wall of thermal fatigue sensitive area of bent pipe of nuclear power station |
| CN111141400B (en) * | 2019-12-04 | 2021-08-24 | 深圳中广核工程设计有限公司 | Method for measuring temperature of pipe wall of thermal fatigue sensitive area of bent pipe of nuclear power station |
| CN112699514A (en) * | 2020-12-31 | 2021-04-23 | 河北工业大学 | Rapid calculation method for transient thermal stress of thermal stratification pipeline |
| DE102021128132B3 (en) | 2021-10-28 | 2022-06-30 | Framatome Gmbh | Monitoring system for monitoring mechanical fatigue of a metal pipe of a power plant, power plant, use and associated method |
| CN114777368A (en) * | 2022-04-08 | 2022-07-22 | 青岛海尔空调器有限总公司 | Method and device for monitoring risk of circulation system pipeline and circulation system |
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