CN112530615A - 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 PDF

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Publication number
CN112530615A
CN112530615A CN201910879224.7A CN201910879224A CN112530615A CN 112530615 A CN112530615 A CN 112530615A CN 201910879224 A CN201910879224 A CN 201910879224A CN 112530615 A CN112530615 A CN 112530615A
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China
Prior art keywords
data
mandatory
controller
recording area
communication module
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Pending
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CN201910879224.7A
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Chinese (zh)
Inventor
石桂连
刘志新
任保华
马腾飞
张保乾
杨晨
闫鑫
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China Techenergy Co Ltd
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China Techenergy Co Ltd
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Priority to CN201910879224.7A priority Critical patent/CN112530615A/en
Publication of CN112530615A publication Critical patent/CN112530615A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/007Expert systems
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/008Man-machine interface, e.g. control room layout
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/08Regulation of any parameters in the plant
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Abstract

The invention discloses a variable forcing method and system suitable for nuclear power station equipment, wherein the method comprises the following steps: the upper computer receives a mandatory parameter list input by a user and starts a communication module; the communication module sends a forcing command to the controller through function call; the controller analyzes the mandatory command, acquires the mandatory parameter list, writes data in the mandatory parameter list into a mandatory data recording area, and replaces original data in the mandatory data recording area; the controller is arranged in the nuclear power station equipment; the communication module reads the data in the current mandatory 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 forcing parameter list or not, and if so, determines that the forcing process is successful. The method reduces labor cost.

Description

Variable forcing method and system suitable for nuclear power station equipment
Technical Field
The invention relates to the technical field of nuclear power stations, in particular to a variable forcing method and system suitable for nuclear power station equipment.
Background
At present, in the debugging process of the traditional nuclear power station equipment, a worker needs to bring a debugging instrument to the site, and online debugging work is carried out by adopting a hard wiring mode and a current signal injection means. The traditional debugging mode has complex procedures, more equipment, low efficiency and higher labor cost. Current signal injection tends to interfere with other on-line devices. And the current detection precision error is high.
Therefore, how to reduce the labor cost is an urgent problem to be solved.
Disclosure of Invention
The invention aims to provide a variable forcing method and 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 plant equipment, which comprises the following steps:
the upper computer receives a mandatory parameter list input by a user and starts a communication module;
the communication module sends a forcing command to the controller through function call;
the controller analyzes the mandatory command, acquires the mandatory parameter list, writes data in the mandatory parameter list into a mandatory data recording area, and replaces original data in the mandatory data recording area; the controller is arranged in the nuclear power station equipment;
the communication module reads the data in the current mandatory 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 forcing parameter list or not, and if so, determines that the forcing 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 marking area, a mandatory area, and a mandatory data recording area.
Preferably, the controller is provided with an embedded program; the communication module reads the data in the current mandatory data recording area, and after the data read is returned to the upper computer, the communication module further comprises:
the controller judges the data in the mandatory data recording area periodically and circularly by using the embedded program and rewrites the data in the mandatory data recording area.
The invention also provides a variable forcing system suitable for nuclear power plant equipment, which is characterized in that the method is realized by the following steps:
the upper computer is used for receiving a mandatory parameter list input by a user and starting the communication module; receiving data returned by the communication module, judging whether the returned data is consistent with the data in the forcing parameter list, and if so, determining that the forcing process is successful;
the communication module is used for sending a forcing command to the controller through function call; reading the data in the current mandatory data recording area, and returning the read data to the upper computer;
the controller is used for analyzing the mandatory command, acquiring the mandatory parameter list, writing data in the mandatory parameter list into a mandatory data recording area, and replacing original data in the mandatory data recording area; the controller is disposed in the nuclear power plant equipment.
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 marking area, a mandatory area, and a mandatory data recording area.
Preferably, the controller is provided with an embedded program; the controller is also used for periodically and circularly judging the data in the mandatory data recording area by using the embedded program and rewriting the data in the mandatory data recording area.
The invention provides a variable forcing method and system suitable for nuclear power station equipment.A host computer receives a forcing parameter list input by a user and starts a communication module; the communication module sends a forcing command to the controller through function call; the controller analyzes the mandatory command, acquires the mandatory parameter list, writes data in the mandatory parameter list into a mandatory data recording area, and replaces original data in the mandatory data recording area; the controller is arranged in the nuclear power station equipment; the communication module reads the data in the current mandatory 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 forcing parameter list or not, and if so, determines that the forcing 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 equipment debugging process, the forced success represents that the nuclear power station equipment normally works, namely the nuclear power station equipment debugging is completed, so that the equipment debugging is automatically realized, manual debugging on site is not needed, 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 used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the provided drawings without creative efforts.
FIG. 1 is a flow chart of a variable forcing method for nuclear power plant equipment according to the present invention;
FIG. 2 is a schematic diagram illustrating a communication process between the human-machine interface and the controller in the method;
FIG. 3 is a schematic diagram of a variable forcing system for nuclear power plant equipment according to the present invention;
fig. 4 is a schematic structural diagram of a variable forcing system suitable for nuclear power plant equipment provided by the invention.
Detailed Description
The core of the invention is to provide a variable forcing method and system suitable for nuclear power station equipment so as to reduce labor cost.
In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Referring to fig. 1, fig. 1 is a flowchart of a variable forcing method for nuclear power plant equipment according to the present invention, the method including the following steps:
s11: the upper computer receives a mandatory parameter list input by a user and starts a communication module;
s12: the communication module sends a forcing command to the controller through function call;
s13: the controller analyzes the forcing command, acquires a forcing parameter list, writes data in the forcing parameter list into a forcing data recording area, and replaces original data in the forcing data recording area;
wherein the controller is arranged in the nuclear power plant equipment;
s14: the communication module reads the data in the current mandatory 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 forcing parameter list or not, and if so, determines that the forcing 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 equipment debugging process, the forced success represents that the nuclear power station equipment normally works, namely the nuclear power station equipment debugging is completed, so that the equipment debugging is automatically realized, manual debugging on site is not needed, the labor cost is reduced, and the working efficiency is improved.
The variable forcing process is to change data of a controller in the nuclear power plant equipment, the changed data is returned to the upper computer after the change is successful, 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 successfully changed, the nuclear power plant equipment is indicated to be normally working, if the nuclear power plant equipment does not normally work, the data is unsuccessfully changed and is also the original data, the returned data is consistent with the original data in the upper computer, the nuclear power plant equipment does not normally work, and the debugging process is completed. The whole variable forcing process is actually the process of equipment debugging, the nuclear power station equipment is forced to work normally successfully, the nuclear power station equipment debugging is completed, and the labor cost is saved.
Based on the method, further, the communication module stores a communication program for communication between the upper computer and the controller.
Specifically, the controller includes a calculation area, a marking area, a mandatory area, and a mandatory data recording area.
Further, the controller is installed with an embedded program. The communication module reads the data in the current mandatory data recording area, and after the read data is returned to the upper computer, the controller periodically and circularly judges the data in the mandatory data recording area by utilizing the embedded program and rewrites the data in the mandatory data recording area.
The invention is provided with an upper computer, a communication module and a controller, wherein the controller is arranged in the nuclear power station equipment, and a computer system in the upper computer and controller hardware equipment are adopted to cooperate with each other, so that the labor cost is greatly simplified, the whole forced process is completed with online debugging, the operation is simple, and the signal data precision is very high. The controller adopts an MPU (Main Processing Unit). The four divided internal memory areas in the controller MPU are respectively as follows: a calculation area, a marking area, a mandatory area and a mandatory data recording area. The forced data log area stores 5104 bytes of data.
In the invention, a worker uses an operating software tool in an upper computer to input a forced parameter information list and inputs a forced signal to a lower computer controller MPU through a communication program in a 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 the nuclear power plant equipment to be intervened.
The upper computer inputs a forced command to a forced recording area in the MPU of the lower computer through a communication mode of a self-maintenance protocol, and then the embedded software which is installed in advance executes a forced logic function according to the command.
Referring to fig. 2, fig. 2 is a schematic diagram of a communication process between the human-computer interface and the controller in the method, and based on the method, the implementation process is as follows:
1. a human-computer interface for providing a mandatory parameter list; the human-computer interface is a user input interface of the upper computer, and the mandatory parameter list comprises offset, length and mandatory values;
2. the communication program sends a forcing 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 into the corresponding position of the mandatory data recording area;
4. the embedded program in the controller periodically and circularly judges the data of the mandatory data recording area and rewrites the data of the mandatory area;
5. the communication program reads back the data of the forced marking area and returns the data to the human-computer interface;
6. and the human-computer interface displays whether the forcing is successful or not according to the forcing state. And (4) the nuclear power equipment is forced to work normally when the forced success shows that the nuclear power equipment works abnormally when the forced failure shows that the nuclear power equipment works abnormally, namely, the debugging of the nuclear power equipment is completed.
The method has the advantages that the forced parameter list is manually input, the upper computer software is adopted for online forcing, so that the debugging equipment is small in quantity, the process is simplified, the 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 online running equipment.
REDACE refers to Real-time and Deterministic Application Coding Environment, Real-time and Deterministic Application programming Environment. Referring to fig. 3, fig. 3 is a flowchart of a user human-machine interface operation process. The man-machine interface operation flow is as follows:
firstly, editing an algorithm through compiling software, 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 thirdly, after the monitoring is started, opening an algorithm graph page under the operator node, and then entering a visual monitoring function. In this case, variables in the algorithm page may be selected, and the enforcement or cancellation of the variables may be performed, or the bulk enforcement or bulk cancellation may be selected.
Fig. 4 is a schematic structural diagram of a variable forcing system suitable for nuclear power plant equipment, which is provided by the invention and is used for implementing the method, and the system comprises:
the upper computer 101 is used for receiving a mandatory parameter list input by a user and starting a communication module; receiving data returned by the communication module, judging whether the returned data is consistent with the data in the forcing parameter list, and if so, determining that the forcing process is successful;
a communication module 102, configured to send a forcing command to a controller through a function call; reading the data in the current mandatory data recording area, and returning the read data to the upper computer;
the controller 103 is configured to parse the mandatory command, obtain a mandatory parameter list, write data in the mandatory parameter list into the mandatory data recording area, and replace original data in the mandatory data recording area;
wherein the controller is disposed 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 equipment debugging process, the forcing success represents that the nuclear power station equipment normally works, namely the nuclear power station equipment debugging is completed, the equipment debugging is automatically realized, manual debugging on site is not needed, the labor cost is reduced, and the working efficiency is improved.
Based on the 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 marking area, a mandatory area, and a mandatory data recording area.
Further, the controller is provided with an embedded program; the controller is also used for periodically and circularly judging the data in the mandatory data recording area by using the embedded program and rewriting the data in the mandatory data recording area.
The embodiments are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same or similar parts among the embodiments are referred to each other. For the system disclosed by the embodiment, the description is relatively simple because the system corresponds to the method disclosed by the embodiment, and the relevant points can be referred to the method part for description.
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 components and steps have been described above generally in terms of their functionality in order to clearly illustrate this 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 implementation. 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. A software module may reside 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 present invention provides a method and a system for enforcing variables suitable for nuclear power plant equipment. The principles and embodiments of the present invention are explained herein using specific examples, which are presented only to assist in understanding the method and its core concepts. It should be noted that, for those skilled in the art, it is possible to make various improvements and modifications to the present invention without departing from the principle of the present invention, and those improvements and modifications also fall within the scope of the claims of the present invention.

Claims (8)

1. A method for variable enforcement for nuclear power plant equipment, comprising:
the upper computer receives a mandatory parameter list input by a user and starts a communication module;
the communication module sends a forcing command to the controller through function call;
the controller analyzes the mandatory command, acquires the mandatory parameter list, writes data in the mandatory parameter list into a mandatory data recording area, and replaces original data in the mandatory data recording area; the controller is arranged in the nuclear power station equipment;
the communication module reads the data in the current mandatory 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 forcing parameter list or not, and if so, determines that the forcing process is successful.
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 claim 2, wherein the controller includes a calculation area, a designation area, a mandatory area, and a mandatory data recording area.
4. The method of any one of claims 1 to 3, wherein the controller is installed with an embedded program; the communication module reads the data in the current mandatory data recording area, and after the data read is returned to the upper computer, the communication module further comprises:
the controller judges the data in the mandatory data recording area periodically and circularly by using the embedded program and rewrites the data in the mandatory data recording area.
5. A variable forcing system for nuclear power plant equipment, for implementing the method of any one of claims 1 to 4, comprising:
the upper computer is used for receiving a mandatory parameter list input by a user and starting the communication module; receiving data returned by the communication module, judging whether the returned data is consistent with the data in the forcing parameter list, and if so, determining that the forcing process is successful;
the communication module is used for sending a forcing command to the controller through function call; reading the data in the current mandatory data recording area, and returning the read data to the upper computer;
the controller is used for analyzing the mandatory command, acquiring the mandatory parameter list, writing data in the mandatory parameter list into a mandatory data recording area, and replacing original data in the mandatory data recording area; the controller is disposed in the nuclear power plant equipment.
6. The system of claim 5, wherein the communication module stores a communication program for communication between the host computer and the controller.
7. The system of claim 6, wherein the controller includes a calculation area, a designation area, a mandatory area, and a mandatory data recording area.
8. The system according to any one of claims 5 to 7, wherein the controller is installed with an embedded program; the controller is also used for periodically and circularly judging the data in the mandatory data recording area by using the embedded program and rewriting the data in the mandatory data recording area.
CN201910879224.7A 2019-09-18 2019-09-18 Variable forcing method and system suitable for nuclear power station equipment Pending CN112530615A (en)

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Citations (7)

* Cited by examiner, † Cited by third party
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
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
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
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

Patent Citations (7)

* Cited by examiner, † Cited by third party
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
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
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
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

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