CN111982245B - Main steam flow calibration method, device, computer equipment and storage medium - Google Patents
Main steam flow calibration method, device, computer equipment and storage medium Download PDFInfo
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- CN111982245B CN111982245B CN202010667827.3A CN202010667827A CN111982245B CN 111982245 B CN111982245 B CN 111982245B CN 202010667827 A CN202010667827 A CN 202010667827A CN 111982245 B CN111982245 B CN 111982245B
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01F—MEASURING VOLUME, VOLUME FLOW, MASS FLOW OR LIQUID LEVEL; METERING BY VOLUME
- G01F25/00—Testing or calibration of apparatus for measuring volume, volume flow or liquid level or for metering by volume
- G01F25/10—Testing or calibration of apparatus for measuring volume, volume flow or liquid level or for metering by volume of flowmeters
- G01F25/15—Testing or calibration of apparatus for measuring volume, volume flow or liquid level or for metering by volume of flowmeters specially adapted for gas meters
Abstract
The application relates to a calibration method, a device, computer equipment and a storage medium of main steam flow. The method comprises the following steps: acquiring main steam flow measurement values of a nuclear power station evaporator acquired by at least two main steam flow detection terminals; determining the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value; if the difference value determined by the at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal; and calibrating the main steam flow measured value of the evaporator of the nuclear power station to obtain a main steam flow corrected value of the main steam flow measured value. By adopting the method, whether the main steam flow measured value of the evaporator of the nuclear power station is abnormal or not can be automatically detected, and under the condition that the main steam flow measured value of the evaporator of the nuclear power station is abnormal, the main steam flow measured value is calibrated, so that the measurement accuracy of the main steam flow measured value is improved.
Description
Technical Field
The present disclosure relates to the field of data processing technologies, and in particular, to a method and apparatus for calibrating main steam flow, a computer device, and a storage medium.
Background
The main steam flow measurement is an important process quantity of a reactor control and protection system and plays an important role in a nuclear power station.
However, in the main steam flow measurement, there is a method of obtaining the main steam flow of the evaporator of the nuclear power plant by measurement with a measuring instrument; however, in the process of measuring the main steam flow, the measuring instrument may have reasons such as drift, fault or failure, so that the measured main steam flow is inaccurate and cannot be calibrated, and thus the accuracy of the measured main steam flow is low.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a main steam flow calibration method, apparatus, computer device, and storage medium that can improve the accuracy of measurement of the main steam flow.
A method of calibrating primary steam flow, the method comprising:
acquiring main steam flow measurement values of a nuclear power station evaporator acquired by at least two main steam flow detection terminals;
determining the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value;
If the difference value determined by at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal;
and calibrating the main steam flow measured value of the evaporator of the nuclear power station to obtain a main steam flow corrected value of the main steam flow measured value.
In one embodiment, before confirming that there is an abnormality in the primary steam flow measurement value of the evaporator of the nuclear power station if the difference value determined by at least one primary steam flow detection terminal meets a preset condition, the method further includes:
obtaining a main steam flow difference standard value of each main steam flow detection terminal;
and if the difference value determined by at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal, including:
and if the absolute value of the difference value determined by at least one main steam flow detection terminal is larger than the corresponding main steam flow difference value standard value, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal.
In one embodiment, the obtaining a main steam flow difference standard value of each main steam flow detection terminal includes:
Acquiring a first measurement uncertainty and a second measurement uncertainty of each main steam flow detection terminal;
and respectively inputting the first measurement uncertainty and the second measurement uncertainty of each main steam flow detection terminal into a main steam flow difference value standard value statistical model to obtain a main steam flow difference value standard value of each main steam flow detection terminal.
In one embodiment, after determining the difference between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value, the method further includes:
and if the absolute values of the differences determined by the main steam flow detection terminals are smaller than or equal to the corresponding main steam flow difference standard values, confirming that the main steam flow measured values of the evaporator of the nuclear power station are normal.
In one embodiment, before determining the difference between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value, the method further includes:
acquiring main steam temperature, main steam pressure and fluid pressure difference before and after a pore plate of the evaporator of the nuclear power station when the main steam flow measurement value is acquired through the main steam flow detection terminal;
And counting according to the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the nuclear power station evaporator to obtain a heat balance flow value of the nuclear power station evaporator, wherein the heat balance flow value is used as a main steam flow reference value corresponding to the main steam flow measurement value.
In one embodiment, the calibrating the main steam flow measurement value of the evaporator of the nuclear power plant to obtain a main steam flow correction value of the main steam flow measurement value includes:
acquiring the switching quantity of a water level valve of the evaporator of the nuclear power station;
and taking the sum of the water level valve switching amount of the nuclear power station evaporator and a main steam flow reference value corresponding to the main steam flow measurement value as a main steam flow correction value of the main steam flow measurement value of the nuclear power station evaporator.
In one embodiment, the method further comprises:
acquiring a main steam flow differential pressure measurement value of the evaporator of the nuclear power station;
and counting to obtain the main steam flow differential pressure correction value of the nuclear power station evaporator according to the main steam flow differential pressure measurement value, the main steam flow measurement value and the main steam flow correction value of the nuclear power station evaporator.
A primary steam flow calibration apparatus, the apparatus comprising:
the measured value acquisition module is used for acquiring main steam flow measured values of the evaporator of the nuclear power station acquired by the at least two main steam flow detection terminals;
the difference value determining module is used for determining the difference value between the main steam flow measured value acquired by each main steam flow detecting terminal and the corresponding main steam flow reference value;
the abnormality detection module is used for confirming that the measured value of the main steam flow of the evaporator of the nuclear power station is abnormal if the difference value determined by at least one main steam flow detection terminal meets a preset condition;
and the measured value calibration module is used for calibrating the main steam flow measured value of the evaporator of the nuclear power station to obtain a main steam flow corrected value of the main steam flow measured value.
A computer device comprising a memory storing a computer program and a processor which when executing the computer program performs the steps of:
acquiring main steam flow measurement values of a nuclear power station evaporator acquired by at least two main steam flow detection terminals;
determining the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value;
If the difference value determined by at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal;
and calibrating the main steam flow measured value of the evaporator of the nuclear power station to obtain a main steam flow corrected value of the main steam flow measured value.
A computer readable storage medium having stored thereon a computer program which when executed by a processor performs the steps of:
acquiring main steam flow measurement values of a nuclear power station evaporator acquired by at least two main steam flow detection terminals;
determining the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value;
if the difference value determined by at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal;
and calibrating the main steam flow measured value of the evaporator of the nuclear power station to obtain a main steam flow corrected value of the main steam flow measured value.
According to the calibration method, the calibration device, the computer equipment and the storage medium of the main steam flow, the main steam flow measured value of the evaporator of the nuclear power station acquired by at least two main steam flow detection terminals is acquired, and the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value is determined; then, if the difference value determined by at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal; finally, calibrating a main steam flow measured value of the evaporator of the nuclear power station to obtain a main steam flow corrected value of the main steam flow measured value; the difference value between the main steam flow measurement value and the corresponding main steam flow reference value is used for confirming whether the main steam flow measurement value is abnormal, so that the purpose of automatically detecting whether the main steam flow measurement value is abnormal is realized, the defect that the accuracy of the main steam flow measurement value obtained by measurement is low due to the fact that the traditional method cannot carry out self-diagnosis is overcome, and the measurement accuracy of the main steam flow measurement value is improved; meanwhile, under the condition that the main steam flow measured value of the evaporator of the nuclear power station is abnormal, the main steam flow measured value of the evaporator of the nuclear power station is automatically calibrated, and the measurement accuracy of the main steam flow measured value is further improved.
Drawings
FIG. 1 is an application environment diagram of a method of calibrating primary steam flow in one embodiment;
FIG. 2 is a flow chart of a method of calibrating main steam flow in one embodiment;
FIG. 3 is a graph of measured flow values for different power platforms in one embodiment;
FIG. 4 is a logic diagram of a main steam flow measurement correction or not judgment logic model according to an embodiment;
FIG. 5 is a logic diagram of calculation of uncertainty propagation and fault probability distribution models in one embodiment;
FIG. 6 is a computational logic diagram of a thermal equilibrium flow calculation model in one embodiment;
FIG. 7 is a flow diagram of a correction to primary steam flow differential pressure measurements in one embodiment;
FIG. 8 is a graph illustrating correction of primary steam flow differential pressure measurements for different power platforms for the same measurement accuracy in one embodiment;
FIG. 9 is a flow chart of a method of calibrating main steam flow in another embodiment;
FIG. 10 is a block diagram of a primary steam flow calibration apparatus in one embodiment;
FIG. 11 is an internal block diagram of a computer device in one embodiment.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application will be further described in detail with reference to the accompanying drawings and examples. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the present application.
The calibration method of the main steam flow can be applied to an application environment shown in fig. 1. Wherein the primary steam flow sensing terminal 110 (e.g., 110a, 110b, 110 c) communicates with the server 120 via a network. The main steam flow detection terminal 110 is connected with the nuclear power plant evaporator 130, and is used for collecting a main steam flow measurement value of the nuclear power plant evaporator 130 and uploading the main steam flow measurement value of the nuclear power plant evaporator 130 to the server 120; the server 120 acquires main steam flow measurement values of the nuclear power station evaporator 130 acquired by the at least two main steam flow detection terminals 110; determining the difference value between the main steam flow measured value acquired by each main steam flow detection terminal 110 and the corresponding main steam flow reference value; if the difference value determined by the at least one main steam flow detection terminal 110 meets a preset condition, confirming that the main steam flow measured value of the nuclear power station evaporator 130 is abnormal; and calibrating the main steam flow measured value of the evaporator of the nuclear power station to obtain a main steam flow corrected value of the main steam flow measured value.
The main steam flow detection terminal 110 refers to a detection device for main steam flow of a nuclear power plant evaporator, specifically refers to a power platform of the nuclear power plant evaporator 130, and is used for judging a deviation result of a main steam flow measurement value of the nuclear power plant evaporator 130; the server 120 may be implemented as a stand-alone server or a server cluster composed of a plurality of servers; the nuclear power plant evaporator 130 is a steam generator of a nuclear power plant, which is a heat exchange device for generating steam required by a steam turbine, and in the nuclear reactor, heat generated by nuclear fission is carried out by a coolant, and is transferred to a two-circuit working medium through the steam generator, so that the steam with a certain temperature, a certain pressure and a certain dryness is generated.
In one embodiment, as shown in fig. 2, a calibration method for main steam flow is provided, and the method is applied to the server in fig. 1 for illustration, and includes the following steps:
step S201, main steam flow measurement values of the nuclear power station evaporator acquired by at least two main steam flow detection terminals are acquired.
The main steam flow detection terminal is used for collecting main steam flow measurement values of the evaporator of the nuclear power station, and can refer to a power platform terminal of the evaporator of the nuclear power station, specifically, a low-power platform terminal, a high-power platform terminal and the like.
It should be noted that, at least two main steam flow detection terminals refer to two or more main steam flow detection terminals, and specifically may refer to two or more power platform terminals.
Specifically, a main steam flow detection terminal collects a main steam flow measurement value of a nuclear power station evaporator, and uploads the collected main steam flow measurement value of the nuclear power station evaporator to a corresponding server; and acquiring main steam flow measurement values of the evaporator of the nuclear power station acquired by at least two main steam flow detection terminals through a server. Thus, the method is favorable for combining the main steam flow reference value subsequently and identifying whether the main steam flow measured value of the evaporator of the nuclear power station acquired by the main steam flow detection terminal is abnormal or not; meanwhile, the purpose of remotely acquiring the main steam flow measurement value of the evaporator of the nuclear power station is achieved.
Of course, the server may also obtain the main steam flow measurement values of the nuclear power plant evaporator acquired by the at least two main steam flow detection terminals from the local database.
Further, the server can also acquire main steam flow measurement values of the evaporator of the nuclear power station acquired by at least two main steam flow detection terminals according to preset frequency; thus, the purpose of periodically detecting the main steam flow measured value of the evaporator of the nuclear power station is achieved.
Step S202, determining a difference value between the main steam flow measured value acquired by each main steam flow detection terminal and a corresponding main steam flow reference value.
The main steam flow reference value refers to a reference standard value of a main steam flow measured value; in the ideal case, the actual flow rate of the main steam of the evaporator of the nuclear power plant is taken as the reference value of the main steam flow rate, but in the actual case, the actual flow rate of the main steam of the evaporator of the nuclear power plant is difficult to obtain, so that the main steam flow rate (such as the thermal balance flow rate value) measured by the higher-precision measuring instrument is approximate to the actual flow rate of the main steam, and is taken as the reference value of the main steam flow rate.
Specifically, when the server acquires the main steam flow measurement value of the evaporator of the nuclear power station by acquiring the main steam flow measurement value of each main steam flow detection terminal, the main steam flow reference value of the evaporator of the nuclear power station is used as the main steam flow reference value corresponding to the main steam flow measurement value of the evaporator of the nuclear power station; and counting the difference between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value according to a preset difference counting instruction. Therefore, whether the main steam flow measured value of the evaporator of the nuclear power station is abnormal or not is determined according to the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value, and the purpose of automatically detecting whether the main steam flow measured value is abnormal or not is achieved.
Of course, the server may also obtain, from the local database, the main steam flow reference value of the nuclear power plant evaporator as the main steam flow reference value corresponding to the main steam flow measurement value of the nuclear power plant evaporator when the main steam flow measurement values of the nuclear power plant evaporator are acquired by each main steam flow detection terminal.
Step S203, if the difference value determined by at least one main steam flow detection terminal meets the preset condition, determining that the main steam flow measurement value of the evaporator of the nuclear power station is abnormal.
The difference value determined by the main steam flow detection terminal meets a preset condition, namely the difference value between the main steam flow measured value acquired by the water flow detection terminal and the corresponding main steam flow reference value is larger; in addition, if the difference between the main steam flow measured value acquired by the water flow detection terminal and the corresponding main steam flow reference value is larger, the deviation degree between the main steam flow measured value and the corresponding main steam flow reference value is larger, and the main steam flow reference value is approximately equal to the real main steam flow, so that the accuracy of the main steam flow measured value acquired by measurement is lower, and the main steam flow measured value needs to be calibrated.
It should be noted that at least one main steam flow detection terminal refers to one or more main steam flow detection terminals, and specifically may refer to one or more power platform terminals.
Specifically, the server compares the difference value determined by the main steam flow detection terminals with a corresponding threshold value, and if the difference value determined by at least one main steam flow detection terminal is greater than the corresponding threshold value, it is confirmed that the difference value determined by at least one main steam flow detection terminal meets a preset condition; and if the difference value determined by the at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal. Therefore, whether the main steam flow measured value is abnormal or not is confirmed through the difference value between the main steam flow measured value and the corresponding main steam flow reference value, the purpose of automatically detecting whether the main steam flow measured value is abnormal or not is achieved, and the defect that the accuracy of the main steam flow measured value obtained by measurement is low due to the fact that the traditional method cannot conduct self-diagnosis is overcome.
Step S204, the main steam flow measured value of the evaporator of the nuclear power station is calibrated, and a main steam flow corrected value of the main steam flow measured value is obtained.
The main steam flow correction value of the main steam flow measurement value refers to the corrected main steam flow measurement value.
Specifically, after confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal, the server can also obtain a preset measured value calibration instruction from the local database, calibrate the main steam flow measured value of the evaporator of the nuclear power station through the preset measured value calibration instruction, and obtain a calibrated main steam flow measured value as a main steam flow correction value of the main steam flow measured value. Therefore, under the condition that the main steam flow measured value of the evaporator of the nuclear power station is abnormal, the accuracy of the finally obtained main steam flow measured value is improved by calibrating the main steam flow measured value, and the measurement accuracy of the main steam flow measured value is further improved.
Further, the server may further input the main steam flow measurement value of the nuclear power plant evaporator into a pre-trained measurement value calibration model, and calibrate the main steam flow measurement value of the nuclear power plant evaporator through the pre-trained measurement value calibration model to obtain a main steam flow correction value of the main steam flow measurement value.
In the calibration method of the main steam flow, the main steam flow measured value of the nuclear power station evaporator acquired by at least two main steam flow detection terminals is acquired, and the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value is determined; then, if the difference value determined by at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal; finally, calibrating a main steam flow measured value of the evaporator of the nuclear power station to obtain a main steam flow corrected value of the main steam flow measured value; the difference value between the main steam flow measurement value and the corresponding main steam flow reference value is used for confirming whether the main steam flow measurement value is abnormal, so that the purpose of automatically detecting whether the main steam flow measurement value is abnormal is realized, the defect that the accuracy of the main steam flow measurement value obtained by measurement is low due to the fact that the traditional method cannot carry out self-diagnosis is overcome, and the measurement accuracy of the main steam flow measurement value is improved; meanwhile, under the condition that the main steam flow measured value of the evaporator of the nuclear power station is abnormal, the main steam flow measured value of the evaporator of the nuclear power station is automatically calibrated, and the measurement accuracy of the main steam flow measured value is further improved.
In one embodiment, the step S203 further includes, before determining that there is an abnormality in the primary steam flow measurement value of the evaporator of the nuclear power plant if the difference value determined by the at least one primary steam flow detection terminal meets the preset condition: acquiring a main steam flow difference standard value of each main steam flow detection terminal; if the difference value determined by the at least one main steam flow detection terminal meets the preset condition, the step S203 confirms that the main steam flow measurement value of the evaporator of the nuclear power station is abnormal, which specifically includes the following steps: and if the absolute value of the difference value determined by the at least one main steam flow detection terminal is larger than the corresponding main steam flow difference value standard value, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal.
The main steam flow difference standard value refers to a reference value of a main steam flow difference value, and different main steam flow detection terminals correspond to different main steam flow difference value standard values; in an actual scene, main steam flow difference standard values corresponding to different power platform terminals are different.
Specifically, the server obtains terminal identifiers of all the main steam flow detection terminals, queries a database storing main steam flow difference value standard values corresponding to a plurality of terminal identifiers according to the terminal identifiers of all the main steam flow detection terminals, obtains the main steam flow difference value standard values corresponding to the terminal identifiers of all the main steam flow detection terminals, and corresponds to the main steam flow difference value standard values serving as all the main steam flow detection terminals; respectively acquiring absolute values of the differences determined by the main steam flow detection terminals, and comparing the absolute values of the differences determined by the main steam flow detection terminals with corresponding main steam flow difference standard values; if the absolute value of the difference value determined by the at least one main steam flow detection terminal is larger than the corresponding main steam flow difference value standard value, the deviation degree between the main steam flow measured value acquired by the main steam flow detection terminal and the corresponding main steam flow reference value is larger, and the main steam flow measured value of the evaporator of the nuclear power station is confirmed to be abnormal.
For example, a multi-power platform verification method is adopted to judge whether the main steam flow measured value of the evaporator of the nuclear power station is abnormal, as shown in fig. 3, the abscissa is the number of the power platform, the ordinate is the main steam flow value, and the main steam flow value comprises a real-time flow value (i.e. the main steam flow measured value) and a heat balance flow value (i.e. the main steam flow reference value); the five power platforms A, B, C, D, E are selected respectively, and the real-time flow value Q and the heat balance flow are calculatedMagnitude Q e Performing difference operation and simultaneously comparing the difference operation with a corresponding judgment standard value (namely a main steam flow difference standard value) C; if the judging results of the power platforms are all qualified, the final result is qualified without correction, otherwise, the main steam flow measured value of the evaporator of the nuclear power station is required to be corrected.
The deviation judging method and the deviation judging process are as follows:
for A power platform, if |Q A -Q eA |＞C A L is then A =0; if |Q A -Q eA |≤C A L is then A ＝1；
For the B power platform, if |Q B -Q eB |＞C B L is then B =0; if |Q B -Q eB |≤C B L is then B ＝1；
For C power platform, if |Q C -Q eC |＞C C L is then C =0; if |Q C -Q eC |≤C C L is then C ＝1；
For D power platform, if |Q D -Q eD |＞C D L is then D =0; if |Q D -Q eD |≤C D L is then D ＝1；
For E power platform, if |Q E -Q eE |＞C E L is then E =0; if |Q E -Q eE |≤C E L is then E ＝1；
If L A =0, which indicates that the judging result of the power platform a is unqualified, that is, the deviation degree between the main steam flow measured value and the corresponding main steam flow reference value is larger, and the main steam flow measured value is abnormal; if L A And (1) indicating that the judging result of the power platform a is qualified, namely, the deviation degree between the main steam flow measured value and the corresponding main steam flow reference value is smaller, namely, the main steam flow measured value is not abnormal.
The specific correction or non-correction judgment logic refers to the correction or non-correction judgment logic model shown in fig. 4, and the judgment logic of the correction or non-correction judgment logic model is as follows: l=L A &L B &L C &L D &L E The method comprises the steps of carrying out a first treatment on the surface of the Inputting the judging result of the A power platform, the judging result of the B power platform, the judging result of the C power platform, the judging result of the D power platform and the judging result of the E power platform into a corrected judging logic model, and if only one judging result of the power platform is unqualified (namely, the judging result is 0), the final result L=0, indicating that the main steam flow measured value of the evaporator of the nuclear power station is abnormal, and correcting the main steam flow measured value of the evaporator of the nuclear power station; if the judging results of all the power platforms are qualified (i.e., the judging result is 1), the final result l=1, which indicates that the main steam flow measured value of the evaporator of the nuclear power plant is not abnormal, and the main steam flow measured value of the evaporator of the nuclear power plant is not required to be corrected.
In this embodiment, by acquiring the main steam flow difference standard value of each main steam flow detection terminal and comparing the absolute value of the difference value determined by each main steam flow detection terminal with the corresponding main steam flow difference standard value, it is beneficial to accurately confirm whether the main steam flow measured value of the evaporator of the nuclear power station is abnormal, thereby achieving the purpose of automatically detecting whether the main steam flow measured value of the evaporator of the nuclear power station is abnormal.
In one embodiment, the step S202 further includes, after determining the difference between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value: and if the absolute value of the difference value determined by each main steam flow detection terminal is smaller than or equal to the corresponding main steam flow difference value standard value, confirming that the main steam flow measured value of the evaporator of the nuclear power station is normal.
Specifically, the server acquires absolute values of differences determined by the main steam flow detection terminals, and compares the absolute values of the differences determined by the main steam flow detection terminals with corresponding main steam flow difference standard values respectively; if the absolute value of the difference value determined by each main steam flow detection terminal is smaller than or equal to the corresponding main steam flow difference value standard value, the deviation degree between the main steam flow measured value acquired by the main steam flow detection terminal and the corresponding main steam flow reference value is smaller, and the main steam flow measured value of the evaporator of the nuclear power station is confirmed to be normal, and the main steam flow measured value of the evaporator of the nuclear power station is not required to be corrected.
In this embodiment, whether the main steam flow measured value is abnormal or not is confirmed by the difference value between the main steam flow measured value and the corresponding main steam flow reference value, so that the purpose of automatically detecting whether the main steam flow measured value is abnormal or not is achieved, and the defect that the accuracy of the main steam flow measured value obtained by measurement is low due to the fact that the traditional method cannot perform self-diagnosis is overcome.
In one embodiment, obtaining a primary steam flow difference value standard value for each primary steam flow detection terminal includes: acquiring a first measurement uncertainty and a second measurement uncertainty of each main steam flow detection terminal; and respectively inputting the first measurement uncertainty and the second measurement uncertainty of each main steam flow detection terminal into a main steam flow difference value standard value statistical model to obtain the main steam flow difference value standard value of each main steam flow detection terminal.
Wherein the first measurement uncertainty refers to a density measurement uncertainty; the second measurement uncertainty refers to differential pressure measurement uncertainty; different main steam flow detection terminals, corresponding first measurement uncertainty and second measurement uncertainty are different.
The main steam flow difference value standard value statistical model refers to a statistical model capable of statistically obtaining a main steam flow difference value standard value of a main steam flow detection terminal according to different measurement uncertainty of the main steam flow detection terminal, and specifically may refer to an uncertainty propagation rate and fault probability distribution model.
Specifically, the server acquires a terminal identifier of the main steam flow detection terminal, queries a database storing measurement uncertainties corresponding to a plurality of terminal identifiers according to the terminal identifier of the main steam flow detection terminal, and obtains a first measurement uncertainty and a second measurement uncertainty corresponding to the terminal identifier of the main steam flow detection terminal as the corresponding first measurement uncertainty and second measurement uncertainty of the main steam flow detection terminal; inputting the corresponding first measurement uncertainty and second measurement uncertainty of the main steam flow detection terminal into a main steam flow difference value standard value statistical model to obtain a main steam flow difference value standard value of the main steam flow detection terminal; with the method, the main steam flow difference standard value of each main steam flow detection terminal can be obtained.
For example, the main steam flow difference standard value of the main steam flow detection terminal can be calculated by using an uncertainty propagation rate and fault probability distribution model as shown in fig. 5, and the measurement uncertainty of the main steam flow detection terminal mainly comprises two parts, namely, a density measurement uncertainty and a differential pressure measurement uncertainty.
The main steam flow measurement and differential pressure correspond to:where k is a coefficient and ΔP is the measured differential pressure; according to the corresponding relation between the main steam flow measurement value and the differential pressure, obtaining:
wherein ρ is the main vapor fluid density, ΔP M The differential steam pressure range value is the differential steam pressure range value, delta P is the differential steam pressure value, and Q is the real-time value of the steam flow.
For the uncertainty of the density measurement,the effect of vapor density on vapor mass flow is large, so uncertainty in the density measurement needs to be calculated. Because the steam flow channel of a nuclear power plant operates at a working condition of 65bar to 75bar, the relation between the steam density and the steam pressure is as follows: ρ=0.58P-4.25 ρ AVG ＝36.6kg/m 3 Therefore:
for the measurement uncertainty of the differential pressure,wherein λ is the differential pressure measurement uncertainty coefficient, +.>
Finally, the server inputs the uncertainty of the two parts into an uncertainty propagation rate and fault probability distribution model shown in fig. 5, and calculates main steam flow difference standard values C of different power platforms through the uncertainty propagation rate and the fault probability distribution model:
in this embodiment, by calculating the main steam flow difference standard value of each main steam flow detection terminal, it is beneficial to compare the absolute value of the difference value determined by each main steam flow detection terminal with the corresponding main steam flow difference standard value, so as to confirm whether the main steam flow measured value of the evaporator of the nuclear power station is abnormal, overcome the defect that the accuracy of the main steam flow measured value obtained by measurement is lower due to the fact that the conventional method cannot perform self-diagnosis, and further improve the measurement accuracy of the main steam flow measured value.
In one embodiment, the step S202, before determining the difference between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value, further includes: acquiring main steam temperature, main steam pressure and fluid pressure difference before and after a pore plate of an evaporator of a nuclear power station when main steam flow measurement values are acquired through a main steam flow detection terminal; and counting according to the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the evaporator of the nuclear power station to obtain a heat balance flow value of the evaporator of the nuclear power station, and taking the heat balance flow value as a main steam flow reference value corresponding to the main steam flow measurement value.
The front-back fluid pressure difference of the orifice plate refers to the front-back fluid pressure difference of a high-precision orifice plate arranged at the inlet of the evaporator of the nuclear power station; the heat balance flow value of the evaporator of the nuclear power station is close to the real flow value of the main steam of the evaporator of the nuclear power station, so the heat balance flow value of the evaporator of the nuclear power station is used as a main steam flow reference value corresponding to the main steam flow measurement value.
Specifically, when a main steam flow measurement value is acquired through a main steam flow detection terminal, a server acquires a main steam temperature, a main steam pressure and a fluid pressure difference between the front and the back of a high-precision orifice plate acquired by a high-precision orifice plate installed at an inlet of the evaporator of the nuclear power plant; calculating to obtain the fluid density before and after the orifice plate based on the main steam temperature and the main steam pressure of the evaporator of the nuclear power station according to a preset fluid density calculation instruction; and calculating a heat balance flow value of the evaporator of the nuclear power station based on the fluid density and the pressure difference of the fluid before and after the orifice plate according to a preset heat balance flow value calculation instruction, and taking the heat balance flow value as a main steam flow reference value corresponding to a main steam flow measurement value.
For example, a high-precision orifice plate is installed at the inlet of the steam generator of the nuclear power station, the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the evaporator of the nuclear power station are acquired through the high-precision orifice plate, the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the evaporator of the nuclear power station are input into a thermal balance flow calculation model shown in fig. 6, and a thermal balance flow value is calculated; specifically, the heat balance flow value Q e The method comprises the steps of measuring by a high-precision orifice plate flowmeter, measuring by the high-precision orifice plate flowmeter to obtain the front-back fluid pressure difference and the fluid density of an orifice plate of a nuclear power station evaporator, and calculating the main steam flow by the fluid density and the front-back fluid pressure difference of the orifice plate; the fluid density is calculated from the measured main steam pressure and main steam temperature; considering the orifice plate cross-sectional area, a specific calculation formula of the heat balance flow value can be obtained:
wherein C is the outflow coefficient (dimensionless), and E is the progressive velocity coefficient (dimensionless): e=1/(1- β) 4 ) 1/2 Beta is the diameter ratio (dimensionless): beta = D/D; d is the diameter (m) of the orifice plate under the operating condition, and D is the diameter (m) of the circular section of the conduit under the operating condition; it should be noted that D and D should be modified by the expansion factor of the sheet and tube; epsilon is the expansion factor (dimensionless) of the fluid, incompressible fluid epsilon=1; ρ r Fluid density (kg/m 3) upstream of the device; ΔP r Is the pressure difference (Pa); alpha is the flow coefficient (dimensionless).
In this embodiment, by obtaining the main steam flow reference value corresponding to the main steam flow measurement value, it is beneficial to determine the difference between the main steam flow measurement value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value.
In one embodiment, the step S204 is performed to calibrate the main steam flow measurement value of the evaporator of the nuclear power plant to obtain a main steam flow correction value of the main steam flow measurement value, and includes: acquiring the switching quantity of a water level valve of an evaporator of the nuclear power station; and taking the sum of the water level valve switching value of the nuclear power station evaporator and the main steam flow reference value corresponding to the main steam flow measured value as a main steam flow correction value of the main steam flow measured value of the nuclear power station evaporator.
The switching amount of the water level valve of the evaporator of the nuclear power station refers to the switching amount of a large valve and a small valve of a water level control system of the evaporator of the nuclear power station.
Specifically, after confirming that the measured value of the main steam flow of the evaporator of the nuclear power station is abnormal, the server acquires the switching value of a water level valve of the evaporator of the nuclear power station and a main steam flow reference value corresponding to the measured value of the main steam flow; and adding the water level valve switching value of the nuclear power station evaporator and the main steam flow reference value corresponding to the main steam flow measured value to obtain a main steam flow corrected value of the main steam flow measured value of the nuclear power station evaporator.
For example, the main steam flow measurement Q of a full power platform r Theoretically, the heat balance flow value (i.e. main steam) at the time of judging standard full powerFlow reference value) Q er Equal but actually due to measurement bias Q r ≠Q er So the correction satisfies the condition that Q is realized r ＝Q er The method comprises the steps of carrying out a first treatment on the surface of the In the actual process, the real-time flow measurement Q of the main steam is often considered r The influence on the switching of the big valve and the small valve of the evaporator water level control system ensures the smooth switching of the big valve and the small valve, so that a switching quantity Q is increased on the basis of the original heat balance flow value a So the correction satisfies the condition that Q is realized r ＝Q er +Q a And then obtaining a main steam flow correction value Q of the main steam flow measured value of the evaporator of the nuclear power station r ＝Q er +Q a 。
In this embodiment, under the condition that it is confirmed that the main steam flow measurement value of the nuclear power plant evaporator is abnormal, the main steam flow measurement value of the nuclear power plant evaporator is corrected, which is favorable for improving the accuracy of the finally obtained main steam flow measurement value of the nuclear power plant evaporator, and further improving the measurement accuracy of the main steam flow measurement value.
In one embodiment, the method of calibrating the main steam flow further comprises: acquiring a main steam flow differential pressure measurement value of an evaporator of a nuclear power station; and counting to obtain the main steam flow differential pressure correction value of the evaporator of the nuclear power station according to the main steam flow differential pressure measurement value, the main steam flow measurement value and the main steam flow correction value of the evaporator of the nuclear power station.
The main steam flow differential pressure correction value refers to a corrected main steam flow differential pressure measurement value.
Specifically, the server acquires a ratio between a main steam flow measurement value and a main steam flow correction value as a first ratio; obtaining the square of the first ratio as a second ratio; and acquiring the acquired main steam flow differential pressure measured value of the evaporator of the nuclear power station, and calculating the product of the second ratio and the main steam flow differential pressure measured value to be used as a main steam flow differential pressure corrected value of the evaporator of the nuclear power station.
For example, the main steam measurement differential pressure correction model and method adopts a full-power main steam flow reference standard coincidence method, namely differential pressure value is calculated on a full-power platformCorrecting until the main steam differential pressure measurement range value is equal to the reference standard value, and further obtaining a corrected main steam differential pressure measurement range value; the specific main steam flow differential pressure correction method and model are shown in FIG. 7; main steam flow measurement Q of full power platform r Theoretically and judging the heat balance flow value (namely the main steam flow reference value) Q at the standard full power er Equal but actually due to measurement bias Q r ≠Q er So the correction satisfies the condition that Q is realized r ＝Q er The method comprises the steps of carrying out a first treatment on the surface of the In the actual process, the real-time flow measurement Q of the main steam is often considered r The influence on the switching of the big valve and the small valve of the evaporator water level control system ensures the smooth switching of the big valve and the small valve, so that a switching quantity Q is increased on the basis of the original heat balance flow value a The correction satisfies the condition: q (Q) r ＝Q er +Q a 。
At the same time Q r And Q er All representing mass flow, due to the main steam flow measuring real time value Q r For main steam pressure P v Is sensitive, so the main steam flow measurement real-time value Q r Is a value corrected by the main steam pressure. Corrected coefficient and main steam pressure P v There is a correlation, so at a known primary steam flow measurement real time value Q r Solving for the main vapor flow differential compaction values ΔP r When the main steam pressure P needs to be considered v Is a function of (a) and (b).
Main steam pressure correction coefficientWith main steam pressure P v The relation of (2) is: />
Taking into account the main steam pressure P v Corrected full power main steam flow measurement real time value Q r ：
The actual full power main steam differential pressure real-time value occupies the percentage of the full range:
the percentage of the theoretical full power main vapor differential compaction time value to full scale is:
solving corrected main steam flow differential pressure measurement range value delta P M '：
Meanwhile, because the correction accuracy of the low-power platform is lower under the same precision, the correction of other low-power platforms should be avoided as much as possible. Comparing the error amount of the 50% power stage correction with the error amount of the 100% power stage correction with the same measurement accuracy, it can be found that the error amount range of the 50% power stage correction is larger, as shown in fig. 8.
In this embodiment, by correcting the main steam flow differential pressure measurement value of the evaporator of the nuclear power station, the accuracy of the final main steam flow differential pressure measurement value is improved, and the measurement accuracy of the main steam flow differential pressure measurement value is further improved.
In one embodiment, as shown in fig. 9, another calibration method for main steam flow is provided, and the method is applied to the server in fig. 1 for illustration, and includes the following steps:
step S901, obtaining main steam flow measurement values of a nuclear power station evaporator acquired by at least two main steam flow detection terminals.
Step S902, obtaining a main steam temperature, a main steam pressure and a fluid pressure difference between the front and rear sides of the orifice plate of the evaporator of the nuclear power station when the main steam flow measurement value is acquired through the main steam flow detection terminal.
In step S903, the heat balance flow value of the evaporator of the nuclear power plant is obtained by statistics according to the main steam temperature, the main steam pressure and the fluid pressure difference between the front and back of the orifice plate of the evaporator of the nuclear power plant, and is used as the main steam flow reference value corresponding to the main steam flow measurement value.
Step S904, determining a difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value.
In step S905, the first measurement uncertainty and the second measurement uncertainty of each main steam flow detection terminal are acquired.
Step S906, the first measurement uncertainty and the second measurement uncertainty of each main steam flow detection terminal are respectively input into a main steam flow difference value standard value statistical model to obtain a main steam flow difference value standard value of each main steam flow detection terminal.
In step S907, if the absolute value of the difference value determined by the at least one main steam flow detection terminal is greater than the corresponding main steam flow difference standard value, it is determined that there is an abnormality in the main steam flow measurement value of the evaporator of the nuclear power station.
Step S908, acquiring the switching quantity of a water level valve of an evaporator of the nuclear power station; and taking the sum of the water level valve switching value of the nuclear power station evaporator and the main steam flow reference value corresponding to the main steam flow measured value as a main steam flow correction value of the main steam flow measured value of the nuclear power station evaporator.
Step S909, obtaining a main steam flow differential pressure measurement value of a nuclear power station evaporator; and counting to obtain the main steam flow differential pressure correction value of the evaporator of the nuclear power station according to the main steam flow differential pressure measurement value, the main steam flow measurement value and the main steam flow correction value of the evaporator of the nuclear power station.
According to the main steam flow calibration method, the main steam flow measurement value is monitored regularly, and if a large deviation exists between the main steam flow measurement value and the main steam flow reference value, the main steam flow measurement value and the main steam flow differential pressure measurement value are required to be corrected so as to ensure availability and accuracy; meanwhile, the scheme is successfully used in Dayawan and Ling Australian nuclear power stations and multi-base nuclear motor sets, the accuracy and the usability of main steam flow measurement can be realized, the reliability of important control or protection channels of the reactor is ensured, and certain feasibility and effectiveness are realized.
It should be understood that, although the steps in the flowcharts of fig. 2 and 9 are shown in order as indicated by the arrows, these steps are not necessarily performed in order as indicated by the arrows. The steps are not strictly limited to the order of execution unless explicitly recited herein, and the steps may be executed in other orders. Moreover, at least some of the steps in fig. 2, 9 may include a plurality of steps or stages that are not necessarily performed at the same time, but may be performed at different times, and the order of execution of the steps or stages is not necessarily sequential, but may be performed in rotation or alternatively with at least some of the other steps or stages.
In one embodiment, as shown in FIG. 10, a primary steam flow calibration apparatus is provided, comprising: a measurement acquisition module 1010, a difference determination module 1020, an anomaly detection module 1030, and a measurement calibration module 1040, wherein:
and the measured value obtaining module 1010 is configured to obtain main steam flow measured values of the evaporator of the nuclear power plant, where the main steam flow measured values are obtained by collecting at least two main steam flow detection terminals.
The difference determining module 1020 is configured to determine a difference between the main steam flow measured value acquired by each main steam flow detecting terminal and the corresponding main steam flow reference value.
The abnormality detection module 1030 is configured to confirm that an abnormality exists in the main steam flow measurement value of the evaporator of the nuclear power station if the difference value determined by the at least one main steam flow detection terminal meets a preset condition.
The measured value calibration module 1040 calibrates the main steam flow measured value of the evaporator of the nuclear power plant to obtain a main steam flow correction value of the main steam flow measured value.
In one embodiment, the calibration device for main steam flow further includes a main steam flow difference value standard value acquisition module, configured to acquire a main steam flow difference value standard value of each main steam flow detection terminal.
In one embodiment, the abnormality detection module 1030 is further configured to confirm that an abnormality exists in the main steam flow measurement value of the evaporator of the nuclear power plant if the absolute value of the difference value determined by the at least one main steam flow detection terminal is greater than the corresponding main steam flow difference value standard value.
In an embodiment, the main steam flow difference value standard value obtaining module is further configured to obtain a first measurement uncertainty and a second measurement uncertainty of each main steam flow detection terminal; and respectively inputting the first measurement uncertainty and the second measurement uncertainty of each main steam flow detection terminal into a main steam flow difference value standard value statistical model to obtain the main steam flow difference value standard value of each main steam flow detection terminal.
In one embodiment, the calibration device for main steam flow further includes a detection module, configured to confirm that the main steam flow measurement value of the evaporator of the nuclear power station is normal if the absolute value of the difference value determined by each main steam flow detection terminal is less than or equal to the corresponding main steam flow difference value standard value.
In one embodiment, the calibration device of the main steam flow further comprises a main steam flow reference value acquisition module, which is used for acquiring the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the evaporator of the nuclear power station when the main steam flow measured value is acquired through the main steam flow detection terminal; and counting according to the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the evaporator of the nuclear power station to obtain a heat balance flow value of the evaporator of the nuclear power station, and taking the heat balance flow value as a main steam flow reference value corresponding to the main steam flow measurement value.
In one embodiment, the measurement calibration module 1040 is further configured to obtain a water level valve switching value of the evaporator of the nuclear power plant; and taking the sum of the water level valve switching value of the nuclear power station evaporator and the main steam flow reference value corresponding to the main steam flow measured value as a main steam flow correction value of the main steam flow measured value of the nuclear power station evaporator.
In one embodiment, the calibration device of the main steam flow further comprises a main steam flow differential pressure correction module for obtaining a main steam flow differential pressure measurement value of the evaporator of the nuclear power station; and counting to obtain the main steam flow differential pressure correction value of the evaporator of the nuclear power station according to the main steam flow differential pressure measurement value, the main steam flow measurement value and the main steam flow correction value of the evaporator of the nuclear power station.
For specific limitations of the calibration means for the main steam flow, reference may be made to the above limitations of the calibration method for the main steam flow, which are not described in detail herein. The various modules in the primary steam flow calibration apparatus described above may be implemented in whole or in part by software, hardware, and combinations thereof. The above modules may be embedded in hardware or may be independent of a processor in the computer device, or may be stored in software in a memory in the computer device, so that the processor may call and execute operations corresponding to the above modules.
In one embodiment, a computer device is provided, which may be a server, and the internal structure of which may be as shown in fig. 11. The computer device includes a processor, a memory, and a network interface connected by a system bus. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer programs, and a database. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The database of the computer equipment is used for storing data such as a main steam flow measured value, a main steam flow reference value, a main steam flow correction value and the like. The network interface of the computer device is used for communicating with an external terminal through a network connection. The computer program, when executed by the processor, implements a method of calibrating the main steam flow.
It will be appreciated by those skilled in the art that the structure shown in fig. 11 is merely a block diagram of a portion of the structure associated with the present application and is not limiting of the computer device to which the present application applies, and that a particular computer device may include more or fewer components than shown, or may combine some of the components, or have a different arrangement of components.
In an embodiment, there is also provided a computer device comprising a memory and a processor, the memory having stored therein a computer program, the processor implementing the steps of the method embodiments described above when the computer program is executed.
In one embodiment, a computer-readable storage medium is provided, storing a computer program which, when executed by a processor, implements the steps of the method embodiments described above.
Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, storage, database, or other medium used in embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, or the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory. By way of illustration, and not limitation, RAM can be in the form of a variety of forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), and the like.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The above examples merely represent a few embodiments of the present application, which are described in more detail and are not to be construed as limiting the scope of the invention. It should be noted that it would be apparent to those skilled in the art that various modifications and improvements could be made without departing from the spirit of the present application, which would be within the scope of the present application. Accordingly, the scope of protection of the present application is to be determined by the claims appended hereto.
Claims (10)
1. A method of calibrating main steam flow, the method comprising:
acquiring main steam flow measurement values of a nuclear power station evaporator acquired by at least two main steam flow detection terminals;
acquiring main steam temperature, main steam pressure and fluid pressure difference before and after a pore plate of the evaporator of the nuclear power station when the main steam flow measurement value is acquired through the main steam flow detection terminal; according to the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the nuclear power station evaporator, the heat balance flow value of the nuclear power station evaporator is obtained through statistics and is used as a main steam flow reference value corresponding to the main steam flow measurement value; determining the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value;
If the difference value determined by at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal;
and taking the sum of the water level valve switching quantity of the nuclear power station evaporator and the main steam flow reference value corresponding to the main steam flow measured value as a main steam flow correction value of the main steam flow measured value of the nuclear power station evaporator.
2. The method of claim 1, further comprising, before confirming that there is an abnormality in the primary steam flow measurement value of the nuclear power plant evaporator if the difference determined by at least one of the primary steam flow detection terminals satisfies a preset condition:
obtaining a main steam flow difference standard value of each main steam flow detection terminal;
and if the difference value determined by at least one main steam flow detection terminal meets a preset condition, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal, including:
and if the absolute value of the difference value determined by at least one main steam flow detection terminal is larger than the corresponding main steam flow difference value standard value, confirming that the main steam flow measured value of the evaporator of the nuclear power station is abnormal.
3. The method of claim 2, wherein said obtaining a master steam flow differential value standard value for each of said master steam flow sensing terminals comprises:
acquiring a first measurement uncertainty and a second measurement uncertainty of each main steam flow detection terminal;
and respectively inputting the first measurement uncertainty and the second measurement uncertainty of each main steam flow detection terminal into a main steam flow difference value standard value statistical model to obtain a main steam flow difference value standard value of each main steam flow detection terminal.
4. The method of claim 2, further comprising, after determining the difference between the primary steam flow measurement value acquired by each of the primary steam flow detection terminals and a corresponding primary steam flow reference value:
and if the absolute values of the differences determined by the main steam flow detection terminals are smaller than or equal to the corresponding main steam flow difference standard values, confirming that the main steam flow measured values of the evaporator of the nuclear power station are normal.
5. The method according to claim 1, wherein the method further comprises:
acquiring a main steam flow differential pressure measurement value of the evaporator of the nuclear power station;
And counting to obtain the main steam flow differential pressure correction value of the nuclear power station evaporator according to the main steam flow differential pressure measurement value, the main steam flow measurement value and the main steam flow correction value of the nuclear power station evaporator.
6. A primary steam flow calibration apparatus, the apparatus comprising:
the measured value acquisition module is used for acquiring main steam flow measured values of the evaporator of the nuclear power station acquired by the at least two main steam flow detection terminals;
the difference value determining module is used for acquiring the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the evaporator of the nuclear power station when the main steam flow measured value is acquired through the main steam flow detecting terminal; according to the main steam temperature, the main steam pressure and the fluid pressure difference before and after the orifice plate of the nuclear power station evaporator, the heat balance flow value of the nuclear power station evaporator is obtained through statistics and is used as a main steam flow reference value corresponding to the main steam flow measurement value; determining the difference value between the main steam flow measured value acquired by each main steam flow detection terminal and the corresponding main steam flow reference value; the main steam flow reference value is a heat balance flow value of the evaporator of the nuclear power station;
The abnormality detection module is used for confirming that the measured value of the main steam flow of the evaporator of the nuclear power station is abnormal if the difference value determined by at least one main steam flow detection terminal meets a preset condition;
and the measured value calibration module is used for taking the sum of the switching value of the water level valve of the nuclear power station evaporator and the main steam flow reference value corresponding to the main steam flow measured value as a main steam flow corrected value of the main steam flow measured value of the nuclear power station evaporator.
7. The device according to claim 6, wherein the main steam flow calibration device further comprises a main steam flow difference standard value acquisition module, configured to acquire a main steam flow difference standard value of each main steam flow detection terminal; the abnormality detection module is further configured to confirm that an abnormality exists in the main steam flow measurement value of the evaporator of the nuclear power station if the absolute value of the difference value determined by the at least one main steam flow detection terminal is greater than the corresponding main steam flow difference value standard value.
8. The apparatus of claim 7, wherein the primary steam flow differential value standard value acquisition module is further configured to acquire a first measurement uncertainty and a second measurement uncertainty for each primary steam flow detection terminal; and respectively inputting the first measurement uncertainty and the second measurement uncertainty of each main steam flow detection terminal into a main steam flow difference value standard value statistical model to obtain the main steam flow difference value standard value of each main steam flow detection terminal.
9. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any one of claims 1 to 5 when the computer program is executed.
10. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 5.
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