CN111665818A - Digital instrument control verification system and method for nuclear power plant - Google Patents
Digital instrument control verification system and method for nuclear power plant Download PDFInfo
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- CN111665818A CN111665818A CN202010473837.3A CN202010473837A CN111665818A CN 111665818 A CN111665818 A CN 111665818A CN 202010473837 A CN202010473837 A CN 202010473837A CN 111665818 A CN111665818 A CN 111665818A
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- G05B—CONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
- G05B23/00—Testing or monitoring of control systems or parts thereof
- G05B23/02—Electric testing or monitoring
- G05B23/0205—Electric testing or monitoring by means of a monitoring system capable of detecting and responding to faults
- G05B23/0218—Electric testing or monitoring by means of a monitoring system capable of detecting and responding to faults characterised by the fault detection method dealing with either existing or incipient faults
- G05B23/0243—Electric testing or monitoring by means of a monitoring system capable of detecting and responding to faults characterised by the fault detection method dealing with either existing or incipient faults model based detection method, e.g. first-principles knowledge model
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- G05B—CONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
- G05B2219/00—Program-control systems
- G05B2219/20—Pc systems
- G05B2219/24—Pc safety
- G05B2219/24065—Real time diagnostics
Abstract
The invention relates to the technical field of nuclear power plant control, in particular to a digital instrument control verification system and a digital instrument control verification method for a nuclear power plant. The digital instrument control verification system of the nuclear power plant integrates multiple state monitoring including a DCS control equipment state, a switch state, a virtual controller and a workstation computer state. The invention realizes comprehensive monitoring, can guide the running state of the nuclear power plant unit control system in an all-around way, 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.
Description
Technical Field
The invention relates to the technical field of nuclear power plant control, in particular to a digital instrument control verification system and a digital instrument control verification 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.
Necessity of
At present, common verification systems of nuclear power plants comprise a full-range simulator, a DCS minimum system and a design verification platform. The simulator is mainly used for training a power plant system and operation regulations of operating personnel in the main control room. The DCS minimum system cannot form a control closed loop environment because of no process system simulation model, and a plurality of instrument control functions are simplified minimum configuration, so that the functions of the DCS control system cannot be comprehensively verified. The design verification platform does not aim at a specific DCS system, and verifies the design file of a design institute. Therefore, the existing verification platform cannot verify the functions and performances of the DCS. The invention uses the virtual control station technology and the process simulation model technology to simulate the whole-range DCS control system of the nuclear power plant, the field industrial equipment and the flow network. The unit DCS engineering data is downloaded in the virtual control station, the simulation model runs the reference unit field process equipment and the flow network model to form a control closed-loop environment, and the unit DCS control system can be effectively and comprehensively verified. 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
In view of the above problems, the present invention provides a system and a method for verifying the digital control of a tuberculosis power plant to overcome the above drawbacks of the prior art.
The purpose of the invention is realized by the following technical scheme.
A digital instrument control verification system of a nuclear power plant comprises a simulation model layer, a control logic layer and a human-computer interface layer, wherein,
(1) the simulation model layer is configured to simulate the operation of the nuclear power plant unit and generate operation data based on an operation instruction sent by the human-computer interface layer, and comprises a simulation model server for simulating a process system of the nuclear power plant unit;
(2) a control logic layer configured to receive an operation instruction sent by the human-computer interface layer and access the simulation model layer, 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 condition of the nuclear power plant unit 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 layer including,
the DCS one-layer control system comprises a safety level instrument control system, a non-safety level instrument control system and a third-party instrument control system, wherein the safety level instrument control system runs a nuclear power plant unit control logic configuration, the safety level instrument control system comprises a 1E level virtual controller and a first exchange unit used for communication, the non-safety level instrument control system comprises an NC level virtual controller and a second exchange unit used for communication, the third-party instrument control system comprises a third-party virtual controller and a third exchange unit used for communication,
an AW interface server which is connected with the first switching unit, the second switching unit and the third switching unit in a communication way,
a front-end server in communication connection with the AW interface server,
an HST/ALM/MTK/AW/CSA server configured as a historian, an alarm, a clock, an AW engineer station and a CSA station, the HST/ALM/MTK/AW/CSA server communicatively connecting the DCS layer control system and the AW interface server;
(3) a human-machine interface layer configured to send operation instructions to the control logic layer and receive processing results returned by the control logic layer, the human-machine interface layer comprising,
a human-computer interface configured to implement corresponding human-computer interaction operation, send corresponding operation instructions to the non-security level instrumentation and control system and a third-party instrumentation and control system, and receive returned processing results,
and the safety level DCS human-computer interface is configured to realize corresponding human-computer interaction operation, send a corresponding operation instruction to the safety level instrument control system and receive a returned processing result.
In the nuclear power plant digital instrument control verification system, the nuclear power plant digital instrument control verification system further comprises a verification control layer which is configured to generate nuclear power plant unit fault information and send the control logic layer, the control logic layer carries out corresponding service logic processing based on the nuclear power plant unit fault information and generates a control instruction, and the simulation model layer simulates the operation of the nuclear power plant unit based on the control instruction and generates operation data to feed back the verification control layer.
In the nuclear power plant digital instrument control verification system, when the nuclear power plant digital instrument control verification system breaks down, a control logic layer generates DCS fault information, and based on the DCS fault information, the working condition of a nuclear power plant unit is calculated and analyzed, working condition deviation is measured, and DCS configuration logic and parameters are corrected.
In the nuclear power plant digital instrument control verification system, the nuclear power plant digital instrument control verification system further comprises a data communication server for data interaction between the simulation model layer and the control logic layer.
In the digital instrument control verification system for the nuclear power plant, a process system comprises a simulation model unit for simulating a nuclear island, a conventional island and a BOP part, a simulation model server comprises a simulator for simulating the process system in a 1:1 mode, and a first exchange unit comprises an exchanger and gateway equipment.
In the nuclear power plant digital instrument control verification system, the DCS layer control system further comprises an ROO switch for data interaction, and the first switching unit, the second switching unit and the third switching unit respectively comprise a Room switch.
In the nuclear power plant digital instrument control verification system, the first-layer DCS control system is in communication connection with the man-machine interface layer through a fourth exchange unit, and further comprises a second-layer DCS calculation server, a historical data server and a real-time data server, wherein the second-layer DCS calculation server is used for calculating the equipment state of a nuclear power plant unit.
In the digital instrument control verification system of the nuclear power plant, the human-computer interface layer also comprises,
a DGS station communicatively coupled to a non-security instrumentation control system, the DGS station configured to generate a control logic configuration offline,
a listing center configured to lock predetermined equipment of the nuclear power plant unit.
According to another aspect of the invention, an instrumentation verification method using the nuclear power plant digitizer instrumentation verification system comprises the following steps,
the first step, generating an operation instruction, wherein the operation instruction is sent to a security level instrumentation and control system through a security level DCS human-computer interface, and is sent to a non-security level instrumentation and control system and a third party instrumentation and control system through a human-computer interface,
a second step of responding to the operation instruction, controlling a logic layer to perform corresponding service logic processing, 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,
and a third step, responding to the control instruction, the simulation model layer executes the control instruction to obtain a corresponding processing result, and the processing result is returned to the human-computer interface layer through the control logic layer.
According to still another aspect of the invention, a fault verification method using the nuclear power plant digital instrumentation verification system comprises the following steps,
the first step, generating the fault information of the nuclear power plant unit and sending the control logic layer,
a second step, responding the fault information of the nuclear power plant unit, carrying out corresponding service logic processing by a control logic layer to generate a control instruction,
a third step, responding to the control instruction, the simulation model layer executes the control instruction to obtain a corresponding processing result, and the processing result is returned to the verification control layer through the control logic layer
Compared with the prior art, the invention has the beneficial effects that:
the nuclear power plant digital instrument control verification system simulates the operation of a nuclear power plant unit through a simulation model layer and generates operation data, the simulation model layer can simulate a large number of signal change states of a nuclear power plant site and is matched with a DCS (distributed control System) to carry out various tests, a control logic layer responds to an operation instruction to carry out corresponding service logic processing, the DCS is provided with a safety instrument control system, a non-safety instrument control system and a third-party instrument control system which operate the nuclear power plant unit control logic configuration respectively at one layer, so that the safety of the nuclear power plant digital instrument control verification system is obviously improved, the nuclear power plant digital instrument control verification system is used as a pre-implementation platform before the nuclear power plant instrument control reconstruction and upgrading to verify the feasibility of an implementation scheme, the possibility of non-stop caused by insufficient scheme argument is reduced, the past non-stop events can be reappeared and analyzed and simultaneously used as experience feedback to carry out item-by item troubleshooting on, the test and verification are carried out on the platform, the maintenance efficiency of the instrument control system is improved, an operation platform for skill training is provided for DCS operation and maintenance personnel of the nuclear power plant, and professional talents in the DCS operation and maintenance field are cultivated. 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 digital instrument control verification system of the nuclear power plant 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 a 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.
Drawings
FIG. 1 is a schematic diagram of a nuclear power plant digitizer verification system according to one embodiment of the present invention;
FIG. 2 is a schematic illustration of the steps of a tool verification method according to one embodiment of the present disclosure.
FIG. 3 is a schematic diagram of the steps of a fault verification method according to one embodiment of the invention.
FIG. 4 is a schematic diagram of a software architecture
FIG. 5 is a schematic diagram of software hierarchy
FIG. 6 is a schematic diagram of signal transmission relationship
Detailed Description
Specific embodiments of the present invention will be described in more detail below with reference to the accompanying drawings. While specific embodiments of the invention are shown in the drawings, it should be understood that the invention may be embodied in various forms and should not be construed as limited to the embodiments set forth herein. Rather, these embodiments are provided so that this disclosure will be thorough and complete, and will fully convey the scope of the invention to those skilled in the art.
It should be noted that 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.
For the purpose of facilitating understanding of the embodiments of the present invention, the following description will be made by taking specific embodiments as examples with reference to the accompanying drawings, and the drawings are not to be construed as limiting the embodiments of the present invention.
For better understanding, fig. 1 is a schematic structural diagram of a nuclear power plant digital control verification system according to an embodiment of the present invention, which includes an emulation model layer, a control logic layer, and a human-machine interface layer, wherein,
the simulation model layer is configured to simulate the operation of the nuclear power plant unit and generate operation data based on an operation instruction sent by the human-computer interface layer, and comprises a simulation model server for simulating a process system of the nuclear power plant unit;
a control logic layer configured to receive an operation instruction sent by the human-computer interface layer and access the simulation model layer, 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 condition of the nuclear power plant unit 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 layer including,
the DCS one-layer control system comprises a safety level instrument control system, a non-safety level instrument control system and a third-party instrument control system, wherein the safety level instrument control system runs a nuclear power plant unit control logic configuration, the safety level instrument control system comprises a 1E level virtual controller and a first exchange unit used for communication, the non-safety level instrument control system comprises an NC level virtual controller and a second exchange unit used for communication, the third-party instrument control system comprises a third-party virtual controller and a third exchange unit used for communication,
an AW interface server which is connected with the first switching unit, the second switching unit and the third switching unit in a communication way,
a front-end server in communication connection with the AW interface server,
an HST/ALM/MTK/AW/CSA server configured as a historian, an alarm, a clock, an AW engineer station and a CSA station, the HST/ALM/MTK/AW/CSA server communicatively connecting the DCS layer control system and the AW interface server;
a human-machine interface layer configured to send operation instructions to the control logic layer and receive processing results returned by the control logic layer, the human-machine interface layer comprising,
a human-computer interface configured to implement corresponding human-computer interaction operation, send corresponding operation instructions to the non-security level instrumentation and control system and a third-party instrumentation and control system, and receive returned processing results,
and the safety level DCS human-computer interface is configured to realize corresponding human-computer interaction operation, send a corresponding operation instruction to the safety level instrument control system and receive a returned processing result.
In one embodiment, the simulation model layer of the nuclear power plant digital instrument control verification system can simulate various operation conditions of a nuclear power plant to be operated and simulate the fault mode of nuclear power plant equipment. The simulation model layer can receive a control instruction sent by the DCS control logic layer, 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 nuclear power plant digital instrumentation verification system, the nuclear power plant digital instrumentation verification system further includes a verification control layer configured to generate nuclear power plant unit fault information and send the control logic layer, the control logic layer performs corresponding service logic processing based on the nuclear power plant unit fault information to generate a control instruction, and the simulation model layer simulates operation of the nuclear power plant unit based on the control instruction and generates operation data to feed back the verification control layer.
In one embodiment of the nuclear power plant digital instrument control verification system, when the nuclear power plant digital instrument control verification system has a fault, the control logic layer generates DCS fault information, and based on the DCS fault information, the working condition of a nuclear power plant unit is calculated and analyzed, the working condition deviation is measured, and DCS configuration logic and parameters are corrected.
In an embodiment of the nuclear power plant digital instrumentation verification system, the nuclear power plant digital instrumentation verification system further includes a data communication server for data interaction between the simulation model layer and the control logic layer.
In one embodiment of the nuclear power plant digital instrumentation verification system, the process system comprises a simulation model unit for simulating a nuclear island, a conventional island and a BOP part, the simulation model server comprises a simulator for simulating the process system in a 1:1 mode, and the first switching unit comprises a switch and a gateway device.
In an embodiment of the nuclear power plant digitizer control verification system, the DCS layer control system further includes an ROO switch for data interaction, and the first switching unit, the second switching unit, and the third switching unit respectively include a Room switch.
In an embodiment of the nuclear power plant digital instrument control verification system, the first-layer DCS control system is in communication connection with the human-computer interface layer through a fourth exchange unit, and further comprises a second-layer DCS calculation server, a historical data server and a real-time data server, wherein the second-layer DCS calculation server is used for calculating the equipment state of a nuclear power plant unit.
In an embodiment of the nuclear power plant digitizer control verification system, the control logic layer is a nuclear power plant DCS control logic layer, and includes a non-security level, a security level, and a third-party control logic. The third-party control logic is realized in an analog simulation mode, the control logic layer can receive an operation instruction of the DCS human-computer interface layer, the instruction is sent to the simulation model layer after logic operation is carried out, the equipment feedback state of the model is received, and the feedback state is fed back to the DCS human-computer interface layer to be displayed after the logic operation.
In an embodiment of the nuclear power plant digital instrument control verification system, the human-machine interface layer further includes,
a DGS station communicatively coupled to a non-security instrumentation control system, the DGS station configured to generate a control logic configuration offline,
a listing center configured to lock predetermined equipment of the nuclear power plant unit.
In an embodiment of the nuclear power plant digital instrument control verification system, a nuclear power plant DCS human-computer interface comprises a non-safety level, a safety level and a third-party instrument control system human-computer interface, the safety level and the third-party instrument control system human-computer interface are 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 layer is mainly responsible for the operation of the nuclear power plant equipment and displays the feedback state of the equipment.
In an embodiment of the nuclear power plant digital instrument control verification system, as shown in fig. 1, the simulation model layer takes a nuclear power plant reference unit as a simulation object, and a process system of the 1:1 simulation reference unit comprises a verification control function.
In an embodiment of the nuclear power plant digital instrumentation verification system, the simulation model server is a Unit1 simulation model server, which runs a nuclear power plant process system simulation model program.
In an embodiment of the nuclear power plant digital instrument control verification system, 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 one embodiment of the nuclear power plant digital instrument control verification system, a first-level DCS control system runs a power plant control logic configuration, wherein the first-level DCS control system comprises a non-safety level, a safety level and a third-party instrument control system, and the control of the scale of the power plant in a 1:1 mode is realized.
In one embodiment of the nuclear power plant digital instrument control verification system, a safety level, a non-safety level and a third-party instrument control system of a control logic layer all adopt virtual machine control systems, and control logic is downloaded from a field unit.
In one embodiment of the nuclear power plant digital control verification system, an AW interface server is a DCS1 layer communication server; 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 nuclear power plant digital instrument control verification system, a process system model part comprises a nuclear island, a conventional island and a BOP part, and a full-range simulator is used for simulating range and precision reference.
In an embodiment of the digital instrumentation verification system for the nuclear power plant, the human-computer interface includes an operating unit main control room control interface OWP, TAGGING, DGS, SVDU, an instrumentation operation and maintenance support system, and the like.
In an embodiment of the nuclear power plant digital control verification system, the nuclear power plant digital control verification system is networked through an industrial ethernet.
As shown in fig. 2, an instrumentation verification method using the nuclear power plant digitizer instrumentation verification system includes the following steps,
the first step, generating an operation instruction, wherein the operation instruction is sent to a security level instrumentation and control system through a security level DCS human-computer interface, and is sent to a non-security level instrumentation and control system and a third party instrumentation and control system through a human-computer interface,
a second step of responding to the operation instruction, controlling a logic layer to perform corresponding service logic processing, 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,
and a third step, responding to the control instruction, the simulation model layer executes the control instruction to obtain a corresponding processing result, and the processing result is returned to the human-computer interface layer through the control logic layer.
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.
As shown in fig. 3, a fault verification method using the nuclear power plant digitizer control verification system includes the following steps,
the method comprises the first step of generating fault information, wherein the safety level fault information is generated by a safety level DCS (distributed control system) man-machine interface and is sent to a safety level instrument control system. The non-safety level fault information is generated by a non-safety level DCS human-computer interface and is sent to a non-safety level instrument control system and a third party instrument control system,
the second step, responding the fault information of the nuclear power plant unit, judging the fault type and identifying the fault level by the instrument control system according to the received fault information, analyzing the relevant equipment and the influence degree related to the fault, carrying out program logic operation through the logic relation of the process equipment and the equipment control principle, finally generating a control instruction of the process equipment, and sending the control instruction to the process simulation model layer through the communication interface,
and thirdly, responding to the control command, wherein the process simulation model layer dynamically responds to the command according to the operation command of the instrument control system and the characteristics of process equipment and a flow network. And meanwhile, returning the process operation response information to the instrument control system to form a control closed loop. And the response information is returned to the human-computer interface layer by the instrument control system.
The method realizes the recurrence of the fault condition according to the fault information of the nuclear power plant, verifies and analyzes the fault condition, summarizes the fault source, provides powerful basis and direction for perfecting DCS configuration design and DCS maintenance, and reduces the occurrence of the fault condition.
When the nuclear power plant digital instrument control verification system has a fault, the control logic layer generates DCS fault information, and calculates and analyzes the working condition of the nuclear power plant unit, measures the working condition deviation and corrects DCS configuration logic and parameters based on the DCS fault information.
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 methods. The storage medium may be a magnetic disk, an optical disk, a read-only memory or a random access memory.
Industrial applicability
The digital instrument control verification system and 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 utility model provides a digital instrument of nuclear power plant accuse verification system which characterized in that: comprises a simulation model layer, a control logic layer and a man-machine interface layer, wherein,
(1) the simulation model layer is configured to simulate the operation of the nuclear power plant unit and generate operation data based on an operation instruction sent by the human-computer interface layer, and comprises a simulation model server for simulating a process system of the nuclear power plant unit;
(2) a control logic layer configured to receive an operation instruction sent by the human-computer interface layer and access the simulation model layer, 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 condition of the nuclear power plant unit 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 layer including,
the DCS one-layer control system comprises a safety level instrument control system, a non-safety level instrument control system and a third-party instrument control system, wherein the safety level instrument control system runs a nuclear power plant unit control logic configuration, the safety level instrument control system comprises a 1E level virtual controller and a first exchange unit used for communication, the non-safety level instrument control system comprises an NC level virtual controller and a second exchange unit used for communication, the third-party instrument control system comprises a third-party virtual controller and a third exchange unit used for communication,
an AW interface server which is connected with the first switching unit, the second switching unit and the third switching unit in a communication way,
a front-end server in communication connection with the AW interface server,
an HST/ALM/MTK/AW/CSA server configured as a historian, an alarm, a clock, an AW engineer station and a CSA station, the HST/ALM/MTK/AW/CSA server communicatively connecting the DCS layer control system and the AW interface server;
(3) a human-machine interface layer configured to send operation instructions to the control logic layer and receive processing results returned by the control logic layer, the human-machine interface layer comprising,
a human-computer interface configured to implement corresponding human-computer interaction operation, send corresponding operation instructions to the non-security level instrumentation and control system and a third-party instrumentation and control system, and receive returned processing results,
and the safety level DCS human-computer interface is configured to realize corresponding human-computer interaction operation, send a corresponding operation instruction to the safety level instrument control system and receive a returned processing result.
2. The nuclear power plant digital instrumentation verification system of claim 1, wherein: the nuclear power plant digital instrument control verification system further comprises a verification control layer which is configured to generate nuclear power plant unit fault information and send the control logic layer, the control logic layer carries out corresponding service logic processing based on the nuclear power plant unit fault information and generates a control instruction, and the simulation model layer simulates the operation of the nuclear power plant unit based on the control instruction and generates operation data to feed back the verification control layer.
3. The nuclear power plant digital instrumentation verification system of claim 1, wherein: when the nuclear power plant digital instrument control verification system has a fault, the control logic layer generates DCS fault information, and based on the DCS fault information, the working condition of the nuclear power plant unit is calculated and analyzed, working condition deviation is measured, and DCS configuration logic and parameters are corrected.
4. The nuclear power plant digital instrumentation verification system of claim 1, wherein: the nuclear power plant digital instrument control verification system further comprises a data communication server used for data interaction between the simulation model layer and the control logic layer.
5. The nuclear power plant digital instrumentation verification system of claim 1, wherein: the process system comprises a simulation model unit for simulating the nuclear island, the conventional island and the BOP part, the simulation model server comprises a simulator for simulating the process system in a ratio of 1:1, and the first switching unit comprises a switch and gateway equipment.
6. The nuclear power plant digital instrumentation verification system of claim 1, wherein: the DCS layer control system further comprises an ROO switch used for data interaction, and the first switching unit, the second switching unit and the third switching unit respectively comprise a Room switch.
7. The nuclear power plant digital instrumentation verification system of claim 1, wherein: the first-level DCS control system is in communication connection with the man-machine interface layer through a fourth exchange unit, and further comprises a second-level DCS calculation server, a historical data server and a real-time data server, wherein the second-level DCS calculation server is used for calculating the equipment state of the nuclear power plant unit.
8. The nuclear power plant digital instrumentation verification system of claim 7, wherein: the man-machine interface layer also comprises a DGS station and a listing center, wherein the DGS station is in communication connection with a non-safety instrument control system and is configured to generate a control logic configuration under an offline condition;
a listing center configured to lock predetermined equipment of the nuclear power plant unit.
9. An instrumentation verification method using the nuclear power plant digital instrumentation verification system according to any one of claims 1 to 8, characterized in that: comprises the following steps of (a) carrying out,
the first step, generating an operation instruction, wherein the operation instruction is sent to a security level instrumentation and control system through a security level DCS human-computer interface, and is sent to a non-security level instrumentation and control system and a third party instrumentation and control system through a human-computer interface,
a second step of responding to the operation instruction, controlling a logic layer to perform corresponding service logic processing, 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,
and a third step, responding to the control instruction, the simulation model layer executes the control instruction to obtain a corresponding processing result, and the processing result is returned to the human-computer interface layer through the control logic layer.
10. A fault verification method applying the nuclear power plant digital instrument control verification system of any one of claims 1-8, characterized in that: comprises the following steps of (a) carrying out,
the first step, generating the fault information of the nuclear power plant unit and sending the control logic layer,
a second step, responding the fault information of the nuclear power plant unit, carrying out corresponding service logic processing by a control logic layer to generate a control instruction,
and a third step, responding to the control instruction, the simulation model layer executes the control instruction to obtain a corresponding processing result, and the processing result is returned to the verification control layer through the control logic layer.
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