CN112530615B - Variable forcing method and system suitable for nuclear power station equipment - Google Patents
Variable forcing method and system suitable for nuclear power station equipment Download PDFInfo
- Publication number
- CN112530615B CN112530615B CN201910879224.7A CN201910879224A CN112530615B CN 112530615 B CN112530615 B CN 112530615B CN 201910879224 A CN201910879224 A CN 201910879224A CN 112530615 B CN112530615 B CN 112530615B
- Authority
- CN
- China
- Prior art keywords
- forced
- data
- controller
- recording area
- communication module
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 238000000034 method Methods 0.000 title claims abstract description 59
- 230000006854 communication Effects 0.000 claims abstract description 65
- 238000004891 communication Methods 0.000 claims abstract description 53
- 230000008569 process Effects 0.000 claims abstract description 29
- 238000004364 calculation method Methods 0.000 claims description 7
- 238000009434 installation Methods 0.000 claims 1
- 230000006870 function Effects 0.000 description 10
- 238000010586 diagram Methods 0.000 description 5
- 238000012544 monitoring process Methods 0.000 description 3
- 239000000243 solution Substances 0.000 description 3
- 230000006978 adaptation Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 230000000750 progressive effect Effects 0.000 description 1
- 230000000007 visual effect Effects 0.000 description 1
Abstract
The invention discloses a variable forcing method and a variable forcing system suitable for nuclear power station equipment, wherein the method comprises the following steps: the upper computer receives a forced parameter list input by a user and starts a communication module; the communication module sends a forced command to the controller through function call; the controller analyzes the forced command, acquires the forced parameter list, writes the data in the forced parameter list into a forced data recording area, and replaces the original data of the forced data recording area; the controller is arranged in nuclear power station equipment; the communication module reads the data in the current forced data recording area and returns the read data to the upper computer; and the upper computer receives the data returned by the communication module, judges whether the returned data is consistent with the data in the forced parameter list, and if so, determines that the forced process is successful. The method reduces labor cost.
Description
Technical Field
The invention relates to the technical field of nuclear power stations, in particular to a variable forcing method and a variable forcing system suitable for nuclear power station equipment.
Background
At present, in the traditional nuclear power station equipment debugging process, workers are required to take a debugging instrument to go to the site, and on-line debugging work is carried out by adopting a hard wiring mode and a current signal injection mode. The traditional debugging mode has complex procedures, more equipment and low efficiency, and the labor cost is high. Current signal injection is prone to interference with other in-line devices. And the current detection accuracy error is high.
Therefore, how to reduce the labor cost is a problem to be solved.
Disclosure of Invention
The invention aims to provide a variable forcing method and a variable forcing system suitable for nuclear power station equipment, so as to reduce labor cost.
In order to solve the technical problem, the invention provides a variable forcing method suitable for nuclear power station equipment, which comprises the following steps:
the upper computer receives a forced parameter list input by a user and starts a communication module;
the communication module sends a forced command to the controller through function call;
The controller analyzes the forced command, acquires the forced parameter list, writes the data in the forced parameter list into a forced data recording area, and replaces the original data of the forced data recording area; the controller is arranged in nuclear power station equipment;
The communication module reads the data in the current forced data recording area and returns the read data to the upper computer;
And the upper computer receives the data returned by the communication module, judges whether the returned data is consistent with the data in the forced parameter list, and if so, determines that the forced process is successful.
Preferably, the communication module stores a communication program for communication between the upper computer and the controller.
Preferably, the controller includes a calculation area, a designation area, a forced area, and a forced data recording area.
Preferably, the controller is provided with an embedded program; the communication module reads the data in the current forced data recording area, and returns the read data to the upper computer, and the communication module further comprises:
The controller uses the embedded program to periodically and circularly judge the data in the forced data recording area and rewrites the data in the forced data recording area.
The invention also provides a variable forcing system suitable for the nuclear power station equipment, which is characterized by comprising the following steps:
The upper computer is used for receiving the forced parameter list input by the user and starting the communication module; and receiving the data returned by the communication module, judging whether the returned data is consistent with the data in the forced parameter list, and if so, determining that the forced process is successful;
The communication module is used for sending a forced command to the controller through function call; reading the data in the current forced data recording area, and returning the read data to the upper computer;
The controller is used for analyzing the forced command, acquiring the forced parameter list, writing the data in the forced parameter list into a forced data recording area, and replacing the original data of the forced data recording area; the controller is disposed in a nuclear power plant.
Preferably, the communication module stores a communication program for communication between the upper computer and the controller.
Preferably, the controller includes a calculation area, a designation area, a forced area, and a forced data recording area.
Preferably, the controller is provided with an embedded program; the controller is also used for judging the data in the forced data recording area by using the embedded program cycle and rewriting the data in the forced data recording area.
The invention provides a variable forcing method and a variable forcing system suitable for nuclear power station equipment, wherein an upper computer receives a forcing parameter list input by a user and starts a communication module; the communication module sends a forced command to the controller through function call; the controller analyzes the forced command, acquires the forced parameter list, writes the data in the forced parameter list into a forced data recording area, and replaces the original data of the forced data recording area; the controller is arranged in nuclear power station equipment; the communication module reads the data in the current forced data recording area and returns the read data to the upper computer; and the upper computer receives the data returned by the communication module, judges whether the returned data is consistent with the data in the forced parameter list, and if so, determines that the forced process is successful. Therefore, the method completes the variable forcing process through the upper computer, the communication module and the controller, finally can judge whether the forcing process is successful, the whole variable forcing process is actually the process of equipment debugging, the forced success represents that the equipment of the nuclear power plant normally works, namely the equipment debugging of the nuclear power plant is completed, the equipment debugging is automatically realized, the equipment is not required to be manually debugged on site, the labor cost is reduced, and the working efficiency is improved.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings that are required to be used in the embodiments or the description of the prior art will be briefly described below, and it is obvious that the drawings in the following description are only embodiments of the present invention, and that other drawings can be obtained according to the provided drawings without inventive effort for a person skilled in the art.
FIG. 1 is a flow chart of a variable forcing method applicable to nuclear power plant equipment provided by the invention;
FIG. 2 is a schematic diagram of a communication process between a human-machine interface and a controller in the method;
FIG. 3 is a schematic diagram of a variable forcing system suitable for a nuclear power plant device according to the present invention;
fig. 4 is a schematic structural diagram of a variable forcing system suitable for a nuclear power plant device according to the present invention.
Detailed Description
The invention provides a variable forcing method and a variable forcing system suitable for nuclear power station equipment, so as to reduce labor cost.
In order that those skilled in the art will better understand the present invention, a technical solution in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in which it is apparent that the described embodiments are only some embodiments of the present invention, not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
Referring to fig. 1, fig. 1 is a flowchart of a variable forcing method for a nuclear power plant device according to the present invention, the method includes the following steps:
s11: the upper computer receives a forced parameter list input by a user and starts a communication module;
s12: the communication module sends a forced command to the controller through function call;
S13: the controller analyzes the forced command, acquires a forced parameter list, writes data in the forced parameter list into a forced data recording area, and replaces original data of the forced data recording area;
Wherein the controller is arranged in the nuclear power plant equipment;
S14: the communication module reads the data in the current forced data recording area and returns the read data to the upper computer;
s15: and the upper computer receives the data returned by the communication module, judges whether the returned data is consistent with the data in the forced parameter list, and if so, determines that the forced process is successful.
Therefore, the method completes the variable forcing process through the upper computer, the communication module and the controller, finally can judge whether the forcing process is successful, the whole variable forcing process is actually the process of equipment debugging, the forced success represents that the equipment of the nuclear power plant normally works, namely the equipment debugging of the nuclear power plant is completed, the equipment debugging is automatically realized, the equipment is not required to be manually debugged on site, the labor cost is reduced, and the working efficiency is improved.
The variable forcing process is to change the data of the controller in the nuclear power plant equipment, return the changed data to the upper computer after the change is successful, and when the returned data displayed on the upper computer is inconsistent with the data in the originally displayed controller, the data in the controller is indicated to be changed successfully, so that the nuclear power plant equipment is normally operated, if the nuclear power plant equipment is abnormally operated, the data is not changed successfully, the data is the original data, the returned data is consistent with the original data in the upper computer, and the nuclear power plant equipment is abnormally operated, namely the debugging process is completed. The whole variable forcing process is actually a process of equipment debugging, forcing success represents that the nuclear power plant equipment works normally, namely, the nuclear power plant equipment debugging is completed, and the labor cost is saved.
Based on the above method, further, a communication program is stored in the communication module, and is used for communication between the upper computer and the controller.
Specifically, the controller includes a calculation area, a designation area, a forced area, and a forced data recording area.
Further, the controller is installed with an embedded program. The communication module reads the data in the current forced data recording area, and after the read data is returned to the upper computer, the controller circularly judges the data in the forced data recording area by utilizing the embedded program period and rewrites the data in the forced data recording area.
The invention has the advantages that the upper computer, the communication module and the controller are arranged in the nuclear power station equipment, the upper computer is adopted to mutually cooperate with the controller hardware equipment, the labor cost is greatly simplified, the whole forced process completes the online debugging, the operation is simple, and the signal data precision is very high. Wherein, the controller adopts MPU (Main Processing Unit, main processing board card). The four differentiated memory areas in the MPU of the controller are respectively: a calculation area, a marking area, a forced area and a forced data recording area. The mandatory data recording area stores 5104 bytes of data.
The invention uses the operation software tool in the upper computer to input the forced parameter information list, and inputs the forced signal to the lower computer controller MPU through the communication program in the communication module. The mandatory parameter list comprises an offset, a length and a mandatory value, wherein the offset is an address stored in a memory, the length is a data value, and the mandatory value is a parameter value of nuclear power station equipment to be intervened.
The upper computer inputs a forced command to a forced recording area in the lower computer MPU through a communication mode of a self-maintenance protocol, and then the forced logic function is executed by embedded software which is loaded in advance according to the command.
Referring to fig. 2, fig. 2 is a schematic diagram of a communication process between a human-computer interface and a controller in the method, and based on the method, the implementation process is as follows:
1. a man-machine interface providing a forced parameter list; the man-machine interface is a user input interface in the upper computer, and the forced parameter list contains offset, length and forced values;
2. The communication program sends a forced command to the controller MPU through protocol function call; the specific function call contains a parameter list; the communication program is stored in the communication module;
3. the controller analyzes the command, and writes the content of the parameter list to the corresponding position of the forced data recording area;
4. the embedded program in the controller periodically and circularly judges the data of the forced data recording area and rewrites the data of the forced area;
5. the communication program reads back the forced indication area data and returns to the human-computer interface;
6. And the man-machine interface displays whether the forcing is successful or not according to the forcing state. And (5) forcing success to indicate normal operation of the nuclear power equipment, and forcing failure to indicate abnormal operation of the nuclear power equipment, namely completing debugging of the nuclear power equipment.
The forced parameter list is manually input, and the upper computer software is adopted for on-line forcing, so that the quantity of debugging equipment is small, the process is simplified, a human-computer interface is friendly, the operation is simple, the debugging efficiency is high, the digital signal precision is high, the error is small, and no interference is caused to other on-line operation equipment.
REDACE refers to Real-TIME AND DETERMINISTIC Application Coding Environment, real-time and deterministic application software programming environments. Referring to fig. 3, fig. 3 is a flowchart of a user man-machine interface operation process. The operation flow of the human-computer interface is as follows:
Firstly, compiling a software editing algorithm, downloading the algorithm to a controller, and adjusting the controller to an operation mode;
Secondly, starting REDACE software, loading the same compiled and downloaded algorithm project, selecting a project operator node, and starting an online monitoring function;
And after the monitoring is started, opening an algorithm graphic page under the operator node, and entering a visual monitoring function. At this time, the variables in the algorithm page may be selected to perform the forced or cancel operation of the variables, or the batch forced or batch cancel forced operation may be selected.
Fig. 4 is a schematic structural diagram of a variable forcing system suitable for a nuclear power plant device, where the system is used to implement the method, and the system includes:
The upper computer 101 is configured to receive a forced parameter list input by a user, and start a communication module; and receiving the data returned by the communication module, judging whether the returned data is consistent with the data in the forced parameter list, and if so, determining that the forced process is successful;
a communication module 102 for sending a forcing command to the controller through a function call; reading the data in the current forced data recording area, and returning the read data to the upper computer;
a controller 103 for analyzing the forcing command, obtaining a forcing parameter list, and writing the data in the forcing parameter list into the forcing data recording area to replace the original data of the forcing data recording area;
wherein the controller is provided in the nuclear power plant equipment.
Therefore, the system completes the variable forcing process through the upper computer, the communication module and the controller, finally can judge whether the forcing process is successful, the whole variable forcing process is actually the process of equipment debugging, the forced success represents that the equipment of the nuclear power plant works normally, namely, the equipment debugging of the nuclear power plant is completed, the equipment debugging is automatically realized, the equipment is not required to be manually debugged on site, the labor cost is reduced, and the working efficiency is improved.
Based on the above system, specifically, the communication module stores a communication program for communication between the upper computer and the controller.
Specifically, the controller includes a calculation area, a designation area, a forced area, and a forced data recording area.
Further, the controller is provided with an embedded program; the controller is also used for judging the data in the forced data recording area by using the embedded program cycle and rewriting the data in the forced data recording area.
In this specification, each embodiment is described in a progressive manner, and each embodiment is mainly described in a different point from other embodiments, so that the same or similar parts between the embodiments are referred to each other. For the system disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and the relevant points refer to the description of the method section.
Those of skill would further appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware, computer software, or combinations of both, and that the various illustrative elements and steps are described above generally in terms of functionality in order to clearly illustrate the interchangeability of hardware and software. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the solution. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present invention.
The steps of a method or algorithm described in connection with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. The software modules may be disposed in Random Access Memory (RAM), memory, read Only Memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.
The variable forcing method and the variable forcing system suitable for the nuclear power station equipment are described in detail. The principles and embodiments of the present invention have been described herein with reference to specific examples, the description of which is intended only to facilitate an understanding of the method of the present invention and its core ideas. It should be noted that it will be apparent to those skilled in the art that various modifications and adaptations of the invention can be made without departing from the principles of the invention and these modifications and adaptations are intended to be within the scope of the invention as defined in the following claims.
Claims (7)
1. A variable forcing method suitable for nuclear power plant equipment, comprising:
the upper computer receives a forced parameter list input by a user and starts a communication module;
the communication module sends a forced command to the controller through function call;
The controller analyzes the forced command, acquires the forced parameter list, writes the data in the forced parameter list into a forced data recording area, and replaces the original data of the forced data recording area; the controller is arranged in nuclear power station equipment;
The communication module reads the data in the current forced data recording area and returns the read data to the upper computer;
The upper computer receives the data returned by the communication module, judges whether the returned data is consistent with the data in the forced parameter list, if so, determines that the forced process is successful, and the nuclear power plant equipment works normally, so that the debugging of the nuclear power plant equipment is completed;
The controller comprises a calculation area, a marking area, a forced area and a forced data recording area.
2. The method of claim 1, wherein the communication module stores a communication program for communication between the host computer and the controller.
3. The method of any one of claims 1 to 2, wherein the controller is installed with an embedded program; the communication module reads the data in the current forced data recording area, and returns the read data to the upper computer, and the communication module further comprises:
The controller uses the embedded program to periodically and circularly judge the data in the forced data recording area and rewrites the data in the forced data recording area.
4. A variable forcing system adapted for use in a nuclear power plant installation, for implementing the method of any one of claims 1 to 3, comprising:
The upper computer is used for receiving the forced parameter list input by the user and starting the communication module; and receiving the data returned by the communication module, judging whether the returned data is consistent with the data in the forced parameter list, and if so, determining that the forced process is successful;
The communication module is used for sending a forced command to the controller through function call; reading the data in the current forced data recording area, and returning the read data to the upper computer;
The controller is used for analyzing the forced command, acquiring the forced parameter list, writing the data in the forced parameter list into a forced data recording area, and replacing the original data of the forced data recording area; the controller is disposed in a nuclear power plant.
5. The system of claim 4, wherein the communication module stores a communication program for communication between the host computer and the controller.
6. The system of claim 5, wherein the controller comprises a calculation area, a designation area, a enforcement area, and a enforcement data recording area.
7. The system according to any one of claims 4 to 6, wherein the controller is installed with an embedded program; the controller is also used for judging the data in the forced data recording area by using the embedded program cycle and rewriting the data in the forced data recording area.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910879224.7A CN112530615B (en) | 2019-09-18 | Variable forcing method and system suitable for nuclear power station equipment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910879224.7A CN112530615B (en) | 2019-09-18 | Variable forcing method and system suitable for nuclear power station equipment |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN112530615A CN112530615A (en) | 2021-03-19 |
| CN112530615B true CN112530615B (en) | 2024-05-14 |
Family
ID=
Citations (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1890718A (en) * | 2003-12-05 | 2007-01-03 | 三星电子株式会社 | Recording apparatus, recording method, and information recording medium |
| KR20120020859A (en) * | 2010-08-31 | 2012-03-08 | 주식회사 포스코아이씨티 | Apparatus for controlling nuclear power generation and method for updating data of that apparatus |
| CN102412003A (en) * | 2011-09-20 | 2012-04-11 | 中广核工程有限公司 | Nuclear power station DCS debugging system and method thereof |
| CN104155972A (en) * | 2014-08-21 | 2014-11-19 | 广西柳工机械股份有限公司 | Mechanical engineering electronic controller parameter debugging method |
| CN104268074A (en) * | 2014-09-05 | 2015-01-07 | 北京广利核系统工程有限公司 | Application software online debugging method based on DCS |
| CN104793075A (en) * | 2015-03-30 | 2015-07-22 | 北京广利核系统工程有限公司 | Periodic test system for protection systems for pressurized water reactor nuclear power plants |
| 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 |
| CN105353671A (en) * | 2015-10-19 | 2016-02-24 | 北京广利核系统工程有限公司 | Variable forcing and releasing device and method for instrument control system of nuclear power station |
| RU2593389C1 (en) * | 2015-01-16 | 2016-08-10 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" - Госкорпорация "Росатом" | Automated system for controlling neutron physical parameters of research nuclear plant |
| WO2018137145A1 (en) * | 2017-01-24 | 2018-08-02 | 北京广利核系统工程有限公司 | Data synchronization method and apparatus |
| CN108922641A (en) * | 2018-05-31 | 2018-11-30 | 北京广利核系统工程有限公司 | The routine test device and method of high temperature reactor of nuclear power plant protection system |
| KR101917038B1 (en) * | 2017-08-31 | 2019-01-24 | 한국수력원자력 주식회사 | Device of reference document integration management and procedure display for making nuclear power plant commissioning procedures |
| CN109448880A (en) * | 2018-09-25 | 2019-03-08 | 北京广利核系统工程有限公司 | Method and system is filled under nuclear safe level hot backup redundancy control station unperturbed |
Patent Citations (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1890718A (en) * | 2003-12-05 | 2007-01-03 | 三星电子株式会社 | Recording apparatus, recording method, and information recording medium |
| KR20120020859A (en) * | 2010-08-31 | 2012-03-08 | 주식회사 포스코아이씨티 | Apparatus for controlling nuclear power generation and method for updating data of that apparatus |
| CN102412003A (en) * | 2011-09-20 | 2012-04-11 | 中广核工程有限公司 | Nuclear power station DCS debugging system and method thereof |
| CN104155972A (en) * | 2014-08-21 | 2014-11-19 | 广西柳工机械股份有限公司 | Mechanical engineering electronic controller parameter debugging method |
| CN104268074A (en) * | 2014-09-05 | 2015-01-07 | 北京广利核系统工程有限公司 | Application software online debugging method based on DCS |
| RU2593389C1 (en) * | 2015-01-16 | 2016-08-10 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" - Госкорпорация "Росатом" | Automated system for controlling neutron physical parameters of research nuclear plant |
| CN104793075A (en) * | 2015-03-30 | 2015-07-22 | 北京广利核系统工程有限公司 | Periodic test system for protection systems for pressurized water reactor nuclear power plants |
| 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 |
| CN105353671A (en) * | 2015-10-19 | 2016-02-24 | 北京广利核系统工程有限公司 | Variable forcing and releasing device and method for instrument control system of nuclear power station |
| WO2018137145A1 (en) * | 2017-01-24 | 2018-08-02 | 北京广利核系统工程有限公司 | Data synchronization method and apparatus |
| KR101917038B1 (en) * | 2017-08-31 | 2019-01-24 | 한국수력원자력 주식회사 | Device of reference document integration management and procedure display for making nuclear power plant commissioning procedures |
| CN108922641A (en) * | 2018-05-31 | 2018-11-30 | 北京广利核系统工程有限公司 | The routine test device and method of high temperature reactor of nuclear power plant protection system |
| CN109448880A (en) * | 2018-09-25 | 2019-03-08 | 北京广利核系统工程有限公司 | Method and system is filled under nuclear safe level hot backup redundancy control station unperturbed |
Non-Patent Citations (2)
| Title |
|---|
| MCGS嵌入式设备与UPS的通信驱动程序开发;张晓明;袁佑新;闪鑫;张学文;;自动化与仪表;20150315(第03期);第69-76页 * |
| 核电站分布式系统虚拟过程控制平台设计研究;高汉军;曲鸣;李青;景应刚;;计算机仿真;20170215(第02期);第144-149页 * |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN108829593B (en) | Code coverage rate calculation and analysis method, device, equipment and storage medium | |
| EP3101547A1 (en) | Control system, method, program and information processing device | |
| CN110888354A (en) | Method and device for realizing automatic identification of access equipment, computer equipment and medium | |
| CN111673251A (en) | Virtual debugging method and device for welding parameters and welding quality of robot spot welding | |
| CN110597714A (en) | Kafka message testing method and device, computer equipment and storage medium | |
| CN111639002A (en) | Method and system for testing sleep power consumption, computer equipment and storage medium | |
| CN110739025B (en) | Power failure test method, device and system for storage equipment | |
| CN111796578A (en) | Vehicle controller testing method, device and system and storage medium | |
| CN102231127A (en) | System and method for detecting BIOS (Basic Input Output System) wrong information display | |
| CN111142469B (en) | Debugging method and debugging system for PLC configuration program | |
| CN112530615B (en) | Variable forcing method and system suitable for nuclear power station equipment | |
| CN112445670B (en) | eMMC test method and device | |
| CN113126993A (en) | Automatic testing method and system applied to vehicle detection software | |
| CN113608089B (en) | SOA test method, system and device for switching power supply MOS tube and readable storage medium | |
| CN112530615A (en) | Variable forcing method and system suitable for nuclear power station equipment | |
| US11340590B2 (en) | Data collection system, data collection method, and information storage medium | |
| CN114879647A (en) | ECU fault code test system, electronic controller and car | |
| CN110297455B (en) | Programmable logic controller and self-checking and recovery method thereof | |
| CN103365237A (en) | Method and device for monitoring and recording component and variable in PLC (Programmable Logic Controller) system | |
| CN108932171B (en) | Embedded software interaction method | |
| US20020026301A1 (en) | Automatic evaluation method, automatic evaluation system, and storage medium storing automatic evaluation program | |
| JP2001154711A (en) | Method and device for debugging process stepping type program | |
| JP5492573B2 (en) | Device / PLC simulator device, method, and program having trace function | |
| CN117331847B (en) | Automatic test method and system supporting graphic interface | |
| CN110688299A (en) | Automatic test platform for application software of nuclear power plant |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant |