CN110580566A - Instrument control system black box test system - Google Patents
Instrument control system black box test system Download PDFInfo
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- CN110580566A CN110580566A CN201910548796.7A CN201910548796A CN110580566A CN 110580566 A CN110580566 A CN 110580566A CN 201910548796 A CN201910548796 A CN 201910548796A CN 110580566 A CN110580566 A CN 110580566A
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- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q10/00—Administration; Management
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- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q50/00—Systems or methods specially adapted for specific business sectors, e.g. utilities or tourism
- G06Q50/06—Electricity, gas or water supply
Abstract
The invention aims to disclose an instrument control system black box test system, which comprises a nuclear power station data model, an instrument control system control and protection logic model and a score board; the method comprises the steps of generating a simulation test vector by using power plant key operation parameters of a nuclear power plant data model under different power plant design basis accidents and over-design basis accidents, generating corresponding output as a correct test result by using an instrument control system control and protection logic model according to the test vector, inputting the same test vector into a design system to be tested, comparing the test vector with the correct test result, collecting and comparing the output results of a reference model and the design to be tested by using a score board, and automatically generating a test report.
Description
Technical Field
The invention relates to a black box test system, in particular to an instrument control system black box test system suitable for the function test and the system integration test of an instrument control system of a digital nuclear power station.
Background
The nuclear power plant instrument control system mainly provides information display and control functions, is used for monitoring the parameters of the nuclear power plant key parameter sensors, and automatically or manually triggers the control and protection functions so as to maintain the safe, stable and reliable operation of the whole power plant.
The digital instrument control system is a distributed control system which is mainly constructed by an industrial computer, a bus technology and an industrial Ethernet. Compared with the traditional instrument control system based on the simulation technology, the intelligent instrument control system has the functions of intelligent alarming, diagnosis, expert system, big data analysis and the like, and accords with human factors engineering in human-computer interface design.
Digital instrument control systems are typically built using microprocessor-based instrument control platforms. However, since microprocessor-based instrumentation systems introduce operating systems and the complexity of the microprocessor itself, there is a risk in the design verification and validation (V & V) integrity and accuracy for security critical systems. Currently, an instrumentation and control system, which is based on Field Programmable Gate Array (FPGA) technology, is gradually introduced into the safety and non-safety systems of nuclear power plants.
Either microprocessor-based or FPGA-based instrumentation platforms, require thorough V & V (verification and validation). Currently, system testing is entirely manual. Although an automated testing tool has been developed, the test cases still need to be written manually, and the accuracy of the test cases cannot be completely guaranteed for a huge nuclear power plant control system and a multi-sequence redundant reactor protection system.
therefore, there is a particular need for an instrumentation black box test system that addresses the above-identified problems.
Disclosure of Invention
The invention aims to provide a black box testing system of an instrument control system, which aims at overcoming the defects of the prior art, realizes automatic testing of the digital instrument control system and solves the problems of inaccuracy and incompleteness of V & V of the digital instrument control system.
The technical problem solved by the invention can be realized by adopting the following technical scheme:
The utility model provides an appearance control system black box test system, its characterized in that, it includes nuclear power station data model, appearance control system control and protection logic model and scoreboard, nuclear power station data model in proper order with appearance control system control and protection logic model with scoreboard intercommunication connects, nuclear power station data model's output through a simulation server with appearance control system control and protection logic model's input intercommunication connects, appearance control system control and protection logic model's output with scoreboard's input intercommunication connects, scoreboard's output test report.
In an embodiment of the invention, the test vectors input by the input end of the nuclear power plant data model are plant key operation parameters of the nuclear power plant data model under different plant design basis accidents and over-design basis accidents.
In one embodiment of the invention, the nuclear power plant data model includes, but is not limited to, a thermal hydraulic model, a neutron dynamics model, and a severe accident analysis model.
In one embodiment of the invention, the simulation server is communicatively coupled to the instrumentation control and protection logic model via sensor signals, and the instrumentation control and protection logic model is communicatively coupled to the simulation server via simulation driver signals.
in an embodiment of the present invention, the simulation server is communicatively connected to the design system to be tested through a sensor signal, and an output terminal of the design system to be tested is communicatively connected to an input terminal of the scoreboard.
In an embodiment of the present invention, the output end of the design system to be tested is further connected to a human-computer interface device.
Compared with the prior art, the instrument control system black box test system generates a simulation test vector by adopting the power plant key operation parameters of the nuclear power plant data model under different power plant design basis accidents and over-design basis accidents, generates corresponding output as a correct test result according to the test vector and the instrument control system control and protection logic model, inputs the same test vector into the design system to be tested, compares the same test vector with the correct test result, acquires and compares the reference model with the output result of the design to be tested by the scoreboard, and automatically generates a test report.
The features of the present invention will be apparent from the accompanying drawings and from the detailed description of the preferred embodiments which follows.
Drawings
FIG. 1 is a schematic diagram of the black box test system of the instrumentation and control system of the present invention;
FIG. 2 is a schematic illustration of a reactor trip signal of the present invention;
Fig. 3 is a schematic diagram of the driving signal of the special safety facility of the present invention.
Detailed Description
In order to make the technical means, the creation characteristics, the achievement purposes and the effects of the invention easy to understand, the invention is further explained below by combining the specific drawings.
Examples
As shown in fig. 1 to 3, the instrument control system black box test system of the present invention includes a nuclear power plant data model, an instrument control system control and protection logic model 8 and a score board 10, wherein the nuclear power plant data model is sequentially connected with the instrument control system control and protection logic model 8 and the score board 10 in a communication manner, an output end of the nuclear power plant data model is connected with an input end of the instrument control system control and protection logic model 8 in a communication manner through a simulation server 4, an output end of the instrument control system control and protection logic model 8 is connected with an input end of the score board 10 in a communication manner, and an output end of the score board 10 outputs a test report.
In this embodiment, the test vector input at the input end of the nuclear power plant data model is a power plant key operation parameter of the nuclear power plant data model in different power plant design basis accidents and over-design basis accidents, and the instrumentation control system control and protection logic model 8 is used as a reference model system.
In this embodiment, the nuclear power plant data model includes, but is not limited to, a thermal hydraulic model 1, a neutron dynamics model 2, and a severe accident analysis model 3, and may be used to simulate models of the nuclear power plant core, the primary loop, and the secondary loop under different operating conditions.
In the present exemplary embodiment, the simulation server 4 is communicatively connected to the instrumentation control and protection logic model 8 via the sensor signals 5, and the instrumentation control and protection logic model 8 is communicatively connected to the simulation server 4 via the simulation driver signals 9.
In this embodiment, the simulation server 4 is communicatively connected to the design under test system 7 via the sensor signals 5, and the output of the design under test system 7 is communicatively connected to the input of the scoreboard 10.
In this embodiment, a human-machine interface device 6 is further connected to the output end of the design-under-test system 7.
According to the instrument control system black box testing system, the data model of the nuclear power station is adopted to generate a simulation testing vector, and the simulation testing vector is compared with the verified reference model system 8, and the scoring board 10 automatically generates the testing report 11, so that the testing accuracy and the testing reality are improved, errors caused by compiling the testing vector are avoided, and the efficiency and the repeatability of the whole testing are improved.
The following further describes that a nuclear power plant benchmark accident-LOCA is simulated by a power plant model to generate a test case, and the test case is respectively sent to a design system 7 to be tested (for example, an FPGA-based instrument control system) and a reference model system 8 (for example, an SCADE-based system function model) to perform automatic black box test.
The LOCA accident is a coolant loss accident, which means that a primary circuit has a large break, and the coolant supplement capacity is insufficient to compensate the loss from the break, so that the reactor core gradually loses cooling, and the fuel rod package bridge is heated and even burnt. The LOCA accident firstly influences the change of the pressure value of the voltage stabilizer, the simulation of the real accident by the corresponding pressure value of the voltage stabilizer in the power plant model is reduced, and when the value is lower than a setting value, the shutdown of the reactor and the driving of related special safety measures are triggered. The specific implementation steps are as follows:
(1) firstly, the nuclear power plant data model is adjusted to a normal working condition, at the moment, the pressure value of the voltage stabilizer is in a normal range, and the reactor shutdown and the special safety facilities are in an un-triggered state, as shown in fig. 2 and 3.
(2) A simulated LOCA accident is initiated in the nuclear power plant data model and the simulated sensor signal representing the pressure value of the potentiostat begins to change. The data is sent to the design system 7 to be tested and the reference model system 8 in real time, and is compared and recorded through the scoring board 10. The simulation driving signal 9 in the reference model system 8 is also fed back to the nuclear power plant data model in real time for simulation calculation.
(3) And when the pressure value of the voltage stabilizer is smaller than the setting value, observing whether the output result of the design system to be tested 7 is consistent with the reference model system 8.
(4) As shown in fig. 2 and 3, when the respective sensor signals are less than the setting value, the design system under test 7 triggers reactor shutdown and special safety facility driving as the reference model system 8.
By the mode, the consistency of the design system to be tested 7 and the reference model system 8 in real power plant accidents can be effectively verified, and therefore the purpose of verifying the correctness is achieved.
The foregoing shows and describes the general principles and broad features of the present invention and advantages thereof. It will be understood by those skilled in the art that the present invention is not limited to the embodiments described above, which are merely illustrative of the principles of the present invention, but that various changes and modifications may be made without departing from the spirit and scope of the invention, which is defined by the appended claims and their equivalents.
Claims (6)
1. The utility model provides an appearance control system black box test system, its characterized in that, it includes nuclear power station data model, appearance control system control and protection logic model and scoreboard, nuclear power station data model in proper order with appearance control system control and protection logic model with scoreboard intercommunication connects, nuclear power station data model's output through a simulation server with appearance control system control and protection logic model's input intercommunication connects, appearance control system control and protection logic model's output with scoreboard's input intercommunication connects, scoreboard's output test report.
2. The instrumentation control system black box test system of claim 1, wherein said test vectors input at said input of said nuclear power plant data model are plant critical operating parameters of said nuclear power plant data model in different plant design basis incidents and over design basis incidents.
3. The instrumentation control system black box test system of claim 1, wherein said nuclear power plant data models comprise, but are not limited to, a thermal hydraulic model, a neutron dynamics model, and a severe accident analysis model.
4. The instrumentation system black box test system of claim 1, wherein said simulation server is communicatively coupled to said instrumentation system control and protection logic model via sensor signals, and said instrumentation system control and protection logic model is communicatively coupled to said simulation server via simulation driver signals.
5. The system for black box testing of an instrumentation control system according to claim 1, wherein said simulation server is communicatively coupled to a design under test system via sensor signals, an output of said design under test system being communicatively coupled to an input of said scoreboard.
6. the system according to claim 1, wherein a human-machine interface device is further coupled to the output of the design-under-test system.
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| CN201910548796.7A CN110580566A (en) | 2019-06-24 | 2019-06-24 | Instrument control system black box test system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111382078A (en) * | 2020-03-13 | 2020-07-07 | 龙婷 | Fault diagnosis simulation method and device, electronic equipment and storage medium |
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| CN105159275A (en) * | 2015-08-16 | 2015-12-16 | 中国科学院合肥物质科学研究院 | Closed-loop test platform used for instrument and control system of nuclear reactor and driven by real-time simulation data |
| CN107894761A (en) * | 2017-11-07 | 2018-04-10 | 广东核电合营有限公司 | The method of testing and platform of Nuclear Power Plant Simulation I＆C system digital improvement |
| CN109741841A (en) * | 2019-01-03 | 2019-05-10 | 中核控制系统工程有限公司 | A kind of control systems of nuclear power plant Department of Automation Guided Missiles Service Test Set and method |
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Patent Citations (4)
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| CN104898633A (en) * | 2015-06-16 | 2015-09-09 | 中广核工程有限公司 | Nuclear power plant non-security-level DCS configuration testing method and system |
| CN105159275A (en) * | 2015-08-16 | 2015-12-16 | 中国科学院合肥物质科学研究院 | Closed-loop test platform used for instrument and control system of nuclear reactor and driven by real-time simulation data |
| CN107894761A (en) * | 2017-11-07 | 2018-04-10 | 广东核电合营有限公司 | The method of testing and platform of Nuclear Power Plant Simulation I＆C system digital improvement |
| CN109741841A (en) * | 2019-01-03 | 2019-05-10 | 中核控制系统工程有限公司 | A kind of control systems of nuclear power plant Department of Automation Guided Missiles Service Test Set and method |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111382078A (en) * | 2020-03-13 | 2020-07-07 | 龙婷 | Fault diagnosis simulation method and device, electronic equipment and storage medium |
| CN111382078B (en) * | 2020-03-13 | 2023-04-28 | 龙婷 | Fault diagnosis simulation method and device, electronic equipment and storage medium |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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Application publication date: 20191217 |