CN105632573A - Acquiring and processing system for reactor control rod drive wire test data - Google Patents
Acquiring and processing system for reactor control rod drive wire test data Download PDFInfo
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- CN105632573A CN105632573A CN201610012297.2A CN201610012297A CN105632573A CN 105632573 A CN105632573 A CN 105632573A CN 201610012297 A CN201610012297 A CN 201610012297A CN 105632573 A CN105632573 A CN 105632573A
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- control rod
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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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- 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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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides an acquiring and processing system for reactor control rod drive wire test data. The system comprises a pressure measuring device, a temperature measuring device, a visible window, a high speed camera, a data acquiring device and a data processing device. The acquiring and processing system for the reactor control rod drive wire test data is high in reliability, has the characteristics of comprehensive range of measurement, high measuring precision, high working stability, fast real time response, and high analysis and processing capacity, and provides a high quality measuring means for science research and process test of a reactor control rod drive wire and related systems.
Description
Technical field
The invention belongs to nuclear power plant reactor security performance checking experimental technique, be specifically related to a kind of reactor control rod and drive thread test Data collection and precessing system.
Background technology
Presurized water reactor Control rod drive line is made up of CRDM, pressure vessels top cover, in-pile component guide cylinder, fuel assembly and the related control rod of drive rod, is constitute the assembly controlling the passage that assembly moves up and down in reactor. Dropping of control rod is the only resource of quick control reactor, and the effect when emergency shut-down is particularly important. During emergent rod drop, presurized water reactor control rod overcomes frictional force between coolant buoyancy, fluid resistance and structure under gravity, inserts reactor core from extreme higher position, to ensure safe shutdown within the time of regulation. The rod drop time of control rod is one of important parameter of npp safety analysis, is also the important indicator driving Motion trend design examination.
Pile Control rod drive line design for abundant confirmatory reaction and can meet the requirement performing security function, needing in mock-up reactor the longitudinally complicated coolant flow regime of stream, laterally stream, the equipment such as simulation top cover, in-pile component, fuel assembly deforms and installs and wrong medium complicated unfavoured state is driven line Rod drop test.
When being driven line Rod drop test, it is necessary to the kinestate of control rod and drive rod is detected. Counter the estimating of induced voltage produced when traditional method is by reading the drive rod cutting magnetic field of CRDM stick location probe record calculates drive rod transient operation speed, additionally vibration signal during record CRDM release drive rod is as scram starting point, thus calculating driving line rod drop time. Using the method to be easily subject to interference effect of signals, there is people because of error in the process reading data, the speed time curve error obtained is bigger.
Additionally, when carrying out Rod drop test, in assay device, the flow regime parameter such as the temperature of fluid circuit, pressure is also the factor affecting experimental accuracy, whether there is the difficult point that the problem such as bubble, air cavity is also detection in test loop. Therefore, how external drive thread test data collecting system function, provide its accuracy and reliability to be a difficult problem.
Summary of the invention
The present invention is directed to the deficiencies in the prior art, it is proposed to a kind of reactor control rod drives thread test Data collection and precessing system.
Reactor control rod drives thread test Data collection and precessing system to include:
Pressure gauge, is arranged in test hydraulic circuits and Test section, and for detecting, scram is initial and the pressure parameter of process medium fluid;
Temperature measuring equipment, is arranged in test hydraulic circuits and Test section, and for detecting, scram is initial and the temperature parameter of process medium fluid;
Visualization window, is arranged in Test section;
High-speed camera instrument, for the drive rod surface of motion in Test section being carried out high ?frequency photograph detection by visualization window, by image capturing system recording image file, processes the transient motion parameter obtaining control rod by dedicated program;
Data acquisition unit, is connected with the sensor in Test section loop by signal network, for the signal data in pilot system is acquired;
Data processing equipment, is made up of multiple stage computer, processes for the signal data that described data collecting card is collected.
Preferably, data acquisition unit includes data collecting card and circuit controls DCS rack, described data collecting card and circuit controls DCS rack for the temperature in pilot system, pressure, flow signal data are acquired.
Preferably, described data acquisition unit includes CRDM control rack; Described CRDM is controlled rack and is connected with the CRDM in pilot system by cable, for control to CRDM, and the electric current in collecting work coil and the voltage model in excellent bit line circle.
Preferably, described computer includes at least one in circuit system control computer, data acquisition computer and video camera control computer.
Preferably, recording equipment is also included; The data of described recording device records include the motion image of drive-rod part in the temperature in CRDM coil current signal before and after scram, the scram voltage signal of stick location probe extraction, test loop, pressure, flow value and scram process.
Compared with prior art, the method have the advantages that
1, reactor control rod provided by the invention drives thread test Data collection and precessing system, reliability is high, have that measurement scope is comprehensive, certainty of measurement is high, job stability is strong, real-time response is fast, analyze and the feature such as disposal ability is strong, drive for reactor control rod scientific research and the process testing of line and related system to provide high-quality measurement means.
2, reactor control rod provided by the invention drives thread test Data collection and precessing system, adopt multiple measurement means, the motor process of the process fluid flow in synchronous detecting driving thread test device, the electric current in CRDM coil and voltage change process and control rod and drive rod; Realize multi-faceted Data acquisition and issuance to process, comprehensive synchronization can obtain reactor and drive line state parameter in emergent rod drop and driving mechanism running, have the advantages that accuracy of measurement height, real time response speed are fast.
Accompanying drawing explanation
Fig. 1 is the schematic diagram of the reactor control rod driving thread test Data collection and precessing system meeting the preferred embodiment of the present invention.
Detailed description of the invention
Understandable for enabling the above-mentioned purpose of the present invention, feature and advantage to become apparent from, below for third generation passive nuclear reactor AP1000 Control rod drive line Rod drop test and the present invention is further detailed explanation in conjunction with the drawings and specific embodiments.
Inside presurized water reactor, it is arranged side by side with tens of groups of Control rod drive lines according to reactor core reactivity control strategy, line rod drop time under above-mentioned each unfavorable conditions is driven for obtaining reactor, generally taking one group of full-scale reactor control rod drives line equipment to be subjects, realizes the complicated simulation driving the unfavorable working condition of line by designing double loop, the dislocation system such as mechanism, deformation mechanism and device.
Reactor control rod drives thread test Data collection and precessing system by utilizing the technical equipments such as high-speed photography, again development process method, building Data collection and precessing system on the basis of conventional art, to CRDM running current and motion state parameters, stick location probe voltage signal, drive rod and subsidiary C&P systems location parameter, and in assay device, the fluid flow state parameter of key position carries out accurately measurement, scientific disposal and complete documentation.
As it is shown in figure 1, reactor control rod drives thread test Data collection and precessing system to include:
Pressure gauge, is arranged in test hydraulic circuits and Test section, and for detecting, scram is initial and the pressure parameter of process medium fluid;
Temperature measuring equipment, is arranged in test hydraulic circuits and Test section, and for detecting, scram is initial and the temperature parameter of process medium fluid;
Visualization window, is arranged in Test section;
High-speed camera instrument, for the drive rod surface of motion in Test section being carried out high ?frequency photograph detection by visualization window, by image capturing system recording image file, processes the transient motion parameter obtaining control rod by dedicated program;
Data acquisition unit, is connected with the sensor in Test section loop by signal network, for the signal data in pilot system is acquired;
Data processing equipment, is made up of multiple stage computer, processes for the signal data that described data collecting card is collected.
Preferably, data acquisition unit includes data collecting card and circuit controls DCS rack, described data collecting card and circuit controls DCS rack for the temperature in pilot system, pressure, flow signal data are acquired.
Preferably, described data acquisition unit includes CRDM control rack; Described CRDM is controlled rack and is connected with the CRDM in pilot system by cable, for control to CRDM, and the electric current in collecting work coil and the voltage model in excellent bit line circle.
Preferably, described computer includes at least one in circuit system control computer, data acquisition computer and video camera control computer.
Preferably, recording equipment is also included; The data of described recording device records include the motion image of drive-rod part in the temperature in CRDM coil current signal before and after scram, the scram voltage signal of stick location probe extraction, test loop, pressure, flow value and scram process.
System proposed by the invention can drive in line Rod drop test at third generation passive nuclear plant AP1000 reactor control rod and carry out engineer applied and inspection, result shows that native system normal operation is stable, the induced voltage produced by stick location probe and two approach of image file of high-speed camera instrument record obtain this type reactor control rod motor coordination test data under various unfavorable operating modes, acquire the circulation status parameter of hydraulic circuits and Test section key position simultaneously, a large amount of analytical data are provided for follow-up scientific research, demonstrate this heap-type Control rod drive line fully and perform the ability of security performance.
Compared with prior art, the method have the advantages that
1, reactor control rod provided by the invention drives thread test Data collection and precessing system, reliability is high, have that measurement scope is comprehensive, certainty of measurement is high, job stability is strong, real-time response is fast, analyze and the feature such as disposal ability is strong, drive for reactor control rod scientific research and the process testing of line and related system to provide high-quality measurement means.
2, reactor control rod provided by the invention drives thread test Data collection and precessing system, adopt multiple measurement means, the motor process of the process fluid flow in synchronous detecting driving thread test device, the electric current in CRDM coil and voltage change process and control rod and drive rod; Realize multi-faceted Data acquisition and issuance to process, comprehensive synchronization can obtain reactor and drive line state parameter in emergent rod drop and driving mechanism running, have the advantages that accuracy of measurement height, real time response speed are fast.
In this specification, each embodiment adopts the mode gone forward one by one to describe, and what each embodiment stressed is the difference with other embodiments, between each embodiment identical similar portion mutually referring to. For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so what describe is fairly simple, relevant part illustrates referring to method part.
Those skilled in the art specifically can should be used for using different methods to realize described function to each, but this realization is it is not considered that beyond the scope of this invention.
Obviously, invention can be carried out various change and modification without deviating from the spirit and scope of the present invention by those skilled in the art. So, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technologies thereof, then the present invention is also intended to include these change and modification.
Claims (5)
1. a reactor control rod drives thread test Data collection and precessing system, it is characterised in that including:
Pressure gauge, is arranged in test hydraulic circuits and Test section, and for detecting, scram is initial and the pressure parameter of process medium fluid;
Temperature measuring equipment, is arranged in test hydraulic circuits and Test section, and for detecting, scram is initial and the temperature parameter of process medium fluid;
Visualization window, is arranged in Test section;
High-speed camera instrument, for the drive rod surface of motion in Test section being carried out high ?frequency photograph detection by visualization window, by image capturing system recording image file, processes the transient motion parameter obtaining control rod by dedicated program;
Data acquisition unit, is connected with the sensor in Test section loop by signal network, for the signal data in pilot system is acquired;
Data processing equipment, is made up of multiple stage computer, processes for the signal data that described data collecting card is collected.
2. reactor control rod as claimed in claim 1 drives thread test Data collection and precessing system, it is characterized in that, described data acquisition unit includes data collecting card and circuit controls DCS rack, described data collecting card and circuit controls DCS rack for the temperature in pilot system, pressure, flow signal data are acquired.
3. reactor control rod as claimed in claim 1 drives thread test Data collection and precessing system, it is characterised in that described data acquisition unit includes CRDM and controls rack; Described CRDM is controlled rack and is connected with the CRDM in pilot system by cable, for control to CRDM, and the electric current in collecting work coil and the voltage model in excellent bit line circle.
4. reactor control rod as claimed in claim 1 drives thread test Data collection and precessing system, it is characterised in that described computer includes circuit system and controls at least one in computer, data acquisition computer and video camera control computer.
5. reactor control rod as claimed in claim 1 drives thread test Data collection and precessing system, it is characterised in that also include recording equipment; The data of described recording device records include the motion image of drive-rod part in the temperature in CRDM coil current signal before and after scram, the scram voltage signal of stick location probe extraction, test loop, pressure, flow value and scram process.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610012297.2A CN105632573A (en) | 2016-01-08 | 2016-01-08 | Acquiring and processing system for reactor control rod drive wire test data |
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| CN201610012297.2A CN105632573A (en) | 2016-01-08 | 2016-01-08 | Acquiring and processing system for reactor control rod drive wire test data |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106531252A (en) * | 2016-10-12 | 2017-03-22 | 中广核核电运营有限公司 | Control bar position measuring and testing method |
| CN108735310A (en) * | 2018-06-04 | 2018-11-02 | 江苏核电有限公司 | A kind of analog training device of control rod drive mechanism measurement of electric parameter |
| CN111696692A (en) * | 2020-07-16 | 2020-09-22 | 上海核工程研究设计院有限公司 | Control rod driving mechanism state monitoring and health management method and system |
| CN112002448A (en) * | 2020-08-28 | 2020-11-27 | 清华大学 | Method and device for measuring thermal state performance of control rod drive wire |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4713210A (en) * | 1985-11-18 | 1987-12-15 | General Electric Company | Control rod driveline and grapple |
| CN103400613A (en) * | 2013-07-30 | 2013-11-20 | 中广核工程有限公司 | Cross flow testing apparatus and method for cold test on drive wires of nuclear power plants |
| CN103500591A (en) * | 2013-09-29 | 2014-01-08 | 中广核工程有限公司 | Cold test mis-centering device for reactor control rod drive wire of nuclear power plant |
| CN103500524A (en) * | 2013-09-29 | 2014-01-08 | 中广核工程有限公司 | Cold test device and method for control rod drive line of nuclear power plant |
| CN103714736A (en) * | 2013-12-31 | 2014-04-09 | 中国核动力研究设计院 | Pressurized water reactor driving line cold test device |
| CN105004512A (en) * | 2014-04-18 | 2015-10-28 | 中科华核电技术研究院有限公司 | Testing bench of control rod driving mechanism |
-
2016
- 2016-01-08 CN CN201610012297.2A patent/CN105632573A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4713210A (en) * | 1985-11-18 | 1987-12-15 | General Electric Company | Control rod driveline and grapple |
| CN103400613A (en) * | 2013-07-30 | 2013-11-20 | 中广核工程有限公司 | Cross flow testing apparatus and method for cold test on drive wires of nuclear power plants |
| CN103500591A (en) * | 2013-09-29 | 2014-01-08 | 中广核工程有限公司 | Cold test mis-centering device for reactor control rod drive wire of nuclear power plant |
| CN103500524A (en) * | 2013-09-29 | 2014-01-08 | 中广核工程有限公司 | Cold test device and method for control rod drive line of nuclear power plant |
| CN103714736A (en) * | 2013-12-31 | 2014-04-09 | 中国核动力研究设计院 | Pressurized water reactor driving line cold test device |
| CN105004512A (en) * | 2014-04-18 | 2015-10-28 | 中科华核电技术研究院有限公司 | Testing bench of control rod driving mechanism |
Non-Patent Citations (3)
| Title |
|---|
| 王继英 等: "秦山核电二期工程控制棒驱动线热态综合试验", 《核动力工程》 * |
| 胡俊 等: "秦山核电二期工程控制棒驱动线冷态对中试验研究", 《核动力工程》 * |
| 顾汉洋 等: "AP1000控制棒驱动线落棒试验研究", 《核动力工程》 * |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106531252A (en) * | 2016-10-12 | 2017-03-22 | 中广核核电运营有限公司 | Control bar position measuring and testing method |
| CN108735310A (en) * | 2018-06-04 | 2018-11-02 | 江苏核电有限公司 | A kind of analog training device of control rod drive mechanism measurement of electric parameter |
| CN108735310B (en) * | 2018-06-04 | 2024-06-11 | 江苏核电有限公司 | Simulation training device for measuring electrical parameters of control rod driving mechanism |
| CN111696692A (en) * | 2020-07-16 | 2020-09-22 | 上海核工程研究设计院有限公司 | Control rod driving mechanism state monitoring and health management method and system |
| CN111696692B (en) * | 2020-07-16 | 2024-01-30 | 上海核工程研究设计院股份有限公司 | Control rod driving mechanism state monitoring and health management method and system |
| CN112002448A (en) * | 2020-08-28 | 2020-11-27 | 清华大学 | Method and device for measuring thermal state performance of control rod drive wire |
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Application publication date: 20160601 |