CN111812998A - Nuclear power plant double-unit digital instrument control verification system and method - Google Patents

Nuclear power plant double-unit digital instrument control verification system and method Download PDF

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Publication number
CN111812998A
CN111812998A CN202010512839.9A CN202010512839A CN111812998A CN 111812998 A CN111812998 A CN 111812998A CN 202010512839 A CN202010512839 A CN 202010512839A CN 111812998 A CN111812998 A CN 111812998A
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unit
control
nuclear power
power plant
module
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CN111812998B (en
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张才科
曲鸣
谢成龙
刘培邦
周智
陆潘
苏继昌
姚敏剑
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CNNC Nuclear Power Operation Management Co Ltd
China Nuclear Power Operation Technology Corp Ltd
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CNNC Nuclear Power Operation Management Co Ltd
China Nuclear Power Operation Technology Corp Ltd
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    • GPHYSICS
    • G05CONTROLLING; REGULATING
    • G05BCONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
    • G05B17/00Systems involving the use of models or simulators of said systems
    • G05B17/02Systems involving the use of models or simulators of said systems electric

Abstract

The invention discloses a nuclear power plant double-unit digital instrument control verification system and a method, wherein the system comprises: the simulation model layer simulates the operation of a nuclear power plant unit based on the operation instruction and generates operation data, and comprises a first simulation model server and a second simulation model server for simulating the nuclear power plant; the control logic layer receives an operation instruction sent by the human-computer interface layer, accesses the simulation model layer, responds to the operation instruction to perform corresponding service logic processing, calculates and analyzes the working conditions of the first unit and the second unit of the nuclear power plant in real time based on the operation data, measures the working condition deviation, corrects DCS configuration logic and parameters, generates a nuclear power plant unit operation control instruction based on the corrected DCS configuration logic and parameters, and sends the operation instruction to the control logic layer and receives a processing result returned by the control logic layer. The advantages are that: the efficiency of the instrument control system maintenance is improved, and an operation platform for skill training is provided for DCS operation and maintenance personnel of the nuclear power plant.

Description

Nuclear power plant double-unit digital instrument control verification system and method
Technical Field
The invention belongs to the technical field of nuclear power plant control, and particularly relates to a double-unit digital instrument control verification system and a method for a nuclear power plant.
Background
The DCS system has been widely used in a nuclear power plant in recent years because of its advantages such as reliability and stability. However, the DCS system has many test blind areas in the factory test and field debugging processes, and it is impossible to completely cover and test the system defects. Defects of the DCS and blind points of operation and maintenance personnel for cognition on the DCS can cause that some common operation events occur in the operation and maintenance process of the DCS, and unplanned shutdown can be caused in severe cases. In recent years, unscheduled shutdown events of nuclear power plants of the middle nuclear group occur for many times, and most reasons are related to a DCS system through analysis. Therefore, in order to ensure the safe and stable operation of the nuclear power plant, a DCS verification system parallel to an actual unit is urgently required to be built for verifying the transformation upgrading or test scheme of the DCS of the nuclear power plant, analyzing the events which occur in the past, providing guidance for the daily operation and maintenance of the DCS, checking the potential safety hazards of the DCS, training the skills of related personnel of the nuclear power plant, and protecting and driving the nuclear power plant in the safe and stable operation.
The existing nuclear power generating units are basically built together by two units, and 1-layer equipment of DCS systems of the two units are in the same ring network to form intercommunication and interconnection. During the overhaul of the power plant, one unit is generally out of service, and the other unit is normally operated. For a unit which is shut down, overhaul operations such as starting and stopping can be carried out on equipment of an important system during overhaul, if a DCS has potential defects, a control instruction can be mistakenly sent to the running unit, and shutdown and even shutdown can be caused under severe conditions. Such accidents have also occurred before. Therefore, the double-unit digital instrument control verification system can be established to comprehensively verify the double-unit instrument control system, and the possibility of accidents caused by insufficient scheme demonstration is reduced. The research of information security inspection, defense and optimization can be completed; finishing the recurrence and analysis of DCS fault conditions; and completing verification of the DCS software change or upgrade scheme.
The above information disclosed in this background section is only for enhancement of understanding of the background of the invention and therefore it may contain information that does not form the prior art that is well known to those of ordinary skill in the art.
Disclosure of Invention
The invention aims to provide a two-unit digital instrument control verification system and a two-unit digital instrument control verification method for a nuclear power plant, which can effectively overcome the defects in the prior art.
The technical scheme of the invention is as follows:
a nuclear power plant double-unit digital instrument control verification system comprises a simulation module, a control logic module and a human-computer interface module, wherein,
the simulation module comprises a first simulation model server for simulating a process system of a first unit of the nuclear power plant and a second simulation model server for simulating a process system of a second unit of the nuclear power plant, the simulation module is in communication connection with the control logic module through the data communication server, and the simulation module simulates the operation of the first unit and the second unit of the nuclear power plant and generates operation data based on an operation instruction sent by the human-computer interface module;
the control logic module receives the operation instruction sent by the human-computer interface module and the simulation module, responds to the operation instruction to perform corresponding service logic processing, the service logic processing comprises real-time calculation and analysis of the working conditions of the first unit and the second unit of the nuclear power plant, measurement of the working condition deviation, correction of DCS configuration logic and parameters and generation of nuclear power plant unit operation control instructions based on the corrected DCS configuration logic and parameters,
the control logic module comprises a control logic module and a control logic module,
the DCS one-layer control system comprises a first safety level instrument control system and a first non-safety level instrument control system for operating a first unit control logic configuration of the nuclear power plant and a second safety level instrument control system and a second non-safety level instrument control system for operating a second unit control logic configuration of the nuclear power plant, wherein the first safety level instrument control system and the second safety level instrument control system respectively comprise a 1E level virtual controller for controlling virtual equipment, a 1E channel controller and a first exchange unit for communication, the first non-safety level instrument control system and the second non-safety level instrument control system respectively comprise an NC level virtual controller for controlling the virtual equipment, an NC level control cabinet for controlling the virtual equipment and a second exchange unit for communication, the 1E channel controller and the NC level control cabinet are respectively connected with a data communication server through I/O interface communication,
a first AW interface server and a second AW interface server which are respectively connected with the first switching unit and the second switching unit in a communication way,
a first front-end server and a second front-end server which are respectively connected with the first AW interface server and the second AW interface server in a communication way,
the first HST/ALM/MTK/AW/CSA server and the second HST/ALM/MTK/AW/CSA server comprise a history library, an alarm, a clock, an AW engineer station and a CSA station, and the first HST/ALM/MTK/AW/CSA server and the second HST/ALM/MTK/AW/CSA server are respectively connected with the DCS layer control system, the first AW interface server and the second AW interface server in a communication mode;
the human-computer interface module sends an operation instruction to the control logic module and receives a processing result returned by the control logic module;
the human-machine interface module comprises a human-machine interface module,
the first human-computer interface and the second human-computer interface realize corresponding human-computer interaction operation, send corresponding operation instructions to the first non-safety instrument control system and the second non-safety instrument control system and receive returned processing results,
and the first safety level DCS man-machine interface and the second safety level DCS man-machine interface realize corresponding man-machine interaction operation, send corresponding operation instructions to the first safety level instrument control system and the second safety level instrument control system and receive returned processing results.
Also comprises a verification control module which sends an operation instruction to the simulation module and receives a processing result returned by the simulation module, the verification control station comprises,
the first verification control station and the second verification control station realize corresponding man-machine interaction operation, an operator executes corresponding operation according to requirements, and the control stations send corresponding operation instructions to the process simulation model and receive corresponding processing results of model dynamics.
The verification control module generates nuclear power plant unit fault information and sends the simulation module, the simulation module carries out corresponding service logic processing and generates operation data based on the nuclear power plant unit fault information, the verification control module and the logic control module are fed back, the logic control module formulates a corresponding control regulation strategy according to the change of process parameters in the simulation module and generates a control instruction, the control instruction is sent to the simulation module, the simulation module carries out corresponding service processing and dynamically responds to the operation data in order to generate, and the first unit and the second unit can operate the functions in parallel.
When the double-unit digital instrument control verification system of the nuclear power plant breaks down, the control logic module generates DCS fault information, and calculates and analyzes the working conditions of the first unit and the second unit of the nuclear power plant, measures the working condition deviation and corrects DCS configuration logic and parameters based on the DCS fault information.
The first switching unit comprises gateway equipment and a switch which is respectively connected with the 1E-level virtual controller and the 1E channel controller, and the second switching unit comprises a switch which is respectively connected with the NC-level virtual controller and the NC-level control cabinet.
The process system comprises a simulation model unit for simulating a nuclear island, a conventional island and a BOP part, and the simulation model server comprises a simulator for simulating the process system in a ratio of 1: 1.
The DCS layer control system further comprises a Root switch for data interaction, the first switching unit and the second switching unit are respectively provided with the Root switch, and the second switching unit comprises a field communication protocol for communicating field equipment and a virtual communication protocol for communicating virtual equipment.
The first-layer DCS control system is in communication connection with the human-computer interface module through a third exchange unit, and further comprises a first second-layer DCS calculation server, a second-layer DCS calculation server, a historical data server and a real-time data server, wherein the first second-layer DCS calculation server and the second-layer DCS calculation server are used for calculating the equipment states of the first unit and the second unit of the nuclear power plant respectively.
The human-machine interface module also comprises a human-machine interface module,
a first DGS station and a second DGS station, each communicatively coupled to a non-security instrumented system, the DGS stations configured to generate a control logic configuration offline,
a first listing center and a second listing center configured to lock predetermined equipment of first and second units of the nuclear power plant, respectively.
An instrument control verification method of a nuclear power plant double-unit digital instrument control verification system comprises the following steps:
firstly, generating an operation instruction, wherein the operation instruction is sent to a simulation module through a verification control station;
secondly, responding to the operation instruction, adjusting operation data by the simulation module according to the operation instruction, returning the operation data to the control logic module, and performing corresponding service logic processing by the control logic module, wherein the service logic processing comprises real-time calculation and analysis of the working condition of the nuclear power unit based on the operation data, measurement of the working condition deviation, correction of DCS configuration logic and parameters, and generation of a nuclear power unit operation control instruction based on the corrected DCS configuration logic and parameters, wherein the NC-level control cabinet operates and operates field equipment based on the operation instruction, and the 1E-level virtual controller and the NC-level virtual controller virtually operate virtual equipment based on the operation instruction;
thirdly, responding to the control instruction, the simulation module dynamically responds according to the control instruction to obtain a corresponding processing result, the processing result is returned to the human-computer interface module through the control logic module, and meanwhile, the operation data is sent to the verification control module;
the first unit and the second unit can run in parallel, or one of the units can be run to verify whether the other unit is influenced.
The invention has the beneficial effects that: in the prior art, an in-service nuclear power plant is basically constructed by two units together, and 1-layer networks of DCS systems of the two units are communicated and are in the same ring network. If there are potential design defects, the operation of the DCS system equipment of one unit may affect the operation of another unit. During the overhaul period of the power plant, one unit is generally stopped and the other unit is normally operated, the stopped unit can involve the starting and stopping of some important system equipment, and if the stopped unit is mistakenly sent to the operating unit, the unit can be stopped and stopped in a serious condition. Similar events happen before, so that the verification coverage area is wider by adopting the double units, and the safe and stable operation of the power plant can be ensured. The nuclear power plant double-unit digital instrument control verification system is used as a pre-implementation platform before nuclear power plant instrument control transformation and upgrade, verifies the feasibility of an implementation scheme, reduces the possibility of non-stop caused by insufficient demonstration of the scheme, can reproduce and analyze the conventional non-stop events, and simultaneously is used as experience feedback to check similar problems in the instrument control system item by item. The non-safety instrument control system comprises an NC-level virtual controller for controlling the virtual equipment and an NC-level control cabinet for controlling the field equipment, so that instrument control verification can be simultaneously carried out on the field equipment and the virtual equipment, and the applicability and the authenticity of verification of the invention are further improved. The nuclear power plant double-unit digital instrument control verification system disclosed by the invention is used for carrying out tests and verification, so that the maintenance efficiency of the instrument control system is improved, an operation platform for skill training is provided for nuclear power plant DCS operation and maintenance personnel, and professional talents in the DCS operation and maintenance field are cultured. The invention adopts a control system 1:1 of the actual operation unit for the first time, and provides a solid foundation for checking the potential design defects of the control system, verifying the DCS upgrading and transforming scheme of the unit, analyzing events, feeding experience and the like.
The nuclear power plant double-unit digital instrument control verification system integrates multiple state monitoring including a DCS control equipment state, a switch state, a virtual controller and a workstation computer state, realizes comprehensive monitoring, can guide the running state of the nuclear power plant unit control system in an all-around manner, meets the requirement of fine control, and improves the running reliability of the nuclear power plant unit control system; according to the invention, the verification is carried out according to the fault information of the nuclear power generating unit and the fault information reappearance of the DCS, the DCS configuration is modified, the design of the DCS configuration is gradually perfected, and the occurrence of equipment fault conditions is reduced.
The above description is only an overview of the technical solutions of the present invention, and in order to make the technical means of the present invention more clearly apparent, and to make the implementation of the content of the description possible for those skilled in the art, and to make the above and other objects, features and advantages of the present invention more obvious, the following description is given by way of example of the specific embodiments of the present invention.
Detailed Description
The present invention will be described in further detail with reference to specific examples.
The DCS minimum system is provided with a complete real object NC-level field control cabinet unit and a 1E-level field control cabinet unit. Therefore, the method can complete the off-line verification of the DCS system hardware replacement or upgrade scheme and the verification of the influence on the field process equipment after the equipment is replaced by the localization.
Certain terms are used throughout the description and claims to refer to particular components. As one skilled in the art will appreciate, various names may be used to refer to a component. This specification and claims do not intend to distinguish between components that differ in name but not function. In the following description and in the claims, the terms "include" and "comprise" are used in an open-ended fashion, and thus should be interpreted to mean "include, but not limited to. The description which follows is a preferred embodiment of the invention, but is made for the purpose of illustrating the general principles of the invention and not for the purpose of limiting the scope of the invention. The scope of the present invention is defined by the appended claims.
In order to facilitate understanding of the embodiments of the present invention, the following description will be further explained with reference to specific embodiments as examples.
A nuclear power plant double-unit digital instrument control verification system comprises a simulation module, a control logic module and a human-computer interface module, wherein,
the simulation module is configured to simulate the operation of a first unit and a second unit of the nuclear power plant based on an operation instruction sent by the human-computer interface module and generate operation data, the simulation module comprises a first simulation model server for simulating a process system of the first unit of the nuclear power plant and a second simulation model server for simulating a process system of the second unit of the nuclear power plant, and the simulation module is in communication connection with the control logic module through the data communication server;
a control logic module configured to receive the operation instruction sent by the human-computer interface module and access the simulation module, and to perform corresponding service logic processing in response to the operation instruction, the service logic processing including real-time calculation and analysis of the operating conditions of the first and second units of the nuclear power plant based on the operation data, measurement of the operating condition deviation, and correction of DCS configuration logic and parameters, and generation of a nuclear power plant unit operation control instruction based on the corrected DCS configuration logic and parameters, the control logic module including,
the DCS one-layer control system comprises a first safety level instrument control system and a first non-safety level instrument control system for operating a first unit control logic configuration of the nuclear power plant and a second safety level instrument control system and a second non-safety level instrument control system for operating a second unit control logic configuration of the nuclear power plant, wherein the first safety level instrument control system and the second safety level instrument control system respectively comprise a 1E level virtual controller for controlling virtual equipment, a 1E channel controller and a first exchange unit for communication, the first non-safety level instrument control system and the second non-safety level instrument control system respectively comprise an NC level virtual controller for controlling the virtual equipment, an NC level control cabinet for controlling the virtual equipment and a second exchange unit for communication, the 1E channel controller and the NC level control cabinet are respectively connected with a data communication server through I/O interface communication,
a first AW interface server and a second AW interface server which are respectively connected with the first switching unit and the second switching unit in a communication way,
first and second front-end servers communicatively coupled to the first AW interface server and the second AW interface server, respectively,
first and second HST/ALM/MTK/AW/CSA servers configured as historians, alarms, clocks, AW engineer stations and CSA stations, said first and second HST/ALM/MTK/AW/CSA servers communicatively connected to said DCS layer control system and said first and second AW interface servers, respectively;
a human-machine interface module configured to send an operation instruction to the control logic module and receive a processing result returned by the control logic module, the human-machine interface module comprising,
a first human-machine interface and a second human-machine interface which are configured to realize corresponding human-machine interaction operation, send corresponding operation instructions to the first non-safety instrument control system and the second non-safety instrument control system and receive returned processing results,
and the first safety level DCS man-machine interface and the second safety level DCS man-machine interface are configured to realize corresponding man-machine interaction operation, send corresponding operation instructions to the first safety level instrumentation and control system and the second safety level instrumentation and control system and receive returned processing results.
A first verification control module and a second verification control module configured to send operation instructions to the simulation module and receive processing results returned by the simulation module, the verification control station including,
the system comprises a first verification control station and a second verification control station, wherein the first verification control station and the second verification control station are configured to realize corresponding human-computer interaction operation, an operator executes corresponding operation according to requirements, and the control stations send corresponding operation instructions to a process simulation model and receive corresponding processing results of model dynamics.
In one embodiment, the simulation module of the nuclear power plant double-unit digital instrument control verification system can simulate various operation conditions of operating a nuclear power plant and simulate the fault mode of nuclear power plant equipment. The simulation module can receive the control instruction sent by the DCS control logic module, perform equipment action and feed back the equipment state to the DCS control logic. The process system simulated by the simulation model server comprises: the reactor core simulation system comprises a reactor core physical simulation model, a main loop thermal hydraulic simulation model, a process flow simulation model, an electrical system simulation model, a containment simulation model and the like.
In an embodiment of the two-unit digital instrumentation verification system for the nuclear power plant, the two-unit digital instrumentation verification system for the nuclear power plant further includes a verification control module configured to generate fault information of the nuclear power plant unit and send the fault information to the control logic module, the control logic module performs corresponding service logic processing based on the fault information of the nuclear power plant unit and generates a control instruction, and the simulation module simulates operation of the first and second units of the nuclear power plant based on the control instruction and generates operation data to feed back the verification control module.
In one embodiment of the nuclear power plant double-unit digital instrument control verification system, when the nuclear power plant double-unit digital instrument control verification system has a fault, the control logic module generates DCS fault information, calculates and analyzes the working conditions of the first and second units of the nuclear power plant, measures the working condition deviation and corrects DCS configuration logic and parameters based on the DCS fault information.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the non-safety control logic configuration comprises a physical control cabinet with minimum configuration, the rest cabinets are simulated in a 3D simulation mode, the physical controller and a virtual controller, control logic configuration engineering consistent with that of the nuclear power plant, a configuration engineer station, an interface with a process system, the physical cabinet is realized in a hard wiring mode, the virtual controller is realized in a software communication mode, and the like.
In one embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the process system comprises a simulation model unit for simulating a nuclear island, a conventional island and a BOP part, and the simulation model server comprises a simulator for simulating the process system in a ratio of 1: 1.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the first switching unit includes a gateway device and a switch connected to the 1E-level virtual controller and the 1E-channel controller, respectively, and the second switching unit includes a switch connected to the NC-level virtual controller and the NC-level control cabinet, respectively.
In an embodiment of the two-unit digital instrument control verification system of the nuclear power plant, the DCS layer control system further includes a Root switch for data interaction, the first switching unit and the second switching unit are respectively provided with a Root switch, and the second switching unit includes a field communication protocol for communicating with field devices and a virtual communication protocol for communicating with virtual devices.
In an embodiment of the two-unit digital instrument control verification system of the nuclear power plant, the first layer DCS control system is in communication connection with the human-computer interface module via a third exchange unit, and further includes a first and a second layer DCS calculation servers, a historical data server and a real-time data server, which are respectively used for calculating the device states of the first and the second units of the nuclear power plant.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the control logic module is a nuclear power plant DCS control logic module and includes non-security level and security level control logic. The control logic module can receive an operation instruction of the DCS human-computer interface module, carry out logic operation, send the instruction to the simulation module, receive the equipment feedback state of the model, and feed the feedback state to the DCS human-computer interface module for display after the logic operation.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the human-machine interface module further comprises,
a first DGS station and a second DGS station, each communicatively coupled to a non-security instrumented system, the DGS stations configured to generate a control logic configuration offline,
a first listing center and a second listing center configured to lock predetermined equipment of first and second units of the nuclear power plant, respectively.
In an embodiment of the nuclear power plant double-unit digital instrument control verification system, the nuclear power plant DCS human-computer interface comprises a non-safety-level human-computer interface and a safety-level human-computer interface, the safety-level human-computer interface is realized in an analog simulation mode, and the safety-level DCS human-computer interface is consistent with the nuclear power plant DCS human-computer interface in configuration. The human machine interface includes OWP operator station, DGS configuration engineer station, historian station, interface station to control logic, etc. And operating engineering data of the nuclear power plant DCS man-machine interface, wherein the engineering data comprises functions of flow chart operation display, alarm, log, trend and the like. The human-computer interface module is mainly responsible for the operation of the nuclear power plant equipment and displays the feedback state of the equipment.
In one embodiment of the nuclear power plant double-unit digital instrument control verification system, a simulation module takes a nuclear power plant reference unit as a simulation object, and a process system of the nuclear power plant reference unit is simulated in a ratio of 1:1 and comprises a verification control function.
In an embodiment of the two-Unit digital instrument control verification system for the nuclear power plant, the first simulation model server is a Unit1 simulation model server, and runs a simulation model program of a nuclear power plant process system. The second simulation model server is a Unit2 simulation model server, which runs a nuclear power plant process system simulation model program.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the data communication server is an L1L0 data communication server, and is responsible for data interaction between the simulation model and the DCS system.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, a first-level DCS control system runs a power plant control logic configuration, wherein the first-level DCS control system comprises a first non-safety level, a second non-safety level and a first safety level instrument control system, and the control of the scale of the power plant in a ratio of 1:1 is realized.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the first and second security levels and the first and second non-security level instrument control systems of the control logic module all adopt virtual machine control systems, and control logic is downloaded from a field unit.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the first and second AW interface servers are DCS 1-layer communication servers; SAR is a historical data server; STR is a real-time data server; the CFR is a front-end server, and the DCS is a 2-layer communication server; the CCT is a central server and is responsible for processing all KIC data; OWP is an operator station responsible for plant operation control and parameter monitoring; TAGGING is a card hanging center and is responsible for hanging cards for equipment; DGS is a two-layer engineer station;
in one embodiment of the two-unit digital instrument control verification system for the nuclear power plant, a process system model part comprises a nuclear island, a conventional island and a BOP part, and a full-range simulator is used for referring to a simulation range and precision.
In an embodiment of the two-unit digital instrument control verification system of the nuclear power plant, the human-computer interface comprises an operating unit main control room control interface OWP, TAGGING, DGS, SVDU, an instrument control operation and maintenance support system and the like.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the two-unit digital instrument control verification system for the nuclear power plant is networked through an industrial ethernet.
In an embodiment of the two-unit digital instrument control verification system for the nuclear power plant, the NC-level control cabinet comprises a power supply, a controller, a communication interface module and a wiring terminal.
The instrument control verification method utilizing the nuclear power plant double-unit digital instrument control verification system comprises the following steps,
a first step of generating an operation instruction, the operation instruction being sent to the simulation module via the verification control station,
and a second step, responding to the operation instruction, adjusting the operation data by the simulation module according to the operation instruction, and returning the operation data to the logic control layer. The control logic module carries out corresponding service logic processing, wherein the service logic processing comprises the steps of calculating and analyzing the working condition of the nuclear power unit in real time based on the operating data, measuring the working condition deviation, correcting DCS configuration logic and parameters, and generating a nuclear power unit operation control command based on the corrected DCS configuration logic and parameters, wherein the NC-level control cabinet operates and operates the field equipment based on the operation command, the 1E-level virtual controller and the NC-level virtual controller virtually operate the virtual equipment based on the operation command,
and a third step, responding to the control instruction, wherein the simulation module dynamically responds according to the control instruction to obtain a corresponding processing result, and the processing result is returned to the human-computer interface module through the control logic module. And meanwhile, the operation data is sent to the verification control module.
The first and second units may be run in parallel or one of the units may be run to verify that the other unit is affected.
The method can optimize and verify the operation condition of the nuclear power plant unit through service logic processing, provides a solid foundation for checking potential design defects of the control system, verifying a DCS (distributed control system) upgrading and transforming scheme of the unit, analyzing events, feeding back experience and the like, realizes comprehensive monitoring, can guide the operation state of the nuclear power plant unit control system in an all-around manner, and meets the requirement of fine control.
A fault verification method utilizing the nuclear power plant double-unit digital instrument control verification system comprises the following steps,
the first step, generating the fault information of the nuclear power plant unit and sending the fault information to the simulation module,
and secondly, responding to the fault information of the nuclear power plant unit, generating operation data by the simulation model according to the fault information, and sending the operation data to the control logic module. The control logic module makes a corresponding control command according to the collected operation data and the control strategy and sends the control command to the simulation module,
and thirdly, responding to the control instruction, the simulation module executes the control instruction to obtain a corresponding processing result, and the processing result is returned to the human-computer interface module through the control logic module. And meanwhile, the operation data is sent to the verification control module.
The first and second units may be run in parallel or one of the units may be run to verify that the other unit is affected.
The method realizes the recurrence of the fault conditions according to the nuclear power fault information, verifies and analyzes the fault conditions, summarizes the fault source, provides powerful basis and direction for perfecting DCS configuration design and DCS maintenance, and reduces the occurrence of the fault conditions.
When the nuclear power plant double-unit digital instrument control verification system has a fault, the control logic module generates DCS fault information, and based on the DCS fault information, the control logic module calculates and analyzes the working condition of the nuclear power plant unit, measures the working condition deviation and corrects DCS configuration logic and parameters.
A computer readable medium that when executed performs the method.
And the graphical user interface comprises the nuclear power plant double-unit digital instrument control verification system.
It will be understood by those skilled in the art that all or part of the processes of the above methods may be implemented by a computer program, which can be stored in a computer-readable storage medium, and when executed, can include the processes of the embodiments of the above methods. The storage medium may be a magnetic disk, an optical disk, a read-only memory or a random access memory.
Industrial applicability
The two-unit digital instrument control verification system and the method for the nuclear power plant can be manufactured and used in the field of nuclear power plants.
The foregoing describes the general principles of the present application in conjunction with specific embodiments, however, it is noted that the advantages, effects, etc. mentioned in the present application are merely examples and are not limiting, and they should not be considered essential to the various embodiments of the present application. Furthermore, the foregoing disclosure of specific details is for the purpose of illustration and description and is not intended to be limiting, since the foregoing disclosure is not intended to be exhaustive or to limit the disclosure to the precise details disclosed.
The foregoing description has been presented for purposes of illustration and description. Furthermore, the description is not intended to limit embodiments of the application to the form disclosed herein. While a number of example aspects and embodiments have been discussed above, those of skill in the art will recognize certain variations, modifications, alterations, additions and sub-combinations thereof.

Claims (10)

1. The nuclear power plant double-unit digital instrument control verification system is characterized in that: comprises a simulation module, a control logic module and a human-computer interface module, wherein,
the simulation module comprises a first simulation model server for simulating a process system of a first unit of the nuclear power plant and a second simulation model server for simulating a process system of a second unit of the nuclear power plant, the simulation module is in communication connection with the control logic module through the data communication server, and the simulation module simulates the operation of the first unit and the second unit of the nuclear power plant and generates operation data based on an operation instruction sent by the human-computer interface module;
the control logic module receives the operation instruction sent by the human-computer interface module and the simulation module, responds to the operation instruction to perform corresponding service logic processing, the service logic processing comprises real-time calculation and analysis of the working conditions of the first unit and the second unit of the nuclear power plant, measurement of the working condition deviation, correction of DCS configuration logic and parameters and generation of nuclear power plant unit operation control instructions based on the corrected DCS configuration logic and parameters,
the control logic module comprises a control logic module and a control logic module,
the DCS one-layer control system comprises a first safety level instrument control system and a first non-safety level instrument control system for operating a first unit control logic configuration of the nuclear power plant and a second safety level instrument control system and a second non-safety level instrument control system for operating a second unit control logic configuration of the nuclear power plant, wherein the first safety level instrument control system and the second safety level instrument control system respectively comprise a 1E level virtual controller for controlling virtual equipment, a 1E channel controller and a first exchange unit for communication, the first non-safety level instrument control system and the second non-safety level instrument control system respectively comprise an NC level virtual controller for controlling the virtual equipment, an NC level control cabinet for controlling the virtual equipment and a second exchange unit for communication, the 1E channel controller and the NC level control cabinet are respectively connected with a data communication server through I/O interface communication,
a first AW interface server and a second AW interface server which are respectively connected with the first switching unit and the second switching unit in a communication way,
a first front-end server and a second front-end server which are respectively connected with the first AW interface server and the second AW interface server in a communication way,
the first HST/ALM/MTK/AW/CSA server and the second HST/ALM/MTK/AW/CSA server comprise a history library, an alarm, a clock, an AW engineer station and a CSA station, and the first HST/ALM/MTK/AW/CSA server and the second HST/ALM/MTK/AW/CSA server are respectively connected with the DCS layer control system, the first AW interface server and the second AW interface server in a communication mode;
the human-computer interface module sends an operation instruction to the control logic module and receives a processing result returned by the control logic module;
the human-machine interface module comprises a human-machine interface module,
the first human-computer interface and the second human-computer interface realize corresponding human-computer interaction operation, send corresponding operation instructions to the first non-safety instrument control system and the second non-safety instrument control system and receive returned processing results,
and the first safety level DCS man-machine interface and the second safety level DCS man-machine interface realize corresponding man-machine interaction operation, send corresponding operation instructions to the first safety level instrument control system and the second safety level instrument control system and receive returned processing results.
2. The nuclear power plant double-unit digital instrument control verification system of claim 1, characterized in that: also comprises a verification control module which sends an operation instruction to the simulation module and receives a processing result returned by the simulation module, the verification control station comprises,
the first verification control station and the second verification control station realize corresponding man-machine interaction operation, an operator executes corresponding operation according to requirements, and the control stations send corresponding operation instructions to the process simulation model and receive corresponding processing results of model dynamics.
3. The nuclear power plant double-unit digital instrument control verification system of claim 2, characterized in that: the verification control module generates nuclear power plant unit fault information and sends the simulation module, the simulation module carries out corresponding service logic processing and generates operation data based on the nuclear power plant unit fault information, the verification control module and the logic control module are fed back, the logic control module formulates a corresponding control regulation strategy according to the change of process parameters in the simulation module and generates a control instruction, the control instruction is sent to the simulation module, the simulation module carries out corresponding service processing and dynamically responds to the operation data in order to generate, and the first unit and the second unit can operate the functions in parallel.
4. The nuclear power plant double-unit digital instrument control verification system of claim 1, characterized in that: when the double-unit digital instrument control verification system of the nuclear power plant breaks down, the control logic module generates DCS fault information, and calculates and analyzes the working conditions of the first unit and the second unit of the nuclear power plant, measures the working condition deviation and corrects DCS configuration logic and parameters based on the DCS fault information.
5. The nuclear power plant double-unit digital instrument control verification system of claim 1, characterized in that: the first switching unit comprises gateway equipment and a switch which is respectively connected with the 1E-level virtual controller and the 1E channel controller, and the second switching unit comprises a switch which is respectively connected with the NC-level virtual controller and the NC-level control cabinet.
6. The nuclear power plant double-unit digital instrument control verification system of claim 1, characterized in that: the process system comprises a simulation model unit for simulating a nuclear island, a conventional island and a BOP part, and the simulation model server comprises a simulator for simulating the process system in a ratio of 1: 1.
7. The nuclear power plant double-unit digital instrument control verification system of claim 1, characterized in that: the DCS layer control system further comprises a Root switch for data interaction, the first switching unit and the second switching unit are respectively provided with the Root switch, and the second switching unit comprises a field communication protocol for communicating field equipment and a virtual communication protocol for communicating virtual equipment.
8. The nuclear power plant double-unit digital instrument control verification system of claim 1, characterized in that: the first-layer DCS control system is in communication connection with the man-machine interface layer through a third exchange unit, and further comprises a first DCS second-layer calculation server, a second DCS second-layer calculation server, a historical data server and a real-time data server, wherein the first DCS second-layer calculation server and the second DCS second-layer calculation server are respectively used for calculating the equipment states of a first unit and a second unit of the nuclear power plant.
9. The nuclear power plant double-unit digital instrument control verification system of claim 1, characterized in that: the human-machine interface module also comprises a human-machine interface module,
a first DGS station and a second DGS station, each communicatively coupled to a non-security instrumented system, the DGS stations configured to generate a control logic configuration offline,
a first listing center and a second listing center configured to lock predetermined equipment of first and second units of the nuclear power plant, respectively.
10. An instrumentation verification method using the two-unit digital instrumentation verification system of the nuclear power plant according to any one of claims 1 to 9, comprising the steps of:
firstly, generating an operation instruction, wherein the operation instruction is sent to a simulation module through a verification control station;
secondly, responding to the operation instruction, adjusting operation data by the simulation module according to the operation instruction, returning the operation data to the control logic module, and performing corresponding service logic processing by the control logic module, wherein the service logic processing comprises real-time calculation and analysis of the working condition of the nuclear power unit based on the operation data, measurement of the working condition deviation, correction of DCS configuration logic and parameters, and generation of a nuclear power unit operation control instruction based on the corrected DCS configuration logic and parameters, wherein the NC-level control cabinet operates and operates field equipment based on the operation instruction, and the 1E-level virtual controller and the NC-level virtual controller virtually operate virtual equipment based on the operation instruction;
thirdly, responding to the control instruction, the simulation module dynamically responds according to the control instruction to obtain a corresponding processing result, the processing result is returned to the human-computer interface layer through the control logic module, and meanwhile, operation data are sent to the verification control module;
the first unit and the second unit can run in parallel, or one of the units can be run to verify whether the other unit is influenced.
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