CN111177907B - Automatic assessment method and device for service life of reactor - Google Patents
Automatic assessment method and device for service life of reactor Download PDFInfo
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- CN111177907B CN111177907B CN201911331741.7A CN201911331741A CN111177907B CN 111177907 B CN111177907 B CN 111177907B CN 201911331741 A CN201911331741 A CN 201911331741A CN 111177907 B CN111177907 B CN 111177907B
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Abstract
The invention provides a method and a device for automatically evaluating the service life of a reactor, wherein the method comprises the following steps: acquiring working parameters of a reactor; inputting the working parameters of the reactor into a reactor temperature field model, and outputting the temperature distribution information of the reactor through the reactor temperature field model; selecting highest temperature information of the position where the insulating material is located from the temperature distribution information of the reactor; and determining the aging life of the insulating material to which the highest temperature information belongs as the residual life of the reactor. According to the technical scheme, the automatic assessment of the service life of the reactor is efficiently and accurately performed, the labor cost and the time cost are reduced, the accuracy and the high efficiency of the assessment of the service life of the reactor are improved, and the efficiency of power work is improved.
Description
[ field of technology ]
The invention relates to the technical field of electric power, in particular to an automatic assessment method and device for service life of a reactor.
[ background Art ]
The safe operation and service life of a dry reactor are largely dependent on the safe reliability of the insulation of the reactor windings. The failure of the insulating material due to the fact that the winding temperature exceeds the heat-resistant limit of the insulating material is one of the main reasons for the reactor to work abnormally, so that real-time monitoring, analysis and control of the operating temperature of the reactor are necessary.
Conventional dry reactors, while having an electrified display for monitoring their temperature, still require a worker to manually infer the affected condition of the dry reactor from its temperature change, thereby estimating the remaining life of the dry reactor.
However, this way of inferring is extremely inaccurate and often faces an overwhelming failure of the dry reactor.
Therefore, how to efficiently and accurately detect the life of the reactor is a technical problem to be solved at present.
[ invention ]
The embodiment of the invention provides a method and a device for automatically evaluating the service life of a reactor, aiming at solving the technical problem of inaccurate service life evaluation of the reactor in the related technology.
In a first aspect, an embodiment of the present invention provides a method for automatically evaluating a lifetime of a reactor, including: acquiring working parameters of a reactor; inputting the working parameters of the reactor into a reactor temperature field model, and outputting the temperature distribution information of the reactor through the reactor temperature field model; selecting highest temperature information of the position where the insulating material is located from the temperature distribution information of the reactor; and determining the aging life of the insulating material to which the highest temperature information belongs as the residual life of the reactor.
In the above embodiment of the present invention, the reactor may be a dry reactor.
In the above embodiment of the present invention, optionally, before the step of obtaining the reactor operating parameter, the method further includes: acquiring a training sample, wherein the training sample comprises historical working parameters and historical reactor temperature distribution information corresponding to the historical working parameters; initializing working parameters of an initial reactor temperature field model; inputting the historical working parameters into the initial reactor temperature field model, and outputting predicted reactor temperature distribution information through the initial reactor temperature field model; and adjusting working parameters of the initial reactor temperature field model according to the difference between the predicted reactor temperature distribution information and the historical reactor temperature distribution information to obtain the reactor temperature field model.
In the foregoing embodiment of the present invention, optionally, the step of obtaining an operating parameter of the reactor includes: acquiring working parameters of the reactor at intervals of a first time; storing the working parameters of the reactor to a designated position; the step of inputting the reactor operating parameters into a reactor temperature field model comprises the following steps: and acquiring the working parameters of the reactor stored in the designated position every second time period, wherein the second time period is longer than the first time period.
In the above embodiment of the present invention, optionally, the second duration is an integer multiple of the first duration, the integer being greater than 1.
In the above embodiment of the present invention, optionally, the method further includes: judging whether the residual life of the reactor is smaller than a specified percentage of a predetermined life; and sending out a life shortage early warning based on the condition that the residual life is smaller than the specified percentage of the preset life.
In a second aspect, an embodiment of the present invention provides an automatic assessment device for a lifetime of a reactor, including: the working parameter acquisition unit is used for acquiring working parameters of the reactor; the model calculation unit is used for inputting the working parameters of the reactor into a reactor temperature field model and outputting the temperature distribution information of the reactor through the reactor temperature field model; a maximum temperature selecting unit for selecting maximum temperature information at a position where an insulating material is located from the reactor temperature distribution information; and a remaining life determining unit configured to determine an aged life of the insulating material to which the highest temperature information belongs as a remaining life of the reactor.
In the above embodiment of the present invention, the reactor may be a dry reactor.
In the above embodiment of the present invention, optionally, the method further includes: the sample acquisition unit is used for acquiring a training sample before the working parameter acquisition unit acquires the working parameters of the reactor, wherein the training sample comprises historical working parameters and historical reactor temperature distribution information corresponding to the historical working parameters; the initialization unit is used for initializing working parameters of the initial reactor temperature field model; the model training unit is used for inputting the historical working parameters into the initial reactor temperature field model and outputting predicted reactor temperature distribution information through the initial reactor temperature field model; and the model adjusting unit is used for adjusting the working parameters of the initial reactor temperature field model according to the difference between the predicted reactor temperature distribution information and the historical reactor temperature distribution information to obtain the reactor temperature field model.
In the above embodiment of the present invention, optionally, the operation parameter acquiring unit is configured to: acquiring working parameters of the reactor at intervals of a first time; the model calculation unit is used for: and acquiring the working parameters of the reactor stored in the designated position every second time period, wherein the second time period is longer than the first time period.
In the above embodiment of the present invention, optionally, the second duration is an integer multiple of the first duration, the integer being greater than 1.
In the above embodiment of the present invention, optionally, the method further includes: a judging unit configured to judge whether the remaining life of the reactor is smaller than a specified percentage of a predetermined life; and the life early warning unit is used for sending out life shortage early warning based on the condition that the residual life is smaller than the specified percentage of the preset life.
In a third aspect, an embodiment of the present invention provides an electrical apparatus, including: at least one processor; and a memory communicatively coupled to the at least one processor; wherein the memory stores instructions executable by the at least one processor, the instructions being arranged to perform the method of any of the first aspects above.
In a fourth aspect, embodiments of the present invention provide a computer-readable storage medium storing computer-executable instructions for performing the method flow of any one of the first aspects above.
According to the technical scheme, aiming at the technical problem that the service life evaluation of the reactor in the related technology is inaccurate, the residual service life of the reactor can be automatically detected through the preset reactor temperature field model.
Specifically, the reactor temperature field model can be trained through a large number of training samples, the training samples comprise historical working parameters and historical reactor temperature distribution information corresponding to the historical working parameters, and therefore the trained reactor temperature field model reflects the association relation of the reactor working parameters and the reactor temperature distribution information according to a large number of historical data. Therefore, the reactor operating parameters detected in real time can be input into the reactor temperature field model, and the reactor temperature distribution information at that time can be output through the reactor temperature field model. In the temperature distribution information of the reactor at this time, since the insulating material is most easily damaged, the higher the temperature of the insulating material among the insulating materials is, the greater the damage probability is, and when the insulating material is damaged, the normal operation of the whole reactor is affected, so that the highest temperature information of the position where the insulating material is located, namely, the insulating material with the highest temperature can be selected, and the ageing life of the insulating material is taken as the residual life of the reactor.
Through the technical scheme, the automatic assessment of the service life of the reactor is efficiently and accurately performed, the labor cost and the time cost are reduced, the accuracy and the high efficiency of the assessment of the service life of the reactor are improved, and the efficiency of power work is improved.
[ description of the drawings ]
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings that are needed in the embodiments will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and that other drawings can be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 shows a flow chart of a method for automatically evaluating reactor life according to one embodiment of the invention;
FIG. 2 shows a flow chart of training a reactor temperature field model according to one embodiment of the invention;
fig. 3 shows a flowchart of a reactor life automatic evaluation method according to another embodiment of the present invention;
fig. 4 shows a block diagram of an automatic reactor life assessment apparatus according to an embodiment of the present invention;
fig. 5 shows a block diagram of a power device according to an embodiment of the invention.
[ detailed description ] of the invention
For a better understanding of the technical solution of the present invention, the following detailed description of the embodiments of the present invention refers to the accompanying drawings.
It should be understood that the described embodiments are merely some, but not all, embodiments of the invention. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
The terminology used in the embodiments of the invention is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention. As used in this application and the appended claims, the singular forms "a," "an," and "the" are intended to include the plural forms as well, unless the context clearly indicates otherwise.
Fig. 1 shows a flowchart of a method for automatically evaluating a life of a reactor according to an embodiment of the present invention.
As shown in fig. 1, the flow of the automatic assessment method for the life span of the reactor according to one embodiment of the present invention includes:
The reactor is a dry reactor. The electric power reactors are divided into oil-immersed reactors and dry reactors according to insulating mediums. The dry reactor is gradually replaced with the oil-immersed reactor in the power grid due to the characteristics of simple structure, light weight, no saturation phenomenon and the like, so that the study on the service life characteristic of the dry reactor is necessary. The external insulation of the dry reactor mainly adopts an epoxy resin curing molding process, and the intermittent abnormal heating phenomenon is often generated due to factors such as partial discharge, external environment and the like in operation. Because the service life of the insulating material can be continuously reduced at a higher temperature, the dry-type reactor is extremely easy to generate local aging phenomenon, thereby shortening the service life of the reactor and affecting the safe operation of a power grid. Therefore, it is necessary to evaluate and monitor the remaining life of the dry reactor.
And 104, inputting the working parameters of the reactor into a reactor temperature field model, and outputting the temperature distribution information of the reactor through the reactor temperature field model.
The reactor temperature field model is trained through a large number of training samples, the training samples comprise historical working parameters and historical reactor temperature distribution information corresponding to the historical working parameters, and therefore the trained reactor temperature field model reflects the association relation of the reactor working parameters and the reactor temperature distribution information according to a large number of historical data. Therefore, the reactor operating parameters detected in real time can be input into the reactor temperature field model, and the reactor temperature distribution information at that time can be output through the reactor temperature field model.
And 106, selecting the highest temperature information of the position where the insulating material is located from the temperature distribution information of the reactor.
And step 108, determining the aging life of the insulating material to which the highest temperature information belongs as the residual life of the reactor.
In the temperature distribution information of the reactor at this time, since the insulating material is most easily damaged, the higher the temperature of the insulating material among the insulating materials is, the greater the damage probability is, and when the insulating material is damaged, the normal operation of the whole reactor is affected, so that the highest temperature information of the insulating material at the position, namely the insulating material with the highest temperature, can be selected, and the aging life of the insulating material is taken as the residual life of the reactor.
Aiming at the technical problem of inaccurate life assessment of the reactor in the related art, the residual life of the reactor can be automatically detected through a preset reactor temperature field model. Through the technical scheme, the automatic assessment of the service life of the reactor is efficiently and accurately performed, the labor cost and the time cost are reduced, the accuracy and the high efficiency of the assessment of the service life of the reactor are improved, and the efficiency of power work is improved.
FIG. 2 shows a flow chart of training a reactor temperature field model according to one embodiment of the invention.
As shown in fig. 2, a process of training a reactor temperature field model according to an embodiment of the present invention includes:
The training sample is data based on which the accurate residual life of the reactor is successfully estimated, and comprises a large number of historical working parameters of the reactor and historical reactor temperature distribution information corresponding to the historical working parameters.
And 206, inputting the historical operating parameters into the initial reactor temperature field model, and outputting predicted reactor temperature distribution information through the initial reactor temperature field model.
The predicted reactor temperature distribution information is calculated by an initial reactor temperature field model and is different from the actual historical reactor temperature distribution information, so that the working parameters of the initial reactor temperature field model can be adjusted until the model with the adjusted working parameters can output the historical reactor temperature distribution information.
And step 208, adjusting working parameters of the initial reactor temperature field model according to the difference between the predicted reactor temperature distribution information and the historical reactor temperature distribution information to obtain a reactor temperature field model.
The reactor temperature field model is trained through a large number of training samples, the training samples comprise historical working parameters and historical reactor temperature distribution information corresponding to the historical working parameters, and therefore the trained reactor temperature field model reflects the association relation of the reactor working parameters and the reactor temperature distribution information according to a large number of historical data. Therefore, the reactor operating parameters detected in real time can be input into the reactor temperature field model, and the reactor temperature distribution information at that time can be output through the reactor temperature field model.
Therefore, the service life of the reactor can be automatically and efficiently estimated through the reactor temperature field model, and the efficiency of power operation is improved.
Fig. 3 shows a flowchart of a method for automatically evaluating the life of a reactor according to another embodiment of the present invention.
The first duration may be set according to an actual detection requirement, for example, the first duration is set to be 1min.
And step 304, storing the working parameters of the reactor to a designated position.
And 306, acquiring the working parameters of the reactor stored in the designated position every second time period, wherein the second time period is longer than the first time period.
The second time period may be set according to an actual detection requirement, for example, the first time period is set to 5min, that is, the reactor operating parameters are continuously detected and stored in a designated position, and the reactor operating parameters stored in the designated position are acquired every second time period for calculating the temperature distribution information of the reactor.
Optionally, the second duration is an integer multiple of the first duration, the integer being greater than 1, for example, the integer is set to 5.
And 308, outputting reactor temperature distribution information through the reactor temperature field model.
The reactor temperature field model is trained through a large number of training samples, the training samples comprise historical working parameters and historical reactor temperature distribution information corresponding to the historical working parameters, and therefore the trained reactor temperature field model reflects the association relation of the reactor working parameters and the reactor temperature distribution information according to a large number of historical data. Therefore, the reactor operating parameters detected in real time can be input into the reactor temperature field model, and the reactor temperature distribution information at that time can be output through the reactor temperature field model.
And 310, selecting highest temperature information at the position of the insulating material in the temperature distribution information of the reactor.
And 312, determining the aging life of the insulating material to which the highest temperature information belongs as the residual life of the reactor.
In the temperature distribution information of the reactor at this time, since the insulating material is most easily damaged, the higher the temperature of the insulating material among the insulating materials is, the greater the damage probability is, and when the insulating material is damaged, the normal operation of the whole reactor is affected, so that the highest temperature information of the insulating material at the position, namely the insulating material with the highest temperature, can be selected, and the aging life of the insulating material is taken as the residual life of the reactor.
Aiming at the technical problem of inaccurate life assessment of the reactor in the related art, the residual life of the reactor can be automatically detected through a preset reactor temperature field model. Through the technical scheme, the automatic assessment of the service life of the reactor is efficiently and accurately performed, the labor cost and the time cost are reduced, the accuracy and the high efficiency of the assessment of the service life of the reactor are improved, and the efficiency of power work is improved.
It should be added that, in any of the embodiments shown in fig. 1 to 3, the method further includes: judging whether the residual life of the reactor is smaller than a specified percentage of a predetermined life; and sending out a life shortage early warning based on the condition that the residual life is smaller than the specified percentage of the preset life.
That is, once the remaining life of the reactor is less than a specified percentage of a predetermined life, an insufficient life warning is issued to prompt the worker to perform timely treatment, maintaining stable operation of the power equipment or the power system. The specified percentage may be selected to be 10%.
The internal working process of the reactor temperature field model is specifically described below, and the parameters involved are reactor working parameters.
Because the dry reactor is composed of aluminum wires and surrounding insulating epoxy resin and glass fibers, the total impedance includes the capacitive reactance between turns and layers, the inductive reactance itself, and the impedance when the reactor is in ac operation. Only reactor heating is considered herein, and since capacitive reactance and inductive reactance do not generate heat, only aluminum wire resistance heating conditions, namely direct current resistance loss and eddy current loss, need to be considered.
The formula of the DC resistance loss is as follows:
wherein: q-dc loss; i-the effective value of the current; ρ—resistivity; l-aluminum wire length; s-aluminum wire cross section.
Eddy current losses are mainly caused by skin effects and proximity effects. The skin effect is because the wire generates eddy currents in an alternating magnetic field generated by the wire, so that current approaches the surface of the conductor, and the reduction degree of the effective section is generally expressed by skin depth delta:
wherein: f-frequency; gamma-conductivity; mu-permeability.
The reactor parameters are led into delta about 11.9mm which is far larger than the wire diameter of the aluminum wire by 3.2mm, so that the skin effect is not a main eddy current loss influencing factor.
The proximity effect is that the adjacent conductors induce eddy current to generate heat, which is generally 0.8-1 times of direct current heat generation according to previous researches, and the reactor can effectively reduce eddy current loss by adopting litz wire as a winding, so that 0.8 times of direct current loss is taken as the eddy current loss generated by the proximity effect.
The heat dissipation modes of the reactor which normally works are mainly heat conduction, heat radiation and heat convection. The reactor conductor generates heat and is transmitted to the inner surface and the outer surface of the package through heat conduction, after the surface has a certain temperature, heat radiation can be generated, and the heat radiation quantity meets the Stefan-Boltzmann equation:
wherein: qw—the amount of heat radiation per unit area; epsilon-the gamma of the surface of the object, here taken as 0.9; delta-boltzmann constant; t-object temperature; t infinity-air temperature.
And the periphery of the reactor package can perform heat convection with air at the same time, so that Newton's law of cooling is satisfied:
q＝hΔT
wherein: q-heat flux per unit area; h-convection heat transfer coefficient; delta T-air and packet temperature difference
The convection coefficient h directly reflects the severity of convective heat transfer, which is affected by factors such as object surface size, shape, fluid properties, etc., as discussed below.
When a fluid and a solid having different temperatures are convected through their surfaces, the temperature difference exists only in a thin layer of fluid on the solid surface, which is called a temperature boundary layer. Because the temperature gradient is far greater in the direction perpendicular to the temperature boundary layer than in other directions, and the temperature difference in the areas outside the temperature boundary layer is small, the convection heat transfer model is simplified, only the convection heat transfer of the temperature boundary layer is considered, and the temperature boundary layer is divided into laminar flow and turbulent flow. The primary stage of the heated air flow is laminar flow, namely, no gas diffusion exists between laminar flows, the middle and rear stages are turbulent flow, the gas diffusion exists between the laminar flows, and a short transition layer exists between the two stages.
At the bottom of the reactor, air on the surface of the package expands when being heated, the density of the air is reduced and moves upwards, the thickness of the laminar layer is gradually increased from bottom to top, heat dissipation is more and more difficult, and the convection coefficient h is slowly reduced; turbulent flow in the transition layer is increased, heat dissipation is easy from bottom to top, and the convection coefficient h is slowly increased; the heat dissipation capacity in the turbulent layer is approximately equal, and the convection coefficient h is unchanged. In engineering, a rayleigh criterion is generally used to determine the flow state:
wherein: g-gravitational acceleration; beta-gas expansion coefficient; l-reactor height; v—the kinematic viscosity of air; c-specific heat of air; p-air density; lambda-thermal conductivity of air; t-object temperature; t infinity-air temperature.
Because the transition layer is very short, for simplicity of the model, ra < 109 herein, the boundary layer is in a laminar state; if Ra > 109, the boundary layer is in a turbulent state.
The criterion equation for natural convective heat transfer and the local noose number versus convective heat transfer coefficient summarized by Fujii are used herein when the reactor is in laminar heat transfer:
wherein: nu—nussel number; pr-Plantt number; gr—glatiron correction; z-height.
The three are obtained
In the turbulent layer, according to the empirical formula of churchlin:
a turbulence layer convection coefficient h=4.09 is obtained.
In this context, a third type of boundary condition is chosen in the above heat transfer calculations, i.e. the heat transfer heat at the boundary is equal to the convection heat.
The dry reactor can be divided into a series reactor, a shunt reactor, a current limiting reactor, a filter reactor and the like according to the application, but the working principle and the mechanism of the dry reactor are basically similar, one 35kV shunt reactor is modeled, the density p=2.79×103kg/m3 of an aluminum wire is adopted, the heat conductivity k=164W/(m.k), the reactor height h=1m, the ventilation channel width is 0.032m and the like, the dry reactor is obtained by a formula (1), the heat flow density qw=445W/m 2 of a unit area is set as follows:
1. the current of each winding is equal, 15A is taken here;
2. the eddy current loss is 0.8 times of the direct current loss;
3. the heat generated by a single package uniformly flows through the package and is axially symmetrical;
4. neglecting the heat dissipation of the support, only considering the envelope heat radiation and convection heat transfer
The dry reactor heat transfer equation satisfies the formula:
taking the air temperature of 20 ℃ and the highest temperature in the operation of the reactor at the upper third position of the reactor, the service life loss of the insulating material at the operation temperature at the position is studied to replace the service life loss of the reactor.
The values of a and b at the temperature of the insulating material are shown in the following table:
TABLE 1
The normal life of the dry reactor in actual operation is not less than 180000h. The ageing rate k, i.e. the number of life hours lost per hour of the reactor at constant hot spot temperature T operation, is expressed herein by 180000h as a relatively conservative reference value:
loss of life Lc over a period of time T hours at constant hotspot temperature T:
the life of the dry reactor is evaluated by recording the highest point temperature of the dry reactor in real time and accumulating the life loss of the dry reactor through the heat aging rate.
In one implementation of the invention, the reactor life assessment software is compiled by labview, temperature data is stored in an Excel file every 1 minute, the software reads the Excel file every 5 minutes and carries out life assessment, and a flow chart is shown below. Firstly, reading the latest temperature value, judging whether the temperature exceeds the limit temperature, and immediately and remotely warning if the temperature exceeds the limit temperature; then, calculating the service life loss for 5 minutes at the temperature, and accumulating; and finally, calculating the residual life according to the life of 180000h as a reference value, and carrying out remote early warning when the residual life reaches 10%.
Fig. 4 shows a block diagram of an automatic reactor life assessment apparatus according to an embodiment of the present invention.
As shown in fig. 4, the reactor life automatic evaluation device 400 according to one embodiment of the present invention includes: an operation parameter acquiring unit 402, configured to acquire an operation parameter of the reactor; a model calculation unit 404, configured to input the reactor operating parameter into a reactor temperature field model, and output reactor temperature distribution information through the reactor temperature field model; a maximum temperature selection unit 406 for selecting maximum temperature information at a position where an insulating material is located among the reactor temperature distribution information; a remaining life determining unit 408 for determining an aged life of the insulating material to which the highest temperature information belongs as a remaining life of the reactor.
In the above embodiment of the present invention, the reactor may be a dry reactor.
In the above embodiment of the present invention, optionally, the method further includes: a sample acquiring unit, configured to acquire a training sample before the working parameter acquiring unit 402 acquires the working parameter of the reactor, where the training sample includes a historical working parameter and historical reactor temperature distribution information corresponding to the historical working parameter; the initialization unit is used for initializing working parameters of the initial reactor temperature field model; the model training unit is used for inputting the historical working parameters into the initial reactor temperature field model and outputting predicted reactor temperature distribution information through the initial reactor temperature field model; and the model adjusting unit is used for adjusting the working parameters of the initial reactor temperature field model according to the difference between the predicted reactor temperature distribution information and the historical reactor temperature distribution information to obtain the reactor temperature field model.
In the above embodiment of the present invention, optionally, the operation parameter acquiring unit 402 is configured to: acquiring working parameters of the reactor at intervals of a first time; the model calculation unit 404 is configured to: and acquiring the working parameters of the reactor stored in the designated position every second time period, wherein the second time period is longer than the first time period.
In the above embodiment of the present invention, optionally, the second duration is an integer multiple of the first duration, the integer being greater than 1.
In the above embodiment of the present invention, optionally, the method further includes: a judging unit configured to judge whether the remaining life of the reactor is smaller than a specified percentage of a predetermined life; and the life early warning unit is used for sending out life shortage early warning based on the condition that the residual life is smaller than the specified percentage of the preset life.
The automatic reactor life assessment apparatus 400 uses the solution described in any one of the embodiments shown in fig. 1 and 2, and therefore has all the technical effects described above, and will not be described in detail here.
Fig. 5 shows a block diagram of a power device according to an embodiment of the invention.
As shown in fig. 5, a power device 500 of one embodiment of the present invention includes at least one memory 502; and a processor 504 communicatively coupled to the at least one memory 502; wherein the memory stores instructions executable by the at least one processor 504, the instructions being configured to perform the arrangement of any of the embodiments of fig. 1 and 2 described above. Therefore, the power device 500 has the same technical effects as any one of the embodiments of fig. 1 and 2, and will not be described herein.
In addition, an embodiment of the present invention provides a computer readable storage medium storing computer executable instructions for performing the method flow described in any one of the embodiments of fig. 1 to 3.
The technical scheme of the invention is explained in detail by combining the drawings, through the technical scheme of the invention, the automatic assessment of the service life of the reactor is efficiently and accurately carried out, the labor cost and the time cost are reduced, the accuracy and the high efficiency of the assessment of the service life of the reactor are improved, and the efficiency of electric power work is improved.
It should be understood that the term "and/or" as used herein is merely one relationship describing the association of the associated objects, meaning that there may be three relationships, e.g., a and/or B, may represent: a exists alone, A and B exist together, and B exists alone. In addition, the character "/" herein generally indicates that the front and rear associated objects are an "or" relationship.
Depending on the context, the word "if" as used herein may be interpreted as "at … …" or "at … …" or "in response to a determination" or "in response to detection". Similarly, the phrase "if determined" or "if detected (stated condition or event)" may be interpreted as "when determined" or "in response to determination" or "when detected (stated condition or event)" or "in response to detection (stated condition or event), depending on the context.
In the several embodiments provided by the present invention, it should be understood that the disclosed systems, devices, and methods may be implemented in other manners. For example, the apparatus embodiments described above are merely illustrative, e.g., the division of the elements is merely a logical function division, and there may be additional divisions when actually implemented, e.g., multiple elements or components may be combined or integrated into another system, or some features may be omitted or not performed. Alternatively, the coupling or direct coupling or communication connection shown or discussed with each other may be an indirect coupling or communication connection via some interfaces, devices or units, which may be in electrical, mechanical or other form.
In addition, each functional unit in the embodiments of the present invention may be integrated in one processing unit, or each unit may exist alone physically, or two or more units may be integrated in one unit. The integrated units may be implemented in hardware or in hardware plus software functional units.
The integrated units implemented in the form of software functional units described above may be stored in a computer readable storage medium. The software functional unit is stored in a storage medium, and includes several instructions for causing a computer device (which may be a personal computer, a server, or a network device, etc.) or a Processor (Processor) to perform part of the steps of the methods according to the embodiments of the present invention. And the aforementioned storage medium includes: a U-disk, a removable hard disk, a Read-Only Memory (ROM), a random access Memory (Random Access Memory, RAM), a magnetic disk, or an optical disk, or other various media capable of storing program codes.
The foregoing description of the preferred embodiments of the invention is not intended to be limiting, but rather to enable any modification, equivalent replacement, improvement or the like to be made within the spirit and principles of the invention.
Claims (7)
1. The automatic assessment method for the service life of the reactor is characterized by comprising the following steps:
acquiring working parameters of a reactor;
inputting the working parameters of the reactor into a reactor temperature field model, and outputting the temperature distribution information of the reactor through the reactor temperature field model;
selecting highest temperature information of the position where the insulating material is located from the temperature distribution information of the reactor;
determining the aging life of the insulating material to which the highest temperature information belongs as the residual life of the reactor;
judging whether the residual life of the reactor is smaller than a specified percentage of a predetermined life;
based on the condition that the remaining life is less than the specified percentage of the predetermined life, sending out an insufficient life warning;
before the step of obtaining the working parameters of the reactor, the method further comprises the following steps:
acquiring a training sample, wherein the training sample comprises historical working parameters and historical reactor temperature distribution information corresponding to the historical working parameters;
initializing working parameters of an initial reactor temperature field model;
inputting the historical working parameters into the initial reactor temperature field model, and outputting predicted reactor temperature distribution information through the initial reactor temperature field model;
according to the difference between the predicted reactor temperature distribution information and the historical reactor temperature distribution information, adjusting the working parameters of the initial reactor temperature field model to obtain the reactor temperature field model;
the step of obtaining the working parameters of the reactor comprises the following steps:
acquiring working parameters of the reactor at intervals of a first time;
storing the working parameters of the reactor to a designated position;
the step of inputting the reactor operating parameters into a reactor temperature field model comprises the following steps:
and acquiring the working parameters of the reactor stored in the designated position every second time period, wherein the second time period is longer than the first time period.
2. The method for automatically evaluating the life of a reactor according to claim 1, wherein,
the reactor is a dry reactor.
3. The method for automatically evaluating the life of a reactor according to claim 1, wherein,
the second time period is an integer multiple of the first time period, the integer being greater than 1.
4. An automatic assessment device for the life of a reactor, comprising:
the working parameter acquisition unit is used for acquiring working parameters of the reactor at intervals of a first time; storing the working parameters of the reactor to a designated position;
the model calculation unit is used for inputting the working parameters of the reactor into a reactor temperature field model and outputting the temperature distribution information of the reactor through the reactor temperature field model; acquiring the working parameters of the reactor stored in the designated position every second time period, wherein the second time period is longer than the first time period;
a maximum temperature selecting unit for selecting maximum temperature information at a position where an insulating material is located from the reactor temperature distribution information;
a remaining life determining unit configured to determine an aged life of an insulating material to which the highest temperature information belongs as a remaining life of the reactor;
the sample acquisition unit is used for acquiring a training sample before the working parameter acquisition unit acquires the working parameters of the reactor, wherein the training sample comprises historical working parameters and historical reactor temperature distribution information corresponding to the historical working parameters;
the initialization unit is used for initializing working parameters of the initial reactor temperature field model;
the model training unit is used for inputting the historical working parameters into the initial reactor temperature field model and outputting predicted reactor temperature distribution information through the initial reactor temperature field model;
the model adjusting unit is used for adjusting working parameters of the initial reactor temperature field model according to the difference between the predicted reactor temperature distribution information and the historical reactor temperature distribution information to obtain the reactor temperature field model;
a judging unit configured to judge whether the remaining life of the reactor is smaller than a specified percentage of a predetermined life;
and the life early warning unit is used for sending out life shortage early warning based on the condition that the residual life is smaller than the specified percentage of the preset life.
5. The device for automatically evaluating the life of a reactor according to claim 4, wherein,
the reactor is a dry reactor.
6. An electrical device, comprising: at least one processor; and a memory communicatively coupled to the at least one processor;
wherein the memory stores instructions executable by the at least one processor, the instructions being arranged to perform the method of any of the preceding claims 1 to 3.
7. A computer readable storage medium, characterized in that computer executable instructions for performing the method of any one of claims 1 to 3 are stored.
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