CN113408078A - Control system analysis method and device - Google Patents
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Abstract
The embodiment of the invention provides an analysis method and device of a control system. The method comprises the following steps: the method comprises the steps of dividing a nuclear-grade water chilling unit control system according to a function level to obtain a plurality of functional units, dividing the nuclear-grade water chilling unit control system according to a structure level to obtain a plurality of structural units, setting corresponding fault codes for all unit combinations respectively, setting fault modes of all the functional units for all the functional units based on fault judgment bases of all the functional units, setting severity levels of the fault modes of all the functional units for all the functional units according to the fault modes of all the functional units, calculating fault probabilities of all the functional units under all the fault modes of all the functional units according to a first number and a second number, and generating an analysis table of the control system. The invention realizes the discovery of possible design defects and weak links in the scheme research and design stage of the nuclear-grade water chilling unit control system, thereby selecting a safer and more reliable design scheme.
Description
Technical Field
The present invention relates to the field of reliability analysis, and in particular, to an analysis method and an analysis device for a control system.
Background
The traditional nuclear-grade water chilling unit control system is controlled by adopting a non-nuclear controller, but the non-nuclear controller does not implement a safety-grade design rule and perform reliability analysis aiming at the use condition of a nuclear power plant in the stage of scheme research and design, so that the problems of low reliability, high fault rate and the like of the traditional nuclear-grade water chilling unit control system under the actual condition exist, and the operation safety of the nuclear power plant is directly influenced.
Disclosure of Invention
The embodiment of the invention aims to provide an analysis method and device of a control system, so that possible design defects and weak links can be found in the stages of scheme research and design, and a safer and more reliable design scheme can be selected. The specific technical scheme is as follows:
an analysis method of a control system, which is used for analyzing a nuclear grade water chilling unit control system, and comprises the following steps:
and dividing the nuclear-grade water chilling unit control system according to the functional hierarchy to obtain a plurality of functional units, and dividing the nuclear-grade water chilling unit control system according to the structural hierarchy to obtain a plurality of structural units.
Respectively setting corresponding fault codes for each unit combination, wherein the unit combination comprises: one functional unit and each structural unit corresponding to the functional unit, wherein the fault code is used for indicating the corresponding unit combination.
And establishing the fault mode of each functional unit according to the sequence from the lowest layer to the highest layer based on the fault judgment basis of each functional unit.
And according to the fault mode of the functional unit at the highest level, establishing the severity level of the fault mode for the functional unit at the highest level.
Calculating the failure probability of each functional unit under each failure mode of the functional unit according to a first quantity and a second quantity, wherein the first quantity is the quantity of the functional units which normally operate in a first historical time period and fail in a second historical time period; the second number is the number of functional units that normally operate in a first history period and that normally operate in a second history period, which is a period after the first history period.
Generating an analysis table of the nuclear-grade chiller control system based at least on the fault code, the fault mode, the severity level, and the fault probability.
Optionally, the plurality of functional units include:
the system comprises at least one of an equipment operation and display unit, a system power supply unit, a signal isolation distribution unit, a signal acquisition unit, an IO communication unit, a logic processing unit, a signal output unit and a network communication unit.
Optionally, the plurality of structural units include:
the system comprises at least one of human-computer interaction equipment, system power supply equipment, thermal resistance conditioning and isolating equipment, signal conditioning and isolating equipment, an isolation distribution relay, a digital quantity acquisition card, an analog quantity acquisition card, an IO bus management card, an IO communication card, a main processing card, a digital quantity output card, an analog quantity output card, a network communication card, a photoelectric conversion card, network communication equipment and photoelectric conversion equipment.
Optionally, the signal isolation and distribution unit corresponds to the thermal resistance conditioning and isolation device, the signal conditioning and isolation device, and the isolation and distribution relay, respectively.
The signal acquisition unit corresponds to the digital quantity acquisition card and the analog quantity acquisition card respectively.
The IO communication unit corresponds to the IO bus management card and the IO communication card respectively.
The logic processing unit corresponds to the main processing card.
The signal output unit corresponds to the digital quantity output card and the analog quantity output card respectively.
The network communication unit corresponds to the network communication card, the photoelectric conversion card, the network communication equipment and the photoelectric conversion equipment respectively.
The equipment operation and display unit corresponds to the human-computer interaction equipment.
The system power supply unit corresponds to the system power supply equipment.
Optionally, the failure mode includes: a first type of failure mode and/or a second type of failure mode.
The first type of failure mode is: a failure that can be self-diagnosed by the control system.
The second type of failure mode is: failure that cannot be self-diagnosed by the control system.
Optionally, the fault determination criterion includes: at least one of the first determination criterion, the second determination criterion, and the third determination criterion.
The first determination criterion is as follows: in the process that the control system operates for a preset time under a preset operation condition, the functional unit cannot complete a specified function.
The second determination criterion is as follows: in the process that the control system runs for a preset time under a preset running condition, the preset performance index of the functional unit cannot be kept within a preset index range.
The third determination criterion is: in the process that the control system runs for the preset duration under the preset running condition, the functional unit breaks down and the influence caused by the fault exceeds the preset influence range.
Optionally, the calculating the failure probability of each functional unit in each failure mode according to the first number and the second number includes:
according to
The failure probability lambda (t) of the functional unit under the target failure mode is obtained through calculation, wherein dfNf(t) is a first quantity, dt is a duration of the second historical time period, Ns(t) is the second number.
Optionally, the method further includes:
determining compensation measures and diagnosis methods corresponding to the fault modes;
and adding the compensation measures and the diagnosis method into a generated analysis table of the nuclear grade water chilling unit control system.
An analysis device for a control system for analyzing a nuclear grade chiller control system, the device comprising:
and the hierarchical division unit is used for dividing the nuclear-grade water chilling unit control system according to the functional hierarchy to obtain a plurality of functional units, and dividing the nuclear-grade water chilling unit control system according to the structural hierarchy to obtain a plurality of structural units.
The code setting unit is used for setting corresponding fault codes for each unit combination, wherein the unit combination comprises: one functional unit and each structural unit corresponding to the functional unit, wherein the fault code is used for indicating the corresponding unit combination.
And the failure mode setting unit is used for setting the failure modes of the functional units for the functional units according to the sequence from the lowest level to the highest level based on the failure judgment basis of the functional units.
And the severity level setting unit is used for setting the severity level of the fault mode of the functional unit at the highest level for the functional unit at the highest level according to the fault mode of the functional unit at the highest level.
The fault probability calculation unit is used for calculating the fault probability of each functional unit under each fault mode of the functional unit according to a first quantity and a second quantity, wherein the first quantity is the quantity of the functional units which normally operate in a first historical time period and have faults in a second historical time period; the second number is the number of functional units that normally operate in a first history period and that normally operate in a second history period, which is a period after the first history period.
And the analysis table generating unit is used for generating an analysis table of the nuclear-grade water chilling unit control system at least based on the fault code, the fault mode, the severity level and the fault probability.
Optionally, the method further includes:
and the compensation measure determining unit is used for determining the compensation measures and the diagnosis methods corresponding to the fault modes.
And the table filling unit is used for adding the compensation measures and the diagnosis method into the generated analysis table of the nuclear grade water chilling unit control system.
The analysis method and the device for the control system provided by the embodiment of the invention divide the function level of the control system through the functional indexes of the power plant on the operation data and the functional elements of the nuclear power cooling and determining unit control system, so that the reliability of each functional unit is more refined and accurate when being analyzed, the invention can also realize the retrieval of the data of the fault mode, the severity and the like of any functional element according to the generated fault code, so that the indexing and the retrieval of whether the fault mode and the functional unit are faulty or not are more efficient, meanwhile, the capture of the potential safety hazard or the weak link of the design defect in the research and development stage can be realized in the design stage through the research and the simulation operation of the data on the basis of the data of the fault mode, the fault judgment basis, the severity level of the fault mode and the like included in the fault code, therefore, row modification and prevention are carried out, the cost is reduced, and the reliability and the safety of the control system of the nuclear-grade water chilling unit are improved.
Of course, it is not necessary for any product or method of practicing the invention to achieve all of the above-described advantages at the same time.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
Fig. 1 is a flowchart of an analysis method of a control system according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of a nuclear-grade water chilling unit control system according to an embodiment of the present invention;
fig. 3 is a schematic structural diagram of a functional hierarchy of a control system of a nuclear-grade water chilling unit according to an alternative embodiment of the present invention;
fig. 4 is a schematic structural diagram of a nuclear-grade chiller control system hierarchy according to an alternative embodiment of the present invention;
fig. 5 is a schematic diagram of a coding system of a nuclear-grade chiller control system according to an alternative embodiment of the present invention;
fig. 6 is a block diagram of an analysis device of a control system according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
As shown in fig. 1, an embodiment of the present invention provides an analysis method for a control system, which is used for analyzing a nuclear-grade chiller control system, and the method includes:
s101, dividing the nuclear-grade water chilling unit control system according to the functional hierarchy to obtain a plurality of functional units, and dividing the nuclear-grade water chilling unit control system according to the structural hierarchy to obtain a plurality of structural units.
Optionally, in practical application, the functional level of the nuclear-grade chiller control system is mainly derived from the functional requirement of the power plant on the nuclear-grade chiller, so that the structural level of the nuclear-grade chiller control system is analyzed.
The initial appointed level (i.e., the highest level functional unit) of the invention is a nuclear-grade chiller control system, and the control architecture of the nuclear-grade chiller control system shown in fig. 2 is obtained by analyzing the application requirements of the power plant and the requirements of the functions of the chiller. The equipment operation and display system 201 is connected with the network communication system 202 through network communication, the network communication system 202 is connected with the photoelectric conversion system 203 through network communication, the photoelectric conversion system 203 is connected with the logic control system 204 through optical fibers, the logic control system 204 is connected with the IO acquisition system 205 through network communication, the nuclear-grade water chilling unit 206 is connected with the signal conditioning system 207 through hard wiring, the nuclear-grade water chilling unit 206 is connected with the IO acquisition system 205 through hard wiring, the signal conditioning system 207 is connected with the IO acquisition system 205 through hard wiring, and the signal conditioning system 207 is connected with the fault recording system 208 through hard wiring.
Optionally, in another optional embodiment of the present invention, according to the control architecture shown in fig. 2, the control system 300 of the nuclear-grade water chilling unit is decomposed by combining functions and signal flow directions, so as to obtain a plurality of functional units shown in fig. 3, where the functional units include: the system comprises an equipment operation and display unit 301, a system power supply unit 302, a signal isolation distribution unit 303, a signal acquisition unit 304, an IO communication unit 305, a logic processing unit 306, a signal output unit 307 and a network communication unit 308.
Optionally, in practical application, when the structure level is divided, the lowest agreed level is determined according to a maintenance plan and a maintenance mode of a nuclear power plant operation and maintenance stage, and for a local hardware fault of the nuclear-grade water chilling unit control system, the maintenance mode adopted by the nuclear power plant is to replace a spare part for a fault structure unit, so that the lowest agreed level of the control system is located to be the smallest replaceable unit.
Optionally, in another optional embodiment of the present invention, according to the control architecture shown in fig. 2, splitting the minimum replaceable unit stage by stage to obtain a plurality of structural units shown in fig. 4 includes: a Human Machine Interface (HMI) 401, a system power supply device 402, a thermal resistance conditioning and isolating device 403, a signal conditioning and isolating device 404, an isolating and distributing relay 405, a digital quantity acquisition card (DI) 406, an Analog quantity acquisition card (AI) 407, an IO bus management card 408, an IO Communication card (Sub-module Communication Unit, SCU)409, a main processing card 410, a digital quantity Output card (DO) 411, an Analog quantity Output card (AO) 412, a network Communication card 413, a photoelectric conversion card 414, a network Communication device 415 and a photoelectric conversion device 416, wherein the IO Communication card 409, the main processing card 410, the network Communication card 413 and the photoelectric conversion card 414 are respectively located in an IO station 417 and a slave control station 418, the digital quantity acquisition card 406, the main control quantity acquisition card 408, the Analog quantity bus management card 411, the digital quantity Output card 412 and the Analog quantity Output card 419 are located in an IO Communication Interface box, the signal conditioning and isolating equipment 404 is 4-20 m signal conditioning and isolating equipment, and 220V and 50HZ alternating currents are adopted to supply power to the control system through the system power supply equipment 402.
S102, respectively setting corresponding fault codes for each unit combination, wherein each unit combination comprises: one functional unit and each structural unit corresponding to the functional unit, and the fault code is used for indicating the corresponding unit combination.
In order to perform statistics, analysis, tracking and feedback on the failure modes of the control system, a coding system needs to be formulated according to the divided layers, namely, a corresponding relation between the functional units and the structural units is established, and corresponding failure codes are set for unit combinations.
And S103, establishing the fault mode of each functional unit according to the sequence from the lowest layer to the highest layer based on the fault judgment basis of each functional unit.
The failure mode can be obtained by combining relevant data of test, analysis, statistics and prediction according to the function of the functional unit to be judged, and the specific failure mode is not limited too much.
The above-mentioned failure determination basis can be determined according to the allowable limit of the data such as the function, the use environment, the performance index and the like of the functional unit in the actual application scene, and the specific failure determination basis is not limited too much in the present invention.
Optionally, in practical applications, the fault mode and the fault determination basis can be formulated preferentially for the functional units at the lowest level according to requirements, and then the fault mode and the fault determination basis for the functional units at each level are formulated sequentially layer by layer upwards, a specific execution sequence is subject to the purpose of achieving the invention, and the specific execution sequence is not limited too much.
And S104, establishing the severity level of the fault mode for the functional unit at the highest level according to the fault mode of the functional unit at the highest level.
Optionally, in practical applications, the severity level is established for an initial engagement hierarchy, and here, it should be understood with reference to another alternative embodiment of the present invention as shown in table 1:
for convenience of understanding, the above-mentioned alternative embodiment of the present invention uses the chiller units of a third generation nuclear power plant as an example, in the third generation nuclear power plant, the nuclear-grade chiller units adopt a redundant configuration, when the power plant operates normally, the chiller units are all in an operating state, each chiller unit outputs in a power regulation mode according to the requirement of the chiller capacity of the power plant, and when 1 chiller unit is damaged or is in a maintenance state, the missing chiller capacity is provided by other units. According to the process operation principle and the severity of the fault influence of a single water chilling unit, the severity grade score of the fault mode of the nuclear grade water chilling unit control system shown in the table 1 is obtained:
TABLE 1 severity rating Table
Optionally, the above scoring criteria for severity level and specific conditions are set for illustration in the embodiment of the present invention, and those skilled in the art can set the scoring criteria according to the actual conditions, which is not limited by the present invention.
S105, calculating the failure probability of each functional unit in each failure mode according to a first quantity and a second quantity, wherein the first quantity is the quantity of the functional units which normally operate in a first historical time period and have failures in a second historical time period; the second number is the number of functional units that normally operate in the first history period and that normally operate in the second history period, which is a period after the first history period.
The fault probability can be used as an index for measuring the reliability of the control system of the nuclear-grade water cooling unit, and the reliability of each level of functional units of the control system can be judged according to the fault probability, so that weak links with potential safety hazards or design defects are found in the design research and development stage, and targeted modification and prevention are performed.
And S106, generating an analysis table of the control system of the nuclear-grade water chilling unit at least based on the fault codes, the fault modes, the severity levels and the fault probabilities.
The analysis method and the device for the control system provided by the embodiment of the invention divide the function level of the control system through the functional indexes of the power plant on the operation data and the functional elements of the nuclear power cooling and determining unit control system, so that the reliability of each functional unit is more refined and accurate when being analyzed, the invention can also realize the retrieval of the data of the fault mode, the severity and the like of any functional element according to the generated fault code, so that the indexing and the retrieval of whether the fault mode and the functional unit are faulty or not are more efficient, meanwhile, the capture of the potential safety hazard or the weak link of the design defect in the research and development stage can be realized in the design stage through the research and the simulation operation of the data on the basis of the data of the fault mode, the fault judgment basis, the severity level of the fault mode and the like included in the fault code, therefore, row modification and prevention are carried out, the cost is reduced, and the reliability and the safety of the control system of the nuclear-grade water chilling unit are improved.
Optionally, the plurality of functional units may include:
the system comprises at least one of an equipment operation and display unit, a system power supply unit, a signal isolation distribution unit, a signal acquisition unit, an IO communication unit, a logic processing unit, a signal output unit and a network communication unit.
Optionally, the plurality of structural units may include:
the system comprises at least one of human-computer interaction equipment, system power supply equipment, thermal resistance conditioning and isolating equipment, signal conditioning and isolating equipment, an isolation distribution relay, a digital quantity acquisition card, an analog quantity acquisition card, an IO bus management card, an IO communication card, a main processing card, a digital quantity output card, an analog quantity output card, a network communication card, a photoelectric conversion card, network communication equipment and photoelectric conversion equipment.
Optionally, the signal isolation and distribution unit corresponds to the thermal resistance conditioning and isolation device, the signal conditioning and isolation device, and the isolation and distribution relay, respectively.
The signal acquisition unit corresponds to the digital quantity acquisition card and the analog quantity acquisition card respectively.
The IO communication unit corresponds to the IO bus management card and the IO communication card respectively.
The logic processing unit corresponds to the main processing card.
The signal output unit corresponds to the digital quantity output card and the analog quantity output card respectively.
The network communication unit corresponds to the network communication card, the photoelectric conversion card, the network communication equipment and the photoelectric conversion equipment respectively.
The equipment operation and display unit corresponds to the human-computer interaction equipment.
The system power supply unit corresponds to a system power supply device.
For the above correspondence and fault codes, please refer to another alternative embodiment of the present invention as shown in fig. 5, wherein each number in the dashed box in fig. 5 is a fault code. Wherein, the fault code of the man-machine interaction device is 501, the fault code of the system power supply device is 502, the fault code of the thermal resistance conditioning isolation device is 503, the fault code of the signal conditioning isolation device is 504, the fault code of the isolation distribution relay is 505, the fault code of the digital quantity acquisition card is 506, the fault code of the analog quantity acquisition card is 507, the fault code of the IO bus management card is 508, the fault code of the IO communication card is 509, the fault code of the main processing card is 510, the fault code of the digital quantity output card is 511, the fault code of the analog quantity output card is 512, the fault code of the network communication card is 513, the fault code of the photoelectric conversion card is 514, the fault code of the network communication device is 515, the fault code of the photoelectric conversion device is 516, the specific numerical value of the fault code can be selected according to actual needs, and the invention is not limited herein.
Optionally, the failure mode includes:
a first type of failure mode and/or a second type of failure mode.
The first type of failure mode is: failure that can be self-diagnosed by the control system.
The second type of failure mode is: failure that cannot be self-diagnosed by the control system.
Optionally, for convenience of understanding, please refer to another optional embodiment of the present invention shown in table 2 to understand the failure mode, and the failure mode may be set by itself according to the parameter information and the history data of the functional unit, and the present invention does not limit the specific failure mode too much.
TABLE 2 Fault mode LUT
Optionally, the above fault determination criterion includes:
at least one of the first determination criterion, the second determination criterion, and the third determination criterion.
The first criterion is: in the process that the control system operates for the preset time under the preset operation condition, the functional unit cannot complete the specified function.
The second determination criterion is: in the process that the control system operates for the preset time under the preset operation condition, the preset performance index of the functional unit cannot be kept within the preset index range.
The third criterion is: in the process that the control system runs for the preset duration under the preset running condition, the functional unit breaks down and the influence caused by the fault exceeds the preset influence range.
Optionally, the fault determination criterion may be set autonomously according to a parameter index, operation history data, and a maintenance time limit of the functional unit, which is not limited by the present invention.
Optionally, the calculating the failure probability of each functional unit in each failure mode according to the first number and the second number includes:
according to
Calculating and obtaining the failure probability lambda (t) of the functional unit under the target failure mode, wherein dNf(t) is a first quantity, dt is a duration of a second historical time period, Ns(t) is the second number.
Optionally, the method further includes:
and determining compensation measures and diagnosis methods corresponding to the fault modes.
And adding the compensation measures and the diagnosis method into the generated analysis table of the nuclear grade water chilling unit control system.
The analysis method and the device for the control system provided by the embodiment of the invention divide the function level of the control system through the functional indexes of the power plant on the operation data and the functional elements of the nuclear power cooling and determining unit control system, so that the reliability of each functional unit is more refined and accurate when being analyzed, the invention can also realize the retrieval of the data of the fault mode, the severity and the like of any functional element according to the generated fault code, so that the indexing and the retrieval of whether the fault mode and the functional unit are faulty or not are more efficient, meanwhile, the capture of the potential safety hazard or the weak link of the design defect in the research and development stage can be realized in the design stage through the research and the simulation operation of the data on the basis of the data of the fault mode, the fault judgment basis, the severity level of the fault mode and the like included in the fault code, therefore, row modification and prevention are carried out, the cost is reduced, and the reliability and the safety of the control system of the nuclear-grade water chilling unit are improved.
Corresponding to the above embodiment of the analysis method of the control system, the present invention further provides an analysis device of the control system, the device is used for analyzing the control system of the nuclear-grade water chiller, as shown in fig. 6, the device includes:
the hierarchical division unit 801 is configured to divide the nuclear-level chiller control system according to a functional hierarchy to obtain a plurality of functional units, and divide the nuclear-level chiller control system according to a structural hierarchy to obtain a plurality of structural units.
A code setting unit 802, configured to set corresponding fault codes for each unit combination, where the unit combination includes: one functional unit and each structural unit corresponding to the functional unit, and the fault code is used for indicating the corresponding unit combination.
A failure mode setting unit 803, configured to set failure modes of the functional units in order from the lowest hierarchy to the highest hierarchy based on failure determination bases of the functional units.
And a severity level setting unit 804 configured to set a severity level of a failure mode of the highest-level functional unit for the highest-level functional unit according to the failure mode of the highest-level functional unit.
A failure probability calculation unit 805 configured to calculate failure probabilities of the functional units in the failure modes of the functional units according to a first number and a second number, where the first number is the number of functional units that normally operate in the first history time period and have failed in the second history time period; the second number is the number of functional units that normally operate in the first history period and that normally operate in the second history period, which is a period after the first history period.
And the analysis table generating unit 806 is used for generating an analysis table of the nuclear-grade water chilling unit control system at least based on the fault code, the fault mode, the severity level and the fault probability.
Optionally, the plurality of functional units may include:
the system comprises at least one of an equipment operation and display unit, a system power supply unit, a signal isolation distribution unit, a signal acquisition unit, an IO communication unit, a logic processing unit, a signal output unit and a network communication unit.
Optionally, the plurality of structural units may include:
the system comprises at least one of human-computer interaction equipment, system power supply equipment, thermal resistance conditioning and isolating equipment, signal conditioning and isolating equipment, an isolation distribution relay, a digital quantity acquisition card, an analog quantity acquisition card, an IO bus management card, an IO communication card, a main processing card, a digital quantity output card, an analog quantity output card, a network communication card, a photoelectric conversion card, network communication equipment and photoelectric conversion equipment.
Optionally, the signal isolation and distribution unit corresponds to the thermal resistance conditioning and isolation device, the signal conditioning and isolation device, and the isolation and distribution relay respectively;
the signal acquisition unit corresponds to the digital quantity acquisition card and the analog quantity acquisition card respectively.
The IO communication unit corresponds to the IO bus management card and the IO communication card respectively.
The logic processing unit corresponds to the main processing card.
The signal output unit corresponds to the digital quantity output card and the analog quantity output card respectively.
The network communication unit corresponds to the network communication card, the photoelectric conversion card, the network communication equipment and the photoelectric conversion equipment respectively.
The equipment operation and display unit corresponds to the human-computer interaction equipment.
The system power supply unit corresponds to a system power supply device.
Optionally, the failure mode includes:
a first type of failure mode and/or a second type of failure mode.
The first type of failure mode is: failure that can be self-diagnosed by the control system.
The second type of failure mode is: failure that cannot be self-diagnosed by the control system.
Optionally, the above fault determination criterion includes:
at least one of the first determination criterion, the second determination criterion, and the third determination criterion.
The first criterion is: in the process that the control system operates for the preset time under the preset operation condition, the functional unit cannot complete the specified function.
The second determination criterion is: in the process that the control system operates for the preset time under the preset operation condition, the preset performance index of the functional unit cannot be kept within the preset index range.
The third criterion is: in the process that the control system runs for the preset duration under the preset running condition, the functional unit breaks down and the influence caused by the fault exceeds the preset influence range.
Optionally, the failure probability calculating unit 805 is specifically configured to:
according to
Calculating and obtaining the failure probability lambda (t) of the functional unit under the target failure mode, wherein dNf(t) is a first quantity, dt is a duration of a second historical time period, Ns(t) is the second number.
Optionally, the apparatus shown in fig. 6 further includes:
and the compensation measure determining unit is used for determining the compensation measures and the diagnosis methods corresponding to the fault modes.
And the table filling unit is used for adding the compensation measures and the diagnosis measures into the generated analysis table of the nuclear grade water chilling unit control system.
The analysis device of the control system comprises a processor and a memory, wherein the hierarchy dividing unit, the code setting unit, the failure mode setting unit, the severity level setting unit, the failure probability calculation unit, the analysis table generation unit, the measure calling unit and the like are stored in the memory as program units, and the processor executes the program units stored in the memory to realize corresponding functions.
The processor comprises a kernel, and the kernel calls the corresponding program unit from the memory. The kernel can be set to be one or more, and the analysis of the control system is realized by adjusting kernel parameters.
The present application is described with reference to flowchart illustrations and/or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of the application. It will be understood that each flow and/or block of the flow diagrams and/or block diagrams, and combinations of flows and/or blocks in the flow diagrams and/or block diagrams, can be implemented by computer program instructions. These computer program instructions may be provided to a processor of a general purpose computer, special purpose computer, embedded processor, or other programmable data processing apparatus to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing apparatus, create means for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
In a typical configuration, a device includes one or more processors (CPUs), memory, and a bus. The device may also include input/output interfaces, network interfaces, and the like.
The memory may include volatile memory in a computer readable medium, Random Access Memory (RAM) and/or nonvolatile memory such as Read Only Memory (ROM) or flash memory (flash RAM), and the memory includes at least one memory chip. The memory is an example of a computer-readable medium.
Computer-readable media, including both non-transitory and non-transitory, removable and non-removable media, may implement information storage by any method or technology. The information may be computer readable instructions, data structures, modules of a program, or other data. Examples of computer storage media include, but are not limited to, phase change memory (PRAM), Static Random Access Memory (SRAM), Dynamic Random Access Memory (DRAM), other types of Random Access Memory (RAM), Read Only Memory (ROM), Electrically Erasable Programmable Read Only Memory (EEPROM), flash memory or other memory technology, compact disc read only memory (CD-ROM), Digital Versatile Discs (DVD) or other optical storage, magnetic cassettes, magnetic tape magnetic disk storage or other magnetic storage devices, or any other non-transmission medium that can be used to store information that can be accessed by a computing device. As defined herein, a computer readable medium does not include a transitory computer readable medium such as a modulated data signal and a carrier wave.
As will be appreciated by one skilled in the art, embodiments of the present application may be provided as a method, system, or computer program product. Accordingly, the present application may take the form of an entirely hardware embodiment, an entirely software embodiment or an embodiment combining software and hardware aspects. Furthermore, the present application may take the form of a computer program product embodied on one or more computer-usable storage media (including, but not limited to, disk storage, CD-ROM, optical storage, and the like) having computer-usable program code embodied therein.
It is noted that, herein, relational terms such as first and second, and the like may be used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. It should also be noted that the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising an … …" does not exclude the presence of other identical elements in the process, method, article, or apparatus that comprises the element.
All the embodiments in the present specification are described in a related manner, and the same and similar parts among the embodiments may be referred to each other, and each embodiment focuses on the differences from the other embodiments. In particular, for the system embodiment, since it is substantially similar to the method embodiment, the description is simple, and for the relevant points, reference may be made to the partial description of the method embodiment.
The above are merely examples of the present application and are not intended to limit the present application. Various modifications and changes may occur to those skilled in the art. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present application should be included in the scope of the claims of the present application.
Claims (10)
1. An analysis method for a control system, which is used for analyzing a nuclear grade water chilling unit control system, and comprises the following steps:
dividing the nuclear-grade water chilling unit control system according to the functional hierarchy to obtain a plurality of functional units, and dividing the nuclear-grade water chilling unit control system according to the structural hierarchy to obtain a plurality of structural units;
respectively setting corresponding fault codes for each unit combination, wherein the unit combination comprises: one functional unit and each structural unit corresponding to the one functional unit, wherein the fault code is used for indicating a corresponding unit combination;
based on the fault judgment basis of each functional unit, establishing the fault mode of each functional unit according to the sequence from the lowest level to the highest level;
according to the fault mode of the functional unit at the highest level, establishing the severity level of the fault mode for the functional unit at the highest level;
calculating the failure probability of each functional unit under each failure mode of the functional unit according to a first quantity and a second quantity, wherein the first quantity is the quantity of the functional units which normally operate in a first historical time period and fail in a second historical time period; the second number is the number of functional units which normally operate in a first historical period of time and normally operate in a second historical period of time, and the second historical period of time is a period of time after the first historical period of time;
generating an analysis table of the nuclear-grade chiller control system based at least on the fault code, the fault mode, the severity level, and the fault probability.
2. The method of claim 1, wherein the plurality of functional units comprises:
the system comprises at least one of an equipment operation and display unit, a system power supply unit, a signal isolation distribution unit, a signal acquisition unit, an IO communication unit, a logic processing unit, a signal output unit and a network communication unit.
3. The method of claim 2, wherein the plurality of building blocks comprises:
the system comprises at least one of human-computer interaction equipment, system power supply equipment, thermal resistance conditioning and isolating equipment, signal conditioning and isolating equipment, an isolation distribution relay, a digital quantity acquisition card, an analog quantity acquisition card, an IO bus management card, an IO communication card, a main processing card, a digital quantity output card, an analog quantity output card, a network communication card, a photoelectric conversion card, network communication equipment and photoelectric conversion equipment.
4. The method of claim 3, wherein the signal isolation and distribution unit corresponds to the thermal resistance conditioning and isolation device, the signal conditioning and isolation device, and the isolation and distribution relay, respectively;
the signal acquisition unit corresponds to the digital quantity acquisition card and the analog quantity acquisition card respectively;
the IO communication unit corresponds to the IO bus management card and the IO communication card respectively;
the logic processing unit corresponds to the main processing card;
the signal output unit corresponds to the digital quantity output card and the analog quantity output card respectively;
the network communication unit corresponds to the network communication card, the photoelectric conversion card, the network communication equipment and the photoelectric conversion equipment respectively;
the equipment operation and display unit corresponds to the human-computer interaction equipment;
the system power supply unit corresponds to the system power supply equipment.
5. The method of claim 1, wherein the failure mode comprises: a first type of failure mode and/or a second type of failure mode,
the first type of failure mode is: a failure that is self-diagnosable by the control system;
the second type of failure mode is: failure that cannot be self-diagnosed by the control system.
6. The method of claim 1, wherein the fault determination criteria comprises: at least one of the first determination criterion, the second determination criterion, and the third determination criterion,
the first determination criterion is as follows: in the process that the control system operates for a preset time under a preset operation condition, the functional unit cannot complete a specified function;
the second determination criterion is as follows: in the process that the control system operates for a preset time under a preset operation condition, the preset performance index of the functional unit cannot be kept within a preset index range;
the third determination criterion is: in the process that the control system runs for the preset duration under the preset running condition, the functional unit breaks down and the influence caused by the fault exceeds the preset influence range.
7. The method of claim 1, wherein calculating the failure probability of each functional unit in each failure mode that the functional unit has based on the first number and the second number comprises:
according to
Calculating and obtaining the failure probability lambda (t) of the functional unit under the target failure mode, wherein dNf(t) is a first quantity, dt is a duration of the second historical time period, Ns(t) is the second number.
8. The method of claim 1, further comprising:
determining compensation measures and diagnosis methods corresponding to the fault modes;
and adding the compensation measures and the diagnosis method into a generated analysis table of the nuclear grade water chilling unit control system.
9. An analysis device for a control system, for analyzing a nuclear grade chiller control system, the device comprising:
the hierarchical division unit is used for dividing the nuclear-grade water chilling unit control system according to functional hierarchy to obtain a plurality of functional units, and dividing the nuclear-grade water chilling unit control system according to structural hierarchy to obtain a plurality of structural units;
the code setting unit is used for setting corresponding fault codes for each unit combination, wherein the unit combination comprises: one functional unit and each structural unit corresponding to the one functional unit, wherein the fault code is used for indicating a corresponding unit combination;
the fault mode setting unit is used for setting the fault mode of each functional unit according to the sequence from the lowest level to the highest level based on the fault judgment basis of each functional unit;
the severity level setting unit is used for setting the severity level of the fault mode of the functional unit at the highest level for the functional unit at the highest level according to the fault mode of the functional unit at the highest level;
the fault probability calculation unit is used for calculating the fault probability of each functional unit under each fault mode of the functional unit according to a first quantity and a second quantity, wherein the first quantity is the quantity of the functional units which normally operate in a first historical time period and have faults in a second historical time period; the second number is the number of functional units which normally operate in a first historical period of time and normally operate in a second historical period of time, and the second historical period of time is a period of time after the first historical period of time;
and the analysis table generating unit is used for generating an analysis table of the nuclear-grade water chilling unit control system at least based on the fault code, the fault mode, the severity level and the fault probability.
10. The apparatus of claim 9, further comprising:
the compensation measure determining unit is used for determining the compensation measures and the diagnosis methods corresponding to the fault modes;
and the table filling unit is used for adding the compensation measures and the diagnosis method into the generated analysis table of the nuclear grade water chilling unit control system.
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