CN116153546A - System control method, device, computer equipment and storage medium - Google Patents

System control method, device, computer equipment and storage medium Download PDF

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Publication number
CN116153546A
CN116153546A CN202310356492.7A CN202310356492A CN116153546A CN 116153546 A CN116153546 A CN 116153546A CN 202310356492 A CN202310356492 A CN 202310356492A CN 116153546 A CN116153546 A CN 116153546A
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China
Prior art keywords
data
actual working
current control
control data
working data
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CN202310356492.7A
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Chinese (zh)
Inventor
柴大虎
孙新峰
王丹青
汤立宏
王耀刚
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China General Nuclear Power Corp
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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China General Nuclear Power Corp
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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Application filed by China General Nuclear Power Corp, Daya Bay Nuclear Power Operations and Management Co Ltd, Lingdong Nuclear Power Co Ltd, Guangdong Nuclear Power Joint Venture Co Ltd, Lingao Nuclear Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN202310356492.7A priority Critical patent/CN116153546A/en
Publication of CN116153546A publication Critical patent/CN116153546A/en
Pending legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Safety Devices In Control Systems (AREA)

Abstract

The application relates to a system control method, a system control device, a computer device and a storage medium. The method comprises the following steps: the method comprises the steps of obtaining actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices, determining current control data according to each actual working data, and controlling a control unit in the nuclear power station adjusting system according to the current control data. By adopting the method, the running stability of the nuclear power station regulating system can be improved.

Description

System control method, device, computer equipment and storage medium
Technical Field
The present disclosure relates to the field of nuclear island systems, and in particular, to a system control method, apparatus, computer device, and storage medium.
Background
There are some important regulation systems in the nuclear power plant, for example, a conventional island closed-circuit cooling water system, a low-pressure heater system, a generator stator cooling water system and the like, and whether these nuclear power plant regulation systems can stably operate determines whether a nuclear power plant unit can stably operate to a certain extent. Based on this, a system control method for a regulation system in a nuclear power plant has emerged.
The conventional system control method does not consider that a measuring device for measuring actual working data of a nuclear power station adjusting system has random faults, so that accurate actual working data cannot be obtained, and further, the operation of the nuclear power station adjusting system on a control unit is inconsistent with the operation required in the actual working, thereby threatening the safety of a nuclear power station unit, and the improvement is needed.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a system control method, apparatus, computer device, and storage medium capable of improving the operation stability of a nuclear power plant conditioning system.
In a first aspect, the present application provides a system control method. The method comprises the following steps:
acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices;
determining current control data according to each actual working data;
and controlling a control unit in the nuclear power station adjusting system according to the current control data.
In one embodiment, determining current control data according to each actual working data includes:
determining the validity of each actual working data according to the comparison result between each actual working data and the effective working data range; and determining current control data according to the validity of each actual working data.
In one embodiment, determining the current control data according to the validity of each actual working data includes:
according to the validity of each actual working data, determining the effective quantity of the effective actual working data; and determining the current control data according to the ratio between the effective quantity and the total quantity of each piece of actual working data, the effective actual working data and the last control data.
In one embodiment, determining the current control data based on the ratio between the effective number and the total number of each actual working data, the effective actual working data and the last control data, includes:
if the ratio between the effective quantity and the total quantity is larger than the set ratio, determining current control data according to the effective actual working data; if the ratio between the effective number and the total number is smaller than the set ratio, determining the current control data according to the last control data.
In one embodiment, determining current control data based on valid actual operating data includes:
and taking the average value of the effective actual working data as the current control data.
In one embodiment, if the current control data is determined according to the previous control data, after the control unit in the nuclear power plant adjustment system is controlled according to the current control data, the method further includes:
and switching the control mode from automatic control to manual control, and outputting warning information to remind operation and maintenance personnel to intervene in the nuclear power station regulating system.
In a second aspect, the present application further provides a system control device. The device comprises:
the data acquisition module is used for acquiring actual working data of the nuclear power station adjusting system measured by at least two identical measuring devices;
the data determining module is used for determining current control data according to each actual working data;
and the system control module is used for controlling the control unit in the nuclear power station regulating system according to the current control data.
In a third aspect, the present application also provides a computer device. The computer device comprises a memory storing a computer program and a processor which when executing the computer program performs the steps of:
acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices;
determining current control data according to each actual working data;
and controlling a control unit in the nuclear power station adjusting system according to the current control data.
In a fourth aspect, the present application also provides a computer-readable storage medium. The computer readable storage medium having stored thereon a computer program which when executed by a processor performs the steps of:
acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices;
determining current control data according to each actual working data;
and controlling a control unit in the nuclear power station adjusting system according to the current control data.
In a fifth aspect, the present application also provides a computer program product. The computer program product comprises a computer program which, when executed by a processor, implements the steps of:
acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices;
determining current control data according to each actual working data;
and controlling a control unit in the nuclear power station adjusting system according to the current control data.
According to the system control method, the device, the computer equipment and the storage medium, the actual working data of the nuclear power station adjusting system is measured by introducing at least two identical measuring devices, so that the problem that when a single measuring device is adopted, accurate actual working data cannot be obtained due to random faults of the measuring devices can be avoided; and the current control data can be accurately determined according to each actual working data, so that the control unit in the nuclear power station adjusting system is accurately controlled, the stable operation of the nuclear power station adjusting system is ensured, and the safety of a nuclear power station unit is improved.
Drawings
FIG. 1 is a diagram of an application environment for a system control method in one embodiment;
FIG. 2 is a flow chart of a system control method in one embodiment;
FIG. 2A is a logic diagram of an SRI conventional island closed-circuit cooling water system;
FIG. 2B is a logic diagram of a modified SRI conventional island closed-circuit cooling water system;
FIG. 3 is a flow diagram of control data determination in one embodiment;
FIG. 4 is a flow chart of a system control method according to another embodiment;
FIG. 4A is a raw logic diagram of an ABP low pressure feedwater heater system;
FIG. 4B is a logic diagram of a modified ABP low pressure feedwater heater system;
FIG. 5 is a block diagram of a system control device in one embodiment;
FIG. 6 is a block diagram of a system control device according to another embodiment;
fig. 7 is an internal structural diagram of a computer device in one embodiment.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application will be further described in detail with reference to the accompanying drawings and examples. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the present application.
The system control method provided by the embodiment of the application can be applied to an application environment shown in fig. 1. Wherein the terminal 102 communicates with the server 104 via a network. The data storage system may store data that the server 104 needs to process. For example, control data of a previous time of a nuclear power plant control system, and the like. The data storage system may be integrated on the server 104 or may be located on a cloud or other network server. For example, the server 104 acquires actual working data of the nuclear power plant adjusting system measured by at least two identical measuring devices, determines current control data according to each actual working data, and then controls a control unit in the nuclear power plant adjusting system according to the current control data; further, the server 104 may send relevant information (e.g., warning information sent when the nuclear power plant conditioning system fails) during operation of the nuclear power plant conditioning system to the terminal 102. The terminal 102 may be, but is not limited to, various personal computers, notebook computers, smart phones, tablet computers, and internet of things devices. The server 104 may be implemented as a stand-alone server or as a server cluster of multiple servers.
In the practical application of the nuclear power station regulating system, because the transient working condition (namely the instantaneously generated fault effect) of the regulating system, which is possibly caused by the random fault of the measuring device in the regulating system, is not considered, the operation and maintenance personnel can hardly effectively intervene in the control of the unit, thereby causing the shutdown or the shutdown of the unit of the nuclear power station and threatening the safety of the unit of the nuclear power station.
Based on this, in one embodiment, as shown in fig. 2, a system control method is provided, and the method is applied to the server in fig. 1 for illustration, and includes the following steps:
s201, acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices.
The nuclear power station adjusting system refers to a related system used for adjusting and controlling in the nuclear power station; the actual working data refers to relevant data of the nuclear power station regulating system when working.
In this embodiment, the nuclear power plant conditioning system may be an ABP low pressure feedwater heater system, an SRI conventional island closed-loop cooling water system, a GST generator stator cooling water system, a GGR turbine lubrication, a jackshaft and jigger system, and a GRH generator hydrogen cooling system, among others. Correspondingly, the actual working data can be water supply flow data in the ABP low-pressure water supply heater system; cooler outlet main pipe flow in SRI conventional island closed-circuit cooling water system; stator cooling water inlet temperature in the GST generator stator cooling water system; the temperature of lubricating oil in GGR turbine lubrication, top shaft and jigger system; hydrogen temperature in the GRH generator hydrogen cooling system.
Optionally, in order to ensure accuracy of acquiring actual working data of the nuclear power plant adjusting system, for each nuclear power plant adjusting system, a plurality of identical measuring devices may be configured to measure the actual working data of the nuclear power plant adjusting system. Further, in order to ensure that the actual working data acquired by the plurality of measuring devices do not affect each other, each measuring device needs to be configured on a different channel in the same area.
It will be appreciated that, due to the complex construction of the nuclear power plant conditioning system, only one measuring instrument may be included in a single measuring device, or a plurality of measuring instruments may be included.
For example, referring to FIG. 2A, in an SRI conventional island closed circuit cooling water system, conventional island closed circuit cooler outlet header flow is measured by a measuring instrument SRI001MD included in the measuring device. To ensure stable operation of the SRI conventional island closed circuit cooling water system, referring to fig. 2B, 3 measuring devices, namely, SRI001MD, SRI002MD, and SRI003MD3 measuring instruments can be configured to measure the flow of the mother pipe at the outlet of the conventional island closed circuit cooler at the same time.
Further, in order to maintain stable operation of the nuclear power plant control system when internal control of the nuclear power plant control system is performed, it is necessary to acquire actual operation data of the nuclear power plant control system measured by at least two identical measuring devices.
For example, in making adjustments to the cooling water outlet pressure valve SRI060VD in an SRI conventional island closed-circuit cooling water system, it is necessary to obtain the conventional island closed-circuit cooler outlet header flow measured by the measuring instruments SRI001MD, SRI002MD, and SRI003 MD.
S202, determining current control data according to each actual working data.
Wherein the control data refers to data for instructing a control unit in the nuclear power plant regulation system to operate.
Optionally, after each actual working data is obtained, each actual working data may be simultaneously input to a trained control data determining model, where the control data determining model may reject data having errors in each actual working data based on each input actual working data and parameters of the control data determining model itself, and then output current control data based on remaining actual working data.
For example, for SRI conventional island closed-loop cooling water system, the water supply flow A measured by 3 measuring instruments is obtained 1 、A 2 And A 3 After that, A is 1 、A 2 And A 3 Simultaneously input into a trained control data determining model, wherein the control data determining model detects the water supply flow A 1 With errors in the flow rate A of the water supply 1 After rejection, based on feed water flow A 2 And A 3 The current control data a is directly output.
S203, controlling a control unit in the nuclear power station adjusting system according to the current control data.
Wherein the control unit refers to a unit for regulation in a regulation system of a nuclear power plant.
In this embodiment, the control unit may be a valve in the ABP low pressure feedwater heater system that regulates the flow of feedwater; a cooling water outlet pressure valve in the SRI conventional island closed-loop cooling water system; a three-way valve in the GST generator stator cooling water system; shafting lubricating oil cooling water valves in GGR turbine lubrication, top shaft and jigger systems; and a control unit such as a hydrogen temperature control loop in the GRH generator hydrogen cooling system.
Optionally, after receiving the current control data, the current control data may be directly converted into related data for controlling a control unit in the nuclear power plant adjustment system based on a preset conversion relationship; and then performing related operations on the control units in the nuclear power plant regulation system based on the related data.
For example, with continued reference to fig. 2B, after determining the current control data a of the SRI normal island closed-circuit cooling water system, the related data T can be directly determined based on the current control data a and the preset conversion relationship; the relevant data T is then sent to the cooling water outlet pressure valve SRI060VD (i.e. the control unit) of the SRI normal island closed-circuit cooling water system, which is able to make an adjustment of the valve opening based on the relevant data T.
According to the system control method, the actual working data of the nuclear power station adjusting system is measured by introducing at least two identical measuring devices, so that the problem that accurate actual working data cannot be obtained due to random faults of the measuring devices when a single measuring device is adopted can be avoided; and the current control data can be accurately determined according to each actual working data, so that the control unit in the nuclear power station adjusting system is accurately controlled, the stable operation of the nuclear power station adjusting system is ensured, and the safety of a nuclear power station unit is improved.
In order to ensure accuracy of the current control data, an operation of performing validity judgment on the actual working data is introduced on the basis of the above embodiment, and based on this, in this embodiment, an alternative way of determining the current control data is provided, as shown in fig. 3, and specifically includes the following steps:
s301, determining the validity of each actual working data according to the comparison result between each actual working data and the valid working data range.
The effective working data range refers to a range of working data of the nuclear power station adjusting system in normal working, and can be used for judging the effectiveness of actual working data.
Optionally, for each nuclear power station adjusting system, determining an effective working data range corresponding to the nuclear power station adjusting system according to working data obtained when the nuclear power station adjusting system operates normally, and then comparing each actual working data with the effective working data range one by one, if a certain actual working data is within the effective working data range, the actual working data is effective; otherwise, if the actual working data is out of the effective working data range, the actual working data is invalid.
S302, determining current control data according to the validity of each actual working data.
Optionally, after determining the validity of each actual working data, the current control data may be obtained by averaging the valid actual working data.
Alternatively, the following steps may be taken to determine the current control data:
the first step is to determine the effective quantity of the effective actual working data according to the effectiveness of each actual working data.
Optionally, after determining the validity of each actual working data, the number of valid actual working data, that is, the valid number, is counted.
For example, for a SRI conventional island closed circuit cooling water system, when a feed water flow of A is obtained 1 、A 2 And A 3 Then, determining the water supply flow A based on the effective working data range corresponding to the SRI conventional island closed-circuit cooling water system 1 Outside the effective working data range, the water supply flow A 2 And A 3 Within the effective working data range, the effective number is therefore 2.
And a second step of determining current control data according to the ratio between the effective number and the total number of the actual working data, the effective actual working data and the last control data.
The last control data refers to the control data of the last moment when the nuclear power station regulating system stably operates.
Optionally, after the effective number is determined, a determination mode of determining the current control data according to the effective actual working data can be selected according to the ratio between the effective number and the total number of each actual working data; or selecting a determination mode for determining the current control data according to the previous control data.
Further, after the determination mode of the current control data is selected, the current control data is determined based on the determination mode of the current control data.
In the embodiment, by introducing the judgment on the validity of each actual working data, the measurement error caused by the fault of the measuring device in the actual working data is removed, the accuracy of the current control data is ensured, and the running stability of the nuclear power station regulating system is further improved.
On the basis of the above embodiment, in this embodiment, the manner of determining the current control data is further refined, and an alternative manner of determining the current control data is provided, which specifically includes the following steps:
alternatively, if the ratio between the effective number and the total number is greater than the set ratio, the current control data is determined according to the effective actual working data.
Wherein, the set proportion refers to a numerical value for determining the current control data determination mode.
Optionally, calculating the ratio between the effective number and the total number, if the ratio between the effective number and the total number is greater than the set ratio, the effective actual working data may be directly input into the control data determining model, and the control data determining model may directly output the current control data based on each input actual working data and parameters of the control data determining model itself.
Alternatively, the average value of the effective actual working data may be directly used as the current control data.
For example, for a SRI conventional island closed circuit cooling water system, when a feed water flow of A is obtained 1 、A 2 And A 3 After that, if the effective quantity is 2 (namely the water supply flow A 2 And A 3 Is an effective practical workAs data), the ratio between the effective quantity and the total quantity is set to 0.5, which is greater than the set ratio, so that the water supply flow A can be calculated 2 And A 3 As current control data.
Alternatively, if the ratio between the effective number and the total number is smaller than the set ratio, the current control data is determined according to the previous control data.
Alternatively, if the ratio between the effective number and the total number is smaller than the set ratio, the previous control data may be directly used as the current control data.
For example, for SRI conventional island closed-loop cooling water system, the last control data is A 4 The 3 water supply flows measured were A 1 、A 2 And A 3 After that, if the effective quantity is 1 (i.e. the water supply flow A 2 For effective actual working data), the ratio is set to be 0.5, and the ratio between the effective quantity and the total quantity is smaller than the set ratio, so that the last control data A of the SRI conventional island closed-circuit cooling water system can be obtained 4 Directly as current control data.
In this embodiment, by introducing the set proportion, the determination mode of the current control data can be accurately selected, thereby improving the accuracy of the current control data.
On the basis of the above embodiment, if the current control data is determined according to the previous control data, after the control unit in the nuclear power plant adjusting system is controlled according to the current control data, the control mode is also required to be switched from automatic control to manual control, and warning information is output to remind the operation and maintenance personnel to intervene in the nuclear power plant adjusting system.
Specifically, after the stable operation of the nuclear power plant regulation system is maintained by the previous control data, in order to prevent the failure of the nuclear power plant regulation system, it is necessary to switch the control mode from automatic control to manual control and output warning information to the terminal embedded with the nuclear power plant monitoring tool. Wherein, the tool can be APP, visual interface, applet, etc.; the warning information may include information about the particular nuclear power plant conditioning system that is malfunctioning, and about the particular time at which the malfunction is occurring.
In the embodiment, by introducing the switching of the control mode and the sending of the warning information, the timely intervention of operation and maintenance personnel on the failed nuclear power station adjusting system can be ensured, and the running stability of the nuclear power station adjusting system is further improved.
Fig. 4 is a schematic flow chart of a system control method in another embodiment, and on the basis of the foregoing embodiment, this embodiment provides an alternative example of the system control method. With reference to fig. 4, the specific implementation procedure is as follows:
s401, acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices.
S402, determining the validity of each actual working data according to the comparison result between each actual working data and the valid working data range.
S403, determining the effective quantity of the effective actual working data according to the effectiveness of each actual working data.
S404, determining current control data according to the ratio between the effective number and the total number of the actual working data, the effective actual working data and the last control data.
Specifically, if the ratio between the effective number and the total number is greater than the set ratio, determining current control data according to the effective actual working data. Alternatively, the average value of the effective actual working data may be used as the current control data.
If the ratio between the effective number and the total number is smaller than the set ratio, determining the current control data according to the last control data. Further, the control mode is switched from automatic control to manual control, and warning information is output so as to remind operation and maintenance personnel to intervene in the nuclear power station adjusting system.
S405, controlling a control unit in the nuclear power station adjusting system according to the current control data.
The specific process of S401 to S405 may refer to the description of the foregoing method embodiment, and its implementation principle and technical effect are similar, and are not repeated herein.
In practical applications, the configuration within the nuclear power plant conditioning system is complex, for example, referring to fig. 4A, for the ABP low-pressure feedwater heater system, the feedwater flows (i.e., actual operation data) of the low-pressure heaters ABP301RE and ABP401RE are measured by a measuring instrument ABP001MD included in the measuring device, and the feedwater flows of the low-pressure heaters ABP302RE and ABP402RE are measured by the measuring instrument ABP002 MD. The current control data of the ABP low-pressure feedwater heater system is determined by adding the actual working data measured by the measuring instrument ABP001MD and the measuring instrument ABP002 MD.
To ensure stable operation of the ABP low pressure feedwater heater system, referring to fig. 4B, 3 measuring devices, i.e., 6 measuring instruments ABP001MD, ABP002MD, ABP003MD, ABP004MD, ABP005MD, and ABP006MD, may be configured to measure the feedwater flow. Wherein, the measuring instruments ABP001MD, ABP003MD and ABP005MD can simultaneously measure the water supply flow rates of the low-pressure heater ABP301RE and the low-pressure heater ABP401 RE; the feedwater flows of the low-pressure heaters ABP302RE and ABP402RE are measured simultaneously by measuring instruments ABP002MD, ABP004MD, and ABP006 MD. Meanwhile, 6 measuring instruments ABP001MD, ABP002MD, ABP003MD, ABP004MD, ABP005MD, and ABP006MD are all arranged on different channels.
Further, after the actual working data measured by the 6 measuring instruments respectively are obtained, the actual working data B can be measured by the measuring instruments ABP001MD, ABP003MD and ABP005MD 1 、B 2 And B 3 Actual working data B 1 、B 2 And B 3 Comparing with the effective working data range of the ABP low-pressure feed water heater system to obtain an effective number of 2 (namely actual working data B 2 And B 3 Effective and set to 0.5), at this time, the actual working data B can be calculated 2 And B 3 Mean value determination of first control data S 1 。
Similarly, the actual working data C can be measured by measuring instruments ABP002MD, ABP004MD and ABP006MD 1 、C 2 And C 3 Actual working data C 1 、C 2 And C 3 Comparing the effective working data range of the ABP low-pressure feed water heater system with the effective working data range to obtain an effective number of 1, and at the moment, controlling the data C at the previous moment 4 As second control data S 2 The method comprises the steps of carrying out a first treatment on the surface of the Subsequently, the first control data S 1 And second control data S 2 The current control data S can be obtained by addition.
Furthermore, the current control data S can be directly converted into related data for controlling the valve CEX024VL in the ABP low-pressure feedwater heater system based on the current control data S and a preset conversion relationship, and then the valve CEX024VL can adjust the valve opening based on the related data.
It should be understood that, although the steps in the flowcharts related to the embodiments described above are sequentially shown as indicated by arrows, these steps are not necessarily sequentially performed in the order indicated by the arrows. The steps are not strictly limited to the order of execution unless explicitly recited herein, and the steps may be executed in other orders. Moreover, at least some of the steps in the flowcharts described in the above embodiments may include a plurality of steps or a plurality of stages, which are not necessarily performed at the same time, but may be performed at different times, and the order of the steps or stages is not necessarily performed sequentially, but may be performed alternately or alternately with at least some of the other steps or stages.
Based on the same inventive concept, the embodiment of the application also provides a system control device for realizing the above related system control method. The implementation of the solution provided by the device is similar to the implementation described in the above method, so the specific limitation in one or more embodiments of the system control device provided below may refer to the limitation of the system control method hereinabove, and will not be repeated herein.
In one embodiment, as shown in fig. 5, there is provided a system control apparatus 1 including: a data acquisition module 10, a data determination module 20, and a system control module 30, wherein:
the data acquisition module 10 is used for acquiring actual working data of the nuclear power station adjusting system measured by at least two identical measuring devices;
the data determining module 20 is configured to determine current control data according to each actual working data;
and the system control module 30 is used for controlling a control unit in the nuclear power station adjusting system according to the current control data.
In one embodiment, as shown in FIG. 6, the data determination module 20 includes:
a validity determining unit 21, configured to determine validity of each actual working data according to a comparison result between each actual working data and the valid working data range;
the data determining unit 22 is configured to determine current control data according to validity of each actual working data.
In one embodiment, the data determination module 20 is specifically configured to:
according to the validity of each actual working data, determining the effective quantity of the effective actual working data; and determining the current control data according to the ratio between the effective quantity and the total quantity of each piece of actual working data, the effective actual working data and the last control data.
In one embodiment, the data determination unit 22 includes:
the first subunit is used for determining current control data according to the effective actual working data if the ratio between the effective quantity and the total quantity is larger than the set ratio;
and the second subunit is used for determining the current control data according to the last control data if the ratio between the effective number and the total number is smaller than the set ratio.
In one embodiment, the first subunit is specifically configured to:
and taking the average value of the effective actual working data as the current control data.
In one embodiment, the system control device 1 further includes a control switching module, where the control switching module is specifically configured to:
and switching the control mode from automatic control to manual control, and outputting warning information to remind operation and maintenance personnel to intervene in the nuclear power station regulating system.
The respective modules in the above-described system control apparatus may be implemented in whole or in part by software, hardware, and combinations thereof. The above modules may be embedded in hardware or may be independent of a processor in the computer device, or may be stored in software in a memory in the computer device, so that the processor may call and execute operations corresponding to the above modules.
In one embodiment, a computer device is provided, which may be a server, the internal structure of which may be as shown in fig. 7. The computer device includes a processor, a memory, an Input/Output interface (I/O) and a communication interface. The processor, the memory and the input/output interface are connected through a system bus, and the communication interface is connected to the system bus through the input/output interface. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer programs, and a database. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The database of the computer equipment is used for storing data such as control data of the nuclear power station regulating system at the last moment. The input/output interface of the computer device is used to exchange information between the processor and the external device. The communication interface of the computer device is used for communicating with an external terminal through a network connection. The computer program is executed by a processor to implement a system control method.
It will be appreciated by those skilled in the art that the structure shown in fig. 7 is merely a block diagram of some of the structures associated with the present application and is not limiting of the computer device to which the present application may be applied, and that a particular computer device may include more or fewer components than shown, or may combine certain components, or have a different arrangement of components.
In one embodiment, a computer device is provided comprising a memory and a processor, the memory having stored therein a computer program, the processor when executing the computer program performing the steps of:
acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices;
determining current control data according to each actual working data;
and controlling a control unit in the nuclear power station adjusting system according to the current control data.
In one embodiment, when the processor executes logic in the computer program to determine current control data according to each actual working data, the following steps are specifically implemented:
determining the validity of each actual working data according to the comparison result between each actual working data and the effective working data range; and determining current control data according to the validity of each actual working data.
In one embodiment, the following steps are specifically implemented when the processor executes logic in the computer program to determine the current control data according to the validity of each actual working data:
according to the validity of each actual working data, determining the effective quantity of the effective actual working data; and determining the current control data according to the ratio between the effective quantity and the total quantity of each piece of actual working data, the effective actual working data and the last control data.
In one embodiment, the processor executes logic in the computer program to determine the current control data based on the ratio between the effective number and the total number of each actual working data, the effective actual working data and the previous control data, and specifically implements the following steps:
if the ratio between the effective quantity and the total quantity is larger than the set ratio, determining current control data according to the effective actual working data; if the ratio between the effective number and the total number is smaller than the set ratio, determining the current control data according to the last control data.
In one embodiment, the following steps are implemented when the processor executes logic in the computer program to determine the current control data based on the actual working data available:
and taking the average value of the effective actual working data as the current control data.
In one embodiment, if the current control data is determined according to the previous control data, after the control unit in the nuclear power plant regulation system is controlled according to the current control data, the following steps are specifically implemented when the processor executes logic in the computer program:
and switching the control mode from automatic control to manual control, and outputting warning information to remind operation and maintenance personnel to intervene in the nuclear power station regulating system.
In one embodiment, a computer readable storage medium is provided having a computer program stored thereon, which when executed by a processor, performs the steps of:
acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices;
determining current control data according to each actual working data;
and controlling a control unit in the nuclear power station adjusting system according to the current control data.
In one embodiment, the code logic in the computer program for determining the current control data based on the actual operational data, when executed by the processor, performs the steps of:
determining the validity of each actual working data according to the comparison result between each actual working data and the effective working data range; and determining current control data according to the validity of each actual working data.
In one embodiment, the code logic in the computer program for determining the current control data based on the validity of each actual working data, when executed by the processor, specifically implements the steps of:
according to the validity of each actual working data, determining the effective quantity of the effective actual working data; and determining the current control data according to the ratio between the effective quantity and the total quantity of each piece of actual working data, the effective actual working data and the last control data.
In one embodiment, the code logic in the computer program for determining the current control data based on the ratio between the effective number and the total number of each actual job data, the effective actual job data and the previous control data, when executed by the processor, specifically implements the steps of:
if the ratio between the effective quantity and the total quantity is larger than the set ratio, determining current control data according to the effective actual working data; if the ratio between the effective number and the total number is smaller than the set ratio, determining the current control data according to the last control data.
In one embodiment, the code logic in the computer program for determining the current control data based on the valid actual working data, when executed by the processor, specifically implements the steps of:
and taking the average value of the effective actual working data as the current control data.
In one embodiment, if the current control data is determined according to the previous control data, after the control unit in the nuclear power plant adjustment system is controlled according to the current control data, the following steps are specifically implemented when the code logic in the computer program is executed by the processor:
and switching the control mode from automatic control to manual control, and outputting warning information to remind operation and maintenance personnel to intervene in the nuclear power station regulating system.
In one embodiment, a computer program product is provided comprising a computer program which, when executed by a processor, performs the steps of:
acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices;
determining current control data according to each actual working data;
and controlling a control unit in the nuclear power station adjusting system according to the current control data.
In one embodiment, the computer program is executed by the processor to determine the operation of the current control data based on the actual working data, and specifically implement the steps of:
determining the validity of each actual working data according to the comparison result between each actual working data and the effective working data range; and determining current control data according to the validity of each actual working data.
In one embodiment, the computer program is executed by the processor to determine the operation of the current control data based on the validity of each actual working data, and specifically implement the following steps:
according to the validity of each actual working data, determining the effective quantity of the effective actual working data; and determining the current control data according to the ratio between the effective quantity and the total quantity of each piece of actual working data, the effective actual working data and the last control data.
In one embodiment, the computer program is executed by the processor to determine the operation of the current control data based on the ratio between the effective number and the total number of each actual job data, the effective actual job data and the last control data, and specifically implement the steps of:
if the ratio between the effective quantity and the total quantity is larger than the set ratio, determining current control data according to the effective actual working data; if the ratio between the effective number and the total number is smaller than the set ratio, determining the current control data according to the last control data.
In one embodiment, the computer program is executed by the processor to determine the operation of the current control data based on the actual working data in effect, and specifically implement the steps of:
and taking the average value of the effective actual working data as the current control data.
In one embodiment, if the current control data is determined according to the previous control data, the following steps are specifically implemented when the computer program is executed by the processor after the control unit in the nuclear power plant adjustment system is controlled according to the current control data:
and switching the control mode from automatic control to manual control, and outputting warning information to remind operation and maintenance personnel to intervene in the nuclear power station regulating system.
It should be noted that, the data related to the present application (including, but not limited to, the last time control data of the nuclear power plant regulation system, etc.) are information and data fully authorized by each party, and the collection, use and processing of the related data need to comply with the related laws and regulations and standards of the related country and region.
Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, database, or other medium used in the various embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, high density embedded nonvolatile Memory, resistive random access Memory (ReRAM), magnetic random access Memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric Memory (Ferroelectric Random Access Memory, FRAM), phase change Memory (Phase Change Memory, PCM), graphene Memory, and the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory, and the like. By way of illustration, and not limitation, RAM can be in the form of a variety of forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), and the like. The databases referred to in the various embodiments provided herein may include at least one of relational databases and non-relational databases. The non-relational database may include, but is not limited to, a blockchain-based distributed database, and the like. The processors referred to in the embodiments provided herein may be general purpose processors, central processing units, graphics processors, digital signal processors, programmable logic units, quantum computing-based data processing logic units, etc., without being limited thereto.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The above examples only represent a few embodiments of the present application, which are described in more detail and are not to be construed as limiting the scope of the present application. It should be noted that it would be apparent to those skilled in the art that various modifications and improvements could be made without departing from the spirit of the present application, which would be within the scope of the present application. Accordingly, the scope of protection of the present application shall be subject to the appended claims.

Claims (10)

1. A system control method, the method comprising:
acquiring actual working data of a nuclear power station adjusting system measured by at least two identical measuring devices;
determining current control data according to each actual working data;
and controlling a control unit in the nuclear power station adjusting system according to the current control data.
2. The method of claim 1, wherein determining current control data based on each actual operating data comprises:
determining the validity of each actual working data according to the comparison result between each actual working data and the effective working data range;
and determining current control data according to the validity of each actual working data.
3. The method of claim 2, wherein determining current control data based on validity of each actual job data comprises:
according to the validity of each actual working data, determining the effective quantity of the effective actual working data;
and determining current control data according to the ratio between the effective quantity and the total quantity of each piece of actual working data, the effective actual working data and the last control data.
4. A method according to claim 3, wherein said determining current control data based on the ratio between the effective number and the total number of each actual working data, the effective actual working data and the last control data, comprises:
if the ratio between the effective number and the total number is larger than the set ratio, determining current control data according to effective actual working data;
if the ratio between the effective number and the total number is smaller than the set ratio, determining the current control data according to the last control data.
5. The method of claim 4, wherein determining current control data based on valid actual operating data comprises:
and taking the average value of the effective actual working data as the current control data.
6. The method of claim 4, wherein if the current control data is determined based on a previous control data, the method further comprises, after controlling a control unit within the nuclear power plant conditioning system based on the current control data:
and switching the control mode from automatic control to manual control, and outputting warning information to remind operation and maintenance personnel to intervene in the nuclear power station regulating system.
7. A system control apparatus, the apparatus comprising:
the data acquisition module is used for acquiring actual working data of the nuclear power station adjusting system measured by at least two identical measuring devices;
the data determining module is used for determining current control data according to each actual working data;
and the system control module is used for controlling the control unit in the nuclear power station adjusting system according to the current control data.
8. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any of claims 1 to 6 when the computer program is executed.
9. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
10. A computer program product comprising a computer program, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
CN202310356492.7A 2023-03-30 2023-03-30 System control method, device, computer equipment and storage medium Pending CN116153546A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202310356492.7A CN116153546A (en) 2023-03-30 2023-03-30 System control method, device, computer equipment and storage medium

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202310356492.7A CN116153546A (en) 2023-03-30 2023-03-30 System control method, device, computer equipment and storage medium

Publications (1)

Publication Number Publication Date
CN116153546A true CN116153546A (en) 2023-05-23

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Country Status (1)

Country Link
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