CN104635669B - A kind of I＆C system verification method - Google Patents
A kind of I＆C system verification method Download PDFInfo
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- CN104635669B CN104635669B CN201410755636.7A CN201410755636A CN104635669B CN 104635669 B CN104635669 B CN 104635669B CN 201410755636 A CN201410755636 A CN 201410755636A CN 104635669 B CN104635669 B CN 104635669B
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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
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P90/00—Enabling technologies with a potential contribution to greenhouse gas [GHG] emissions mitigation
- Y02P90/02—Total factory control, e.g. smart factories, flexible manufacturing systems [FMS] or integrated manufacturing systems [IMS]
Abstract
A kind of I＆C system verification method, is related to technical field of nuclear power, and the solution is to improve verification efficiency and verification reliability.This method first establishes a platform control station, an instrument control model station and a signal and stands；Network model is established in signal is stood, and establishes a physical equipment mathematical model for each physical equipment in nuclear power station；In instrument control model station a control unit module is established for each control unit of I＆C system；The operating condition of various physical equipments in each physical equipment mathematical model simulation nuclear power station in recycling signal to stand, and interaction relation between each physical equipment in the network model simulation nuclear power station in being stood using signal, it treats each control unit activated in verification I＆C system and is verified.System provided by the invention is suitable for verification nuclear power I＆C system.
Description
Technical field
The present invention relates to nuclear power technologies, more particularly to a kind of technology of I＆C system verification method.
Background technology
Nuclear power I＆C system（Including DCS system）It is extremely complex, it, should be in its exploitation in order to improve nuclear power reliability of operation
Each stage verified, with determine this stage design and manufacture correctness.In I＆C system development process, need to be related to
The stage of verification includes：Instrument control design phase, instrument control software configuration stage, instrument control integration phase, instrument control factory inspection and acceptance stage.Instrument
Control design phase and configuration stage, control strategy show in software function that there is no actual vector operations for it.It integrates and tests
In the receipts stage, after function distribution, instrument control control strategy is located in multiple instrument control cabinets, and each cabinet has variety classes sum number
The I/O equipment and terminal fastener of amount.Control unit includes existing for above-mentioned each stage I＆C system：Control function block test, control
Page test processed, control system test, controller, I/O tests etc..
Currently, the basic principle of instrument control test verification is that each test point signal occurs, and provides process equipment and technological parameter
Feedback of status passes through I＆C system movement locus and as a result, record and analytical equipment and control strategy function accuracy.Such is surveyed
Pilot generally comprises I/O points, upper site, lower site and fieldbus point etc..
Existing I＆C system verification method is all by manually using manual test, utilizing signal generator, oscillograph, process
The various equipment manual tests such as control instrument need outer adduction acquisition various types of signal when carrying out test item, recycle instrument and
The artificial plus signal in instrument control cabinet terminal block of the method for shorting stub.Each point is required for carrying out wiring, step of taking out stitches, test effect
Rate is low, manpower consumption is big, and due to the limitation of instrument, some test items can not carry out, and such as the priority of each test point links
The reliability of relation test, verification result is relatively low.
Invention content
Defect present in for the above-mentioned prior art, technical problem to be solved by the invention is to provide a kind of verification effects
Rate is high, and the high I＆C system verification method of reliability of verification result.
In order to solve the above-mentioned technical problem, a kind of I＆C system verification method provided by the present invention, which is characterized in that tool
Steps are as follows for body：
1）A platform control station, an instrument control model station and a signal is established to stand；
Wherein, platform control station, instrument control model station, I＆C system to be verified pass through communication network mutual connection, signal hair
Raw station is interconnected with instrument control model station by communication network, and the analog signals output port of I＆C system to be verified is turned by modulus
Exchange device is connected to signal and stands, and the feedback signal output mouth that signal is stood is connected to instrument to be verified by digital-to-analogue conversion equipment
The analog signals input port of control system；
2）In signal is stood, a network for simulating interaction relation between each physical equipment in nuclear power station is established
Model, and establish a physical equipment mathematical modulo for simulating equipment operation for each physical equipment in nuclear power station
Type；
In instrument control model station, one is established for simulating the control list for each control unit of I＆C system to be verified
The control unit module of the control function of member；
3）By platform control station, the control unit for preparing to implement verification in I＆C system to be verified is chosen；
4）By platform control station, control unit selected in I＆C system to be verified is activated, and other controls are single
Member excision so that the control unit being activated starts operation so that removed control unit is out of service；
By platform control station, control unit module corresponding with selected control unit in instrument control model station is cut
It removes, and by other control unit module activations so that the control unit module being activated starts operation so that removed control
Unit module is out of service；
5）The operation of various physical equipments in each physical equipment mathematical model simulation nuclear power station in being stood using signal
Operating mode, and interaction relation between each physical equipment in the network model simulation nuclear power station in being stood using signal, to be verified
Each control unit activated in I＆C system is verified；
It is each in each control unit module simulation I＆C system to be verified being activated in instrument control model station in verification process
A corresponding control unit, and the corresponding control signal of station output occurs to signal, and processing signal occurs station and feeds back to these controls
The signal of unit processed；
In verification process, each control unit for being activated in I＆C system to be verified be activated in instrument control model station it is each
Control unit module exchange pertinent information, and station output control signal accordingly occurs to signal, and station occurs for processing signal instead
The signal for these control units of feeding.
I＆C system verification method provided by the invention, the operating condition of station simulation nuclear power plant occurs using signal, and leads to
It crosses instrument control model station and simulates the control unit being removed in I＆C system to be verified, stood by instrument control model station, signal
Coordinate from the control unit that is verified in trend I＆C system and export corresponding checking signal, and receives its feedback signal automatically,
Have the characteristics that verification efficiency is high and verification result reliability is high.
Description of the drawings
Fig. 1 is the schematic diagram of the I＆C system verification method of the embodiment of the present invention.
Specific implementation mode
The embodiment of the present invention is described in further detail below in conjunction with description of the drawings, but the present embodiment is not used to limit
The system present invention, every similar structure using the present invention and its similar variation, should all be included in protection scope of the present invention.
As shown in Figure 1, a kind of I＆C system verification method that the embodiment of the present invention is provided, which is characterized in that specific step
It is rapid as follows：
1）It establishes 1, instrument control model station 2 of a platform control station and station 3 occurs for a signal；
Wherein, platform control station 1, instrument control model station 2, I＆C system to be verified 4 pass through communication network mutual connection, signal
Station 3 occurs to interconnect by communication network with instrument control model station 2, the analog signals output port of I＆C system 4 to be verified passes through
Analog-to-digital conversion equipment 5 is connected to signal and station 3 occurs, and the feedback signal output mouth that station 3 occurs for signal is connect by digital-to-analogue conversion equipment 5
To the analog signals input port of I＆C system 4 to be verified；
2）In station 3 occurs for signal, a net for simulating interaction relation between each physical equipment in nuclear power station is established
Network model, and establish a physical equipment mathematical modulo for simulating equipment operation for each physical equipment in nuclear power station
Type；Nuclear power station physical equipment mathematical model during signal is stood includes pump model, valve model, becomes appliance model, pressure biography
Sensor model, impulse model；Signal stand in network model be thermal-hydraulic, power process simulation set, it will be each
The equipment state of kind physical equipment model acts in actual physics parameter（Such as valve working cause changes in flow rate so as to cause
The dynamic change of full nuclear power station network）, and each physical equipment model is got up by network matrix calculations incorporated；
In instrument control model station 2, one is established for simulating the control for each control unit of I＆C system to be verified
The control unit module of the control function of unit；
3）By platform control station 1, the control unit for preparing to implement verification in I＆C system 4 to be verified is chosen（For example it selects
Take control unit 41,42）, the quantity of selected control unit can be one, can also be multiple；
4）By platform control station 1, by control unit selected in I＆C system 4 to be verified（Such as control unit 41,
42）Activation, and other control units are cut off so that the control unit being activated starts operation so that removed control list
Member is out of service；
By platform control station 1, by control unit module corresponding with selected control unit in instrument control model station（Than
Such as with control unit 41,42 corresponding control unit modules 21,22）Excision, and by other control unit module activations so that
The control unit module being activated starts operation so that removed control unit module is out of service；
5）The operation of various physical equipments in each physical equipment mathematical model simulation nuclear power station in station 3 occurs using signal
Operating mode, and using interaction relation between each physical equipment in the network model simulation nuclear power station in signal generation station 3, to be verified
Each control unit activated in I＆C system（Such as control unit 41,42）It is verified；
In verification process, in each control unit module simulation I＆C system to be verified being activated in instrument control model station 2
Each corresponding control unit, and the corresponding control signal of 3 output of station occurs to signal, and processing signal occurs station 3 and feeds back to this
The signal of a little control units；
In verification process, each control unit for being activated in I＆C system 4 to be verified（Such as control unit 41,42）With instrument
Each control unit module exchange pertinent information being activated in control model station 2, and the corresponding control letter of 3 output of station occurs to signal
Number, and handle signal and the signal that station 3 feeds back to these control units occurs.
For example, control unit 41 is valve automatic control unit, the network model matrix in signal generation station 3, which calculates, works as
By signal each physical equipment number in station 3 occurs for the parameter values such as preceding nuclear power station " pressure ", " temperature ", " flow velocity " " liquid level "
Modeling valve automatic control process is learned, and simulation output corresponding signal is by being used as the survey of control unit 41 after digital-to-analogue conversion
Example on probation inputs I＆C system 4 to be verified, and control unit 1 answers control instruction according to PID logic strategy the output phase, and passes through modulus
The valve model in signal generation station 3 is acted on after conversion, so that the aperture parameter of valve model is changed, and signal is caused to be sent out
Network model dynamic matrix in raw station 3 calculates, and forms the parameters such as new nuclear power station " pressure ", " temperature ", " flow velocity " " liquid level "
State, the closed loop to provide a new round are verified.Meanwhile 3 record logical process of station and control I/O variations occur for signal, with test
The test result automation comparison of preceding preservation, intelligence export test report, evaluate the valve Automatic Control Strategy of control unit 41
Integrality and logical action correctness.
In turn, by platform control station 1, Chernobyl Plant, three mile island nuclear station, Fukushima nuclear power station etc. can be set
Scene is automatically imported as batch testing use-case, movement locus of the access control unit 41,42 under various malfunctions, letter
Number occur station 3 record and analysis result, output report.
Claims (1)
1. a kind of I＆C system verification method, which is characterized in that be as follows：
1）A platform control station, an instrument control model station and a signal is established to stand；
Wherein, by communication network mutual connection, signal is stood for platform control station, instrument control model station, I＆C system to be verified
It is interconnected by communication network with instrument control model station, the analog signals output port of I＆C system to be verified is set by analog-to-digital conversion
It stands for signal is connected to, the feedback signal output mouth that signal is stood is connected to instrument control system to be verified by digital-to-analogue conversion equipment
The analog signals input port of system；
2）In signal is stood, a network mould for simulating interaction relation between each physical equipment in nuclear power station is established
Type, and establish a physical equipment mathematical model for simulating equipment operation for each physical equipment in nuclear power station；
In instrument control model station, one is established for simulating the control unit for each control unit of I＆C system to be verified
The control unit module of control function；
3）By platform control station, the control unit for preparing to implement verification in I＆C system to be verified is chosen；
4）By platform control station, control unit selected in I＆C system to be verified is activated, and other control units are cut
It removes so that the control unit being activated starts operation so that removed control unit is out of service；
By platform control station, control unit module corresponding with selected control unit in instrument control model station is cut off, and
By other control unit module activations so that the control unit module being activated starts operation so that removed control unit
Module is out of service；
5）The operating condition of various physical equipments in each physical equipment mathematical model simulation nuclear power station in being stood using signal,
And interaction relation between each physical equipment in the network model simulation nuclear power station in being stood using signal, treat verification instrument control system
Each control unit activated in system is verified；
It is each right in each control unit module simulation I＆C system to be verified being activated in instrument control model station in verification process
Control unit is answered, and station output control signal accordingly occurs to signal, and processing signal occurs station and feeds back to these control lists
The signal of member；
Each control unit activated in I＆C system to be verified in verification process and each control being activated in instrument control model station
Unit module exchange pertinent information, and the corresponding control signal of station output occurs to signal, and processing signal occurs station and feeds back to
The signal of these control units.
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| CN201410755636.7A CN104635669B (en) | 2014-12-11 | 2014-12-11 | A kind of I＆C system verification method |
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| CN104635669B true CN104635669B (en) | 2018-10-02 |
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Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN105929710A (en) * | 2016-04-18 | 2016-09-07 | 中国神华能源股份有限公司 | RB overall working condition simulation test device and method |
| CN106773785B (en) * | 2016-12-26 | 2020-02-18 | 中核控制系统工程有限公司 | Method for realizing nuclear safety level intelligent simulation verification platform based on FPGA technology |
| CN107577223B (en) * | 2017-09-26 | 2023-11-14 | 中广核研究院有限公司 | Digital improved verification system of nuclear power plant analog control system |
| CN109542059B (en) * | 2018-11-19 | 2022-04-01 | 国核自仪系统工程有限公司 | Historical data compression device and method |
| CN109949956B (en) * | 2019-03-25 | 2021-07-23 | 北京广利核系统工程有限公司 | High-load working condition simulation method and system for nuclear power station control system |
| CN112164481B (en) * | 2020-08-17 | 2023-09-29 | 北京广利核系统工程有限公司 | Intelligent verification method and system for nuclear power safety control display equipment database |
| CN112099453B (en) * | 2020-09-23 | 2022-02-11 | 中国核动力研究设计院 | Function verification system of nuclear power plant safety level instrument control system |
| CN112415985B (en) * | 2020-11-30 | 2022-01-18 | 中广核工程有限公司 | Nuclear power station gate and master control communication verification device and method and related equipment |
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Address after: 200241 No. 428 East Jiangchuan Road, Shanghai, Minhang District Patentee after: STATE NUCLEAR POWER AUTOMATION SYSTEM ENGINEERING Co.,Ltd. Address before: 200241. A2036, building B, building 555, Dongchuan Road, Minhang District, Shanghai Patentee before: STATE NUCLEAR POWER AUTOMATION SYSTEM ENGINEERING Co.,Ltd. |