CN110618661A - Design process and configuration system of nuclear power plant safety level DCS equipment identification prototype - Google Patents
Design process and configuration system of nuclear power plant safety level DCS equipment identification prototype Download PDFInfo
- Publication number
- CN110618661A CN110618661A CN201910797548.6A CN201910797548A CN110618661A CN 110618661 A CN110618661 A CN 110618661A CN 201910797548 A CN201910797548 A CN 201910797548A CN 110618661 A CN110618661 A CN 110618661A
- Authority
- CN
- China
- Prior art keywords
- function
- prototype
- level dcs
- configuration
- hardware
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000012938 design process Methods 0.000 title claims abstract description 21
- 230000006870 function Effects 0.000 claims abstract description 218
- 238000010586 diagram Methods 0.000 claims abstract description 36
- 238000013461 design Methods 0.000 claims abstract description 35
- 238000004891 communication Methods 0.000 claims description 40
- 238000012545 processing Methods 0.000 claims description 17
- 238000013095 identification testing Methods 0.000 claims description 14
- 230000008054 signal transmission Effects 0.000 claims description 7
- 238000012905 input function Methods 0.000 claims description 6
- 230000003068 static effect Effects 0.000 claims description 6
- 230000000694 effects Effects 0.000 abstract description 7
- 238000000034 method Methods 0.000 description 12
- 230000008569 process Effects 0.000 description 8
- 238000012360 testing method Methods 0.000 description 4
- 238000004458 analytical method Methods 0.000 description 3
- 230000008520 organization Effects 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 238000011156 evaluation Methods 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000012544 monitoring process Methods 0.000 description 2
- 238000012795 verification Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000009795 derivation Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000001537 neural effect Effects 0.000 description 1
- 238000012797 qualification Methods 0.000 description 1
- 231100000279 safety data Toxicity 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G05—CONTROLLING; REGULATING
- G05B—CONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
- G05B19/00—Programme-control systems
- G05B19/02—Programme-control systems electric
- G05B19/418—Total factory control, i.e. centrally controlling a plurality of machines, e.g. direct or distributed numerical control [DNC], flexible manufacturing systems [FMS], integrated manufacturing systems [IMS] or computer integrated manufacturing [CIM]
- G05B19/41845—Total factory control, i.e. centrally controlling a plurality of machines, e.g. direct or distributed numerical control [DNC], flexible manufacturing systems [FMS], integrated manufacturing systems [IMS] or computer integrated manufacturing [CIM] characterised by system universality, reconfigurability, modularity
-
- G—PHYSICS
- G05—CONTROLLING; REGULATING
- 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
- G05B2219/30—Nc systems
- G05B2219/33—Director till display
- G05B2219/33273—DCS distributed, decentralised controlsystem, multiprocessor
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P90/00—Enabling technologies with a potential contribution to greenhouse gas [GHG] emissions mitigation
- Y02P90/02—Total factory control, e.g. smart factories, flexible manufacturing systems [FMS] or integrated manufacturing systems [IMS]
Landscapes
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Manufacturing & Machinery (AREA)
- Quality & Reliability (AREA)
- Physics & Mathematics (AREA)
- General Physics & Mathematics (AREA)
- Automation & Control Theory (AREA)
- Testing And Monitoring For Control Systems (AREA)
Abstract
The invention provides a design process and a configuration system of a nuclear power plant safety level DCS equipment identification prototype, which comprises the following steps: determining all basic functions of the security level DCS equipment according to the security level DCS equipment identification object to be identified; constructing a minimum system architecture diagram enveloping all basic functions according to all the determined basic functions; and carrying out corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype. The invention realizes the technical effects of improving the design efficiency of the safety-level DCS equipment identification prototype and reducing the cost of the input of related identification activities.
Description
Technical Field
The invention belongs to the field of a nuclear power plant safety level digital control system, and particularly relates to a design process and a configuration system of a nuclear power plant safety level DCS equipment identification prototype.
Background
The description of class 1E equipment authentication purposes by IEEE std.323 illustrates a general principle of authentication prototype representativeness, i.e. the proof that the equipment used in the actual engineering can normally perform its designed safety function under the assumed working conditions by using the prototype authentication. Furthermore, in IEEE std.323, it is clearly required that the test prototype should represent the actual device in terms of design, material, and manufacturing process. IEEE Std.7-4.3.2 made clearer demands on the representativeness of the authentication prototypes, namely: all system components of a digital computer system for performing security functions and other equipment components that may affect the operation of the security functions during operational or fault conditions are subject to qualification testing, which mainly includes testing and monitoring memory, CPU, input/output components, display functions, diagnostic functions, other related components, communication paths and interfaces, etc. Equipment authentication for instrumentation and control equipment in nuclear power plants, it is common to target hardware and software equipment that performs nuclear safety functions. The DCS system, called the "neural center" of nuclear power plants, and particularly the related devices of the safety-level DCS system, which undertakes important functions such as reactor shutdown protection, dedicated protection, etc., must be subjected to strict identification before being put into engineering use. The safety, reliability and usability of the system are determined mainly through verification of basic performance and functions of the system under the specific environment of artificial manufacturing, so that the capability of the system for executing safety functions under the condition that normal working conditions of the nuclear power plant comprise design benchmark events and the like can be maintained, and possible equipment common cause faults are reduced to the maximum extent.
In the process of identifying the safety-level DCS equipment, whether the adopted prototype can represent the equipment used in the actual engineering or not directly influences the effectiveness of the equipment identification result. According to the requirements of relevant standards, part of the identification tests have certain destructiveness, and the identification activities require a certain period of time, so that for the design of a prototype, factors such as cost and engineering progress are combined to consider to select representative hardware components and application software, and the representativeness of the prototype is mainly considered from the representativeness of hardware and software functions to determine an identification prototype with the minimum size configuration.
In the prior art, as the relevant domestic and foreign standards do not make specific requirements on the configuration of a security level DCS equipment identification prototype, manufacturers generally consider 'big and full' when configuring the identification prototype in order to ensure that the enveloping performance (representativeness) of the equipment identification prototype is sufficient, for example, all types, even modules with the same type and different physical parameter settings (such as the channel number of IO modules, the range setting and the like) are included in hardware; on the other hand, in the engineering application software configuration of a prototype, manufacturers consider that the safety level protection function under different working conditions is included as much as possible.
The prior art has the following defects: the configuration scale of a safety-level DCS equipment identification prototype is too complex, and meanwhile, the equipment identification period is too long, and the cost is increased.
Therefore, in order to solve the technical problems that the configuration scale of a safety-level DCS equipment identification prototype is too complex, the equipment identification period is too long, and the cost is increased in the prior art, a design flow and a configuration system of the safety-level DCS equipment identification prototype of the nuclear power plant are urgently needed.
Disclosure of Invention
The invention provides a design process of a safety-level DCS equipment identification prototype of a nuclear power plant, aiming at the technical problems that the configuration scale of the safety-level DCS equipment identification prototype is too complex, the equipment identification period is too long and the cost is increased in the prior art, and the design process comprises the following steps: determining all basic functions of the security level DCS equipment according to the security level DCS equipment identification object to be identified; constructing a minimum system architecture diagram enveloping all basic functions according to all the determined basic functions; and carrying out corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype.
In the design process of the nuclear power plant safety level DCS equipment identification prototype, the design process further comprises the following steps: and selecting an identification test item and formulating a judgment criterion of the identification test according to the corresponding standard and the technical specification of the platform system.
In the design process of the nuclear power plant safety-level DCS equipment identification prototype, the step of determining all basic functions of the safety-level DCS equipment according to the safety-level DCS equipment identification object to be identified comprises the following steps: the system comprises a ring network communication function, a point-to-point communication function, a subsystem communication function, an analog signal input/output function, a digital signal input/output function, a static display function, a touch screen signal input function, a control logic processing function and a display data generating function.
In the design process of the nuclear power plant safety level DCS equipment identification prototype, the step of performing corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype comprises the following steps: the established minimum system architecture diagram is subjected to hardware configuration, the name and the model of the hardware are listed in a table form, and the name and the model are compared with the hardware in actual engineering application to ensure the effectiveness of the hardware; and carrying out software configuration on the constructed minimum system architecture diagram, wherein the configured software functions are used for realizing all basic functions of the safety-level DCS equipment.
In the design process of the nuclear power plant safety level DCS equipment identification prototype, the configured software functions comprise: analog quantity signal input and output processing logic function, digital quantity signal input and output logic function, signal transmission logic function among different CPUs and control and display logic function of the touch screen.
On the other hand, the invention also provides a configuration system of the nuclear power plant safety level DCS equipment identification prototype, which comprises the following steps: the function judging module is used for determining all basic functions of the security level DCS equipment according to the security level DCS equipment identification object to be identified; the design module is connected with the function judgment module and used for constructing a minimum system architecture diagram enveloping all the basic functions according to all the determined basic functions; and the configuration module is connected with the design module and is used for carrying out corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype.
In the configuration system of the nuclear power plant safety level DCS equipment identification prototype of the present invention, the system further includes: and the standard establishing module is connected with the configuration module and used for selecting an identification test item for the designed equipment identification prototype and formulating a judgment criterion of the identification test according to the corresponding standard and the technical specification of the platform system.
In the configuration system of the nuclear power plant safety level DCS equipment identification prototype, all the basic functions in the function judgment module include: the system comprises a ring network communication function, a point-to-point communication function, a subsystem communication function, an analog signal input/output function, a digital signal input/output function, a static display function, a touch screen signal input function, a control logic processing function and a display data generating function.
In the configuration system of the nuclear power plant safety level DCS equipment identification prototype, the configuration module comprises: the hardware configuration module is connected with the design module and used for performing hardware configuration on the constructed minimum system architecture diagram, listing the name and the model of the hardware in a table form, and comparing the name and the model with the hardware in actual engineering application to ensure the effectiveness of the hardware; and the software configuration module is connected with the design module and used for performing software configuration on the constructed minimum system architecture diagram, and the configured software functions are used for realizing all the basic functions in the function judgment module.
In the configuration system of the nuclear power plant safety level DCS equipment identification prototype, the software functions of the configuration comprise: analog quantity signal input and output processing logic function, digital quantity signal input and output logic function, signal transmission logic function among different CPUs and control and display logic function of the touch screen.
The technical scheme provided by the invention has the beneficial effects that: the invention provides a design process and a configuration system of a nuclear power plant safety-level DCS equipment identification prototype, aiming at the technical problems of too complicated configuration scale of the safety-level DCS equipment identification prototype, too long equipment identification period and increased cost in the prior art, and the design process and the configuration system configure hardware and software to ensure that the prototype used for safety-level DCS equipment identification can completely and correctly represent equipment used in actual engineering, have direct guiding significance for the design of the prototype in the nuclear power plant safety-level DCS equipment identification, and the equipment identification prototype designed by the typical analysis method can improve the efficiency of the design of the safety-level DCS equipment identification prototype and reduce the cost of related identification activities.
Drawings
Fig. 1 is a flow chart of a design process of a nuclear power plant safety level DCS device authentication prototype according to an embodiment of the present invention;
FIG. 2 is a schematic diagram of all basic functions of a security level DCS provided by the first embodiment of the present invention;
FIG. 3 is a diagram illustrating a minimum system architecture that encapsulates all basic functions provided by an embodiment of the present invention;
FIG. 4 is a flowchart of a step S3 according to a first embodiment of the present invention;
FIG. 5 is a diagram illustrating a hardware configuration according to an embodiment of the present invention;
FIG. 6 is a diagram of a software configuration according to an embodiment of the present invention;
fig. 7 is a functional module schematic diagram of a configuration system of a nuclear power plant safety level DCS device authentication prototype according to a second embodiment of the present invention.
Detailed Description
In order to solve the technical problems that the configuration scale of a safety-level DCS equipment identification prototype is too complex, the equipment identification period is too long and the cost is increased in the prior art, the invention aims to provide a design flow and a configuration system of the safety-level DCS equipment identification prototype of a nuclear power plant, and the core idea is as follows: the hardware and the software are configured, so that a prototype used for safety-level DCS equipment identification can completely and correctly represent equipment used in actual engineering, the design of the prototype in the safety-level DCS equipment identification of the nuclear power plant is directly guided, the efficiency of designing the safety-level DCS equipment identification prototype is improved by the aid of the prototype for equipment identification designed by the typical analysis method, and meanwhile, the cost of related identification activities is reduced.
In order to make the objects, technical solutions and advantages of the present invention more apparent, embodiments of the present invention will be described in detail with reference to the accompanying drawings.
Example one
The embodiment of the invention provides a design flow of a nuclear power plant safety level DCS equipment identification prototype, as shown in figure 1, the design flow comprises the following steps:
step S1, determining all basic functions of the security level DCS equipment according to the security level DCS equipment authentication object to be authenticated; the safety-level DCS is designed for executing nuclear safety related control functions, including reactor shutdown protection, special safety protection, waste heat derivation, reactor core temperature monitoring and the like. The basic functions of a safety-level DCS platform are analyzed and determined by combining with the overall technical scheme of an actual nuclear power plant engineering DCS project, and the equipment identification prototype can be ensured to normally execute all designed functions of the equipment used in the actual project under the assumed working condition;
step S2, constructing a minimum system architecture diagram enveloping all basic functions according to all the determined basic functions; the scale of the equipment identification prototype is simplified while the prototype used for safety-level DCS equipment identification is ensured to completely and correctly represent the equipment used in actual engineering, so that the equipment identification period and the equipment cost are reduced;
and step S3, carrying out corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype. And (3) performing hardware and software configuration on the constructed minimum system framework, so that the designed identification prototype is more suitable for practical engineering application, and the effectiveness of the identification prototype is ensured.
Further, after the design of the equipment identification prototype is completed, the method further comprises the following steps: and S4, selecting an identification test item and making a judgment criterion of the identification test according to the corresponding standard and the technical specification of the platform system. The evaluation result of the equipment identification prototype can be evaluated by establishing a judgment criterion, so that the usability and the effectiveness of the basic functions of the platform in the identification process can be checked.
Specifically, as shown in fig. 2, all the basic functions in step S1 include: function 1: ring network communication function, function 2: point-to-point communication function, function 3: subsystem communication function, function 4: analog signal input/output function, function 5: digital signal input/output function, function 6: static display function, function 7: touch screen signal input function, function 8: control logic processing function and function 9: a display data function is generated. Specifically, the security level DCS includes the following devices: the reactor protection (system level) control cabinet comprises a reactor protection (system level) control cabinet, a special safety (system level) control cabinet, a safety logic (equipment level) control cabinet, a reactor core cooling control cabinet, other safety related function control cabinets and a safety data operation and display cabinet, wherein the reactor protection (system level) control cabinet comprises a function 1, a function 2, a function 3, a function 4, a function 5 and a function 8; the special safety (system level) control cabinet comprises a function 1, a function 2, a function 3, a function 5 and a function 8; the safety logic (device level) control cabinet comprises function 1, function 3, function 5 and function 8; the reactor core cooling control cabinet comprises a function 1, a function 2, a function 3, a function 4, a function 5 and a function 8; the other safety-related function control cabinets comprise a function 1, a function 3, a function 4, a function 5 and a function 8; the secure data operation includes function 1, function 6, function 7, and function 9.
Further, as shown in fig. 3, the minimal system architecture diagram enveloping all basic functions includes: the data processing equipment cabinet comprises a display and operation data processing cabinet, a communication ring network, a security level control cabinet #1 and a security level control cabinet #2, wherein the display and operation data processing cabinet can realize a function 1, a function 6, a function 7 and a function 9, the security level control cabinet #1 can communicate with the security level control cabinet #2 through the function 2, and the security level control cabinet #2 can realize a function 1, a function 3, a function 4, a function 5 and a function 8. Specifically, the method comprises the following steps: the display and operation data processing cabinet comprises a ring network communication interface unit which is communicated with a communication ring network, a touch screen data communication interface unit which is connected with the ring network communication interface, a CPU clamping piece-A, a display data communication interface unit which is connected with the CPU clamping piece-A, and a touch screen which is connected with the touch screen data communication interface unit and the display data communication interface unit and is used for displaying data and providing information for operators to obtain, wherein the CPU clamping piece-A comprises a CPU operation unit and a storage unit, and the storage unit comprises a FROM, a ROM and an RAM. The safety level control cabinet #2 comprises a ring network communication interface unit which is communicated with a communication ring network, a control layer communication interface unit which is connected with the ring network communication interface, a CPU clamping piece-A, a control layer communication interface unit which is connected with the CPU clamping piece-A, two parallel-connected input and output clamping pieces which are connected with the control layer communication interface unit, a control layer communication interface unit which is connected with the two input and output clamping pieces, a subsystem communication unit which is connected with the CPU clamping piece-A, and a CPU clamping piece-B which is connected with the subsystem communication unit, wherein the CPU clamping piece-B is connected with the control layer communication interface unit, the CPU clamping piece-A comprises a CPU operation unit and a storage unit, and the storage unit comprises a FROM, a ROM and an RAM. The safety level control cabinet #1 is in communication connection with a control layer communication interface unit in the safety shell control cabinet # 2.
Further, as shown in fig. 4, step S3 includes:
step S31, configuring hardware for the constructed minimum system architecture diagram, listing the name and model of the hardware in a table form, and comparing the name and model with the hardware in actual engineering application to ensure the validity of the hardware; the names and the models of the hardware are listed in a tabular form, so that the hardware is convenient for operators to observe and compare, the configuration process is stored and recorded, the organization is clearer, the achievement is more persuasive, and the relevant examination work of a nuclear safety supervision department can be more effectively matched.
And step S32, performing software configuration on the constructed minimum system architecture diagram, wherein the configured software functions are used for realizing all basic functions in the step S1, so that a prototype used for safety-level DCS equipment authentication can completely and correctly represent equipment used in actual engineering.
Further, as shown in fig. 5, the configured hardware is listed in the table, and it can be seen that: the components in practical engineering applications include: the rack, the control unit are relevant, the input and output unit, the communication unit, the power supply equipment, the auxiliary electric component and other hardware corresponding to the components are as follows: the device comprises a CPU frame, a CPU card, a digital quantity output card, a photoelectric conversion card, a power supply card, a relay and a circuit breaker, wherein the hardware model and version of the equipment identification prototype and the hardware model and version used in actual engineering are compared, the difference is remarked, the representativeness of the equipment identification prototype can be ensured through comparison, and what needs to be explained is that: instead of identifying that the hardware model and version of the prototype configuration and the hardware model and version used by the actual project are exactly the same enough to prove that the hardware representativeness is valid, a typical example is: in terms of electromagnetic compatibility (EMC) certification, the aim is to verify the performance of electrical equipment in electric and magnetic field working environments against interferences and against other equipment, which depends mainly on the electrical circuit of the equipment itself and its working principle. For some electrical devices with the same model, if the electronic circuit and the working principle are completely the same, it is considered that one version of electrical component is used to represent multiple versions of electrical components with the same model used in actual engineering. For example, most DCS manufacturers define different versions of components with different range settings for analog components, but the models are the same, the internal circuit structure and operation principle are also completely the same, and even the ranges of some analog components can be selectively set by software, so that it is not necessary to perform the same EMC verification for each type of analog component actually used. Typical example two: for earthquake resistance identification, the earthquake resistance of the hardware mainly depends on the mechanical structure and the installation mode of the hardware, and under the condition that the mechanical structure and the installation mode of the hardware are completely the same, parts with the types and the versions identical to those used in actual engineering do not need to be used for earthquake resistance identification.
It should be noted that when the identification is performed by using a component different from that used in actual engineering, the reason for its representativeness must be clearly analyzed in the identification file, and if necessary, detailed technical parameters and a device structure diagram need to be provided to assist in description, so as to ensure the representativeness and effectiveness of the device identification prototype.
Furthermore, in order to verify the basic functions of the nuclear power plant safety level DCS, corresponding software is necessarily configured for an authentication test, the software is only a measure for assisting in verifying the basic functions of the platform, and the basic principle is that all the basic functions of the platform should be covered. The configured software functions are shown in fig. 6: the configured software functions include: analog quantity signal input and output processing logic function, digital quantity signal input and output logic function, signal transmission logic function among different CPUs and control and display logic function of the touch screen. Analog quantity signal input output processing logic functions may be used to verify functions 3, 4 and 8; the digital quantity signal input output logic function may be used to verify functions 3, 5 and 8; the logic function of the transmission of signals among different CPUs can be used for verifying function 1, function 2 and function 8; the control and display logic functions of the touch screen may be used for the authentication function 6, the function 7 and the function 9.
Example two
The embodiment of the invention provides a configuration system of a nuclear power plant safety-level DCS equipment identification prototype, which is suitable for the design process of the nuclear power plant safety-level DCS equipment identification prototype shown in the first embodiment, and fig. 7 is a schematic diagram of a configuration system function module of the nuclear power plant safety-level DCS equipment identification prototype provided by the second embodiment of the invention, and the system comprises:
the function judging module 100 is configured to determine all basic functions of the security level DCS device according to a security level DCS device authentication object to be authenticated; all basic functions include: the system comprises a ring network communication function, a point-to-point communication function, a subsystem communication function, an analog signal input/output function, a digital signal input/output function, a static display function, a touch screen signal input function, a control logic processing function and a display data generating function.
The design module 200 is connected to the function judgment module 100, and is configured to construct a minimum system architecture diagram enveloping all the basic functions according to all the determined basic functions; the scale of the equipment identification prototype is simplified while the prototype used for safety-level DCS equipment identification is ensured to completely and correctly represent the equipment used in actual engineering, so that the equipment identification period and the equipment cost are reduced;
the configuration module 300 is connected with the design module 200 and is used for carrying out corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype; and (3) performing hardware and software configuration on the constructed minimum system framework, so that the designed identification prototype is more suitable for practical engineering application, and the effectiveness of the identification prototype is ensured.
The standard establishing module 400 is connected with the configuration module 300 and is used for selecting an identification test item for the designed equipment identification prototype and making a judgment criterion of the identification test according to the corresponding standard and the technical specification of the platform system. The evaluation result of the equipment identification prototype can be evaluated by establishing a judgment criterion, so that the usability and the effectiveness of the basic functions of the platform in the identification process can be checked.
Wherein the configuration module 300 comprises:
the hardware configuration module 310 is connected with the design module 200, and is configured to perform hardware configuration on the constructed minimum system architecture diagram, list names and models of hardware in a table form, and compare the names and models with hardware in actual engineering application to ensure the validity of the hardware; the names and the models of the hardware are listed in a tabular form, so that the hardware is convenient for operators to observe and compare, the configuration process is stored and recorded, the organization is clearer, the achievement is more persuasive, and the relevant examination work of a nuclear safety supervision department can be more effectively matched.
And the software configuration module 320 is connected with the design module 200 and is used for performing software configuration on the constructed minimum system architecture diagram, and the configured software functions are used for realizing all the basic functions in the function judgment module. The configured software functions include: analog quantity signal input and output processing logic function, digital quantity signal input and output logic function, signal transmission logic function among different CPUs and control and display logic function of the touch screen.
In conclusion, the invention provides a design process and a configuration system of a nuclear power plant safety-level DCS equipment identification prototype, which ensure that the prototype used for safety-level DCS equipment identification can completely and correctly represent the equipment used in actual engineering by configuring hardware and software, have direct guiding significance for designing the prototype in the nuclear power plant safety-level DCS equipment identification, and realize the technical effects of improving the design efficiency of the safety-level DCS equipment identification prototype and reducing the cost of related identification activities by the equipment identification prototype designed by the typical analysis method; furthermore, the models and versions of the hardware are listed in a tabular form in the hardware configuration process, so that the organization is clearer, the achievement is more persuasive, and the relevant examination work of a nuclear safety supervision department can be more effectively matched; and the usability and the effectiveness of the basic functions of the inspection platform in the identification process are ensured by formulating judgment criteria of the identification test.
It should be noted that: in practical applications, the functions may be distributed by different functional modules according to needs, that is, the internal structure of the device may be divided into different functional modules, so as to complete all or part of the functions described above. In addition, the system and method embodiments provided by the above embodiments belong to the same concept, and specific implementation processes thereof are described in detail in the method embodiments and are not described herein again.
Those skilled in the art will appreciate that all or part of the steps for implementing the above embodiments may be implemented by hardware, or may be implemented by a program instructing associated hardware, and the program may be stored in a computer readable storage medium.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents, improvements and the like that fall within the spirit and principle of the present invention are intended to be included therein.
Claims (10)
1. A design flow of a nuclear power plant safety level DCS equipment identification prototype is characterized by comprising the following steps:
determining all basic functions of the security level DCS equipment according to the security level DCS equipment identification object to be identified;
constructing a minimum system architecture diagram enveloping all basic functions according to all the determined basic functions;
and carrying out corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype.
2. The design process of the nuclear power plant safety level DCS equipment authentication prototype according to claim 1, characterized in that the design process further comprises:
and selecting an identification test item and formulating a judgment criterion of the identification test according to the corresponding standard and the technical specification of the platform system.
3. The design process of the nuclear power plant safety-level DCS equipment authentication prototype according to claim 2, wherein the determining all basic functions of the safety-level DCS equipment according to the safety-level DCS equipment authentication object to be authenticated comprises: the system comprises a ring network communication function, a point-to-point communication function, a subsystem communication function, an analog signal input/output function, a digital signal input/output function, a static display function, a touch screen signal input function, a control logic processing function and a display data generating function.
4. The design process of the nuclear power plant safety-level DCS equipment identification prototype according to claim 3, wherein the step of performing corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype comprises the steps of:
the established minimum system architecture diagram is subjected to hardware configuration, the name and the model of the hardware are listed in a table form, and the name and the model are compared with the hardware in actual engineering application to ensure the effectiveness of the hardware;
and carrying out software configuration on the constructed minimum system architecture diagram, wherein the configured software functions are used for realizing all basic functions of the safety-level DCS equipment.
5. The design process of the nuclear power plant safety level DCS equipment authentication prototype according to claim 4, wherein the configured software functions comprise: analog quantity signal input and output processing logic function, digital quantity signal input and output logic function, signal transmission logic function among different CPUs and control and display logic function of the touch screen.
6. A configuration system of a nuclear power plant safety level DCS equipment identification prototype is characterized by comprising:
the function judging module is used for determining all basic functions of the security level DCS equipment according to the security level DCS equipment identification object to be identified;
the design module is connected with the function judgment module and used for constructing a minimum system architecture diagram enveloping all the basic functions according to all the determined basic functions;
and the configuration module is connected with the design module and is used for carrying out corresponding hardware and software configuration on the constructed minimum system architecture diagram to complete the design of the equipment identification prototype.
7. The configuration system of the nuclear power plant safety level DCS equipment authentication prototype of claim 6, further comprising:
and the standard establishing module is connected with the configuration module and used for selecting an identification test item for the designed equipment identification prototype and formulating a judgment criterion of the identification test according to the corresponding standard and the technical specification of the platform system.
8. The configuration system of the nuclear power plant safety level DCS equipment authentication prototype according to claim 7, wherein all the basic functions in the function judgment module comprise: the system comprises a ring network communication function, a point-to-point communication function, a subsystem communication function, an analog signal input/output function, a digital signal input/output function, a static display function, a touch screen signal input function, a control logic processing function and a display data generating function.
9. The configuration system of the nuclear power plant safety level DCS equipment authentication prototype according to claim 8, wherein the configuration module comprises:
the hardware configuration module is connected with the design module and used for performing hardware configuration on the constructed minimum system architecture diagram, listing the name and the model of the hardware in a table form, and comparing the name and the model with the hardware in actual engineering application to ensure the effectiveness of the hardware;
and the software configuration module is connected with the design module and used for performing software configuration on the constructed minimum system architecture diagram, and the configured software functions are used for realizing all the basic functions in the function judgment module.
10. The configuration system of the nuclear power plant safety level DCS equipment authentication prototype according to claim 9, wherein the configured software functions comprise: analog quantity signal input and output processing logic function, digital quantity signal input and output logic function, signal transmission logic function among different CPUs and control and display logic function of the touch screen.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910797548.6A CN110618661A (en) | 2019-08-27 | 2019-08-27 | Design process and configuration system of nuclear power plant safety level DCS equipment identification prototype |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910797548.6A CN110618661A (en) | 2019-08-27 | 2019-08-27 | Design process and configuration system of nuclear power plant safety level DCS equipment identification prototype |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN110618661A true CN110618661A (en) | 2019-12-27 |
Family
ID=68922052
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910797548.6A Pending CN110618661A (en) | 2019-08-27 | 2019-08-27 | Design process and configuration system of nuclear power plant safety level DCS equipment identification prototype |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110618661A (en) |
Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102522128A (en) * | 2011-11-09 | 2012-06-27 | 中广核工程有限公司 | Method and system for testing configuration logic design of DCS (Distributed Control System) of nuclear power station |
| CN104898512A (en) * | 2015-05-05 | 2015-09-09 | 北京广利核系统工程有限公司 | Construction method of equipment appraisal model machine for nuclear power plant nuclear safety level digitized instrument control system |
| CN106257367A (en) * | 2015-06-18 | 2016-12-28 | 中核控制系统工程有限公司 | A kind of nuclear power DCS platform test device based on analogue system and method for testing |
| CN106528060A (en) * | 2015-09-11 | 2017-03-22 | 黑龙江傲立辅龙科技开发有限公司 | Train control system-based expandable security computer platform construction method |
| WO2018083658A1 (en) * | 2016-11-07 | 2018-05-11 | Molecular Devices (Austria) GmbH | System for optically monitoring operating conditions in a sample analyzing apparatus |
| CN109032100A (en) * | 2018-09-21 | 2018-12-18 | 北京广利核系统工程有限公司 | A method of identification npp safety grade I&C system equipment applicability |
| CN109324597A (en) * | 2018-09-21 | 2019-02-12 | 北京广利核系统工程有限公司 | A kind of engineering adaptability test method of two generation of nuclear power station pressurization water-water reactor safety level DCS |
| CN208507215U (en) * | 2018-07-27 | 2019-02-15 | 北京广利核系统工程有限公司 | A kind of digitlization post-accident monitoring system device for nuclear power station |
| CN109765860A (en) * | 2018-12-17 | 2019-05-17 | 中广核研究院有限公司 | Verification method, verifying device and the verifying system of nuclear reactor DCS |
-
2019
- 2019-08-27 CN CN201910797548.6A patent/CN110618661A/en active Pending
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102522128A (en) * | 2011-11-09 | 2012-06-27 | 中广核工程有限公司 | Method and system for testing configuration logic design of DCS (Distributed Control System) of nuclear power station |
| CN104898512A (en) * | 2015-05-05 | 2015-09-09 | 北京广利核系统工程有限公司 | Construction method of equipment appraisal model machine for nuclear power plant nuclear safety level digitized instrument control system |
| CN106257367A (en) * | 2015-06-18 | 2016-12-28 | 中核控制系统工程有限公司 | A kind of nuclear power DCS platform test device based on analogue system and method for testing |
| CN106528060A (en) * | 2015-09-11 | 2017-03-22 | 黑龙江傲立辅龙科技开发有限公司 | Train control system-based expandable security computer platform construction method |
| WO2018083658A1 (en) * | 2016-11-07 | 2018-05-11 | Molecular Devices (Austria) GmbH | System for optically monitoring operating conditions in a sample analyzing apparatus |
| CN208507215U (en) * | 2018-07-27 | 2019-02-15 | 北京广利核系统工程有限公司 | A kind of digitlization post-accident monitoring system device for nuclear power station |
| CN109032100A (en) * | 2018-09-21 | 2018-12-18 | 北京广利核系统工程有限公司 | A method of identification npp safety grade I&C system equipment applicability |
| CN109324597A (en) * | 2018-09-21 | 2019-02-12 | 北京广利核系统工程有限公司 | A kind of engineering adaptability test method of two generation of nuclear power station pressurization water-water reactor safety level DCS |
| CN109765860A (en) * | 2018-12-17 | 2019-05-17 | 中广核研究院有限公司 | Verification method, verifying device and the verifying system of nuclear reactor DCS |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN100454196C (en) | Method for verifying safety apparatus and safety apparatus verified by the same | |
| CN103163397B (en) | Universal analog quantity plate detection system for nuclear plant and method | |
| CN109765860B (en) | Nuclear reactor DCS verification method, verification device and verification system | |
| CN101572440B (en) | Power grid code analysis and test method | |
| CN110427314B (en) | Method and system for testing information safety reliability of metering automation terminal | |
| CN112269744A (en) | System abnormity testing method and device, computer equipment and storage medium | |
| CN106201804A (en) | The device of a kind of measuring and calculation mainboard, method and system | |
| CN106294036A (en) | A kind of hardware fault verification method, device and client | |
| CN102841305A (en) | System and method for debugging FPGA (field programmable gate array) in real time | |
| US20120323341A1 (en) | Control device | |
| CN202421448U (en) | Relay detecting device for nuclear power stations | |
| Lee et al. | PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systems | |
| CN110618661A (en) | Design process and configuration system of nuclear power plant safety level DCS equipment identification prototype | |
| CN104898512B (en) | The construction method of nuclear power plant's nuclear safe level digitlization instrument control system equipment identification model machine | |
| CN113739926B (en) | Method and device for detecting temperature rise fault of train electric appliance cabinet and terminal equipment | |
| CN112214403B (en) | Automatic test method, device and system based on protection device model file | |
| CN108983714B (en) | Method and device for monitoring state of unit of million-kilowatt nuclear power station and terminal equipment | |
| CN113778552A (en) | Monitoring parameter modification method and device and computer equipment | |
| Yasko et al. | Verification of FPGA based NPP I&C systems considering multiple faults: Technique and automation tool | |
| Hassan et al. | Digital I&C systems in nuclear power plants. Risk-screening of environmental stressors and a comparison of hardware unavailability with an existing analog system | |
| CN104483574B (en) | The method of three-dimensional effect pilot system and test device three-dimensional effect | |
| Hirschberg | Prospects for probabilistic safety assessment | |
| CN117784698B (en) | Automatic test method and device for diesel engine control logic | |
| Hwang et al. | Black-box testing tool of railwaysignalling system software with a focus on user convenience | |
| CN113132521B (en) | Soft fault test method and system for mobile terminal |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| RJ01 | Rejection of invention patent application after publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20191227 |