CN109215820B - Nuclear power plant evaporator Steam-water Flow Measurement channel comparative approach and system - Google Patents
Nuclear power plant evaporator Steam-water Flow Measurement channel comparative approach and system Download PDFInfo
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Abstract
The present invention relates to nuclear power plant evaporator Steam-water Flow Measurement channel comparative approach and systems, comprising: S1, is formulated using uncertainty mean square root method and intersects standard of comparison；The real-time steam flow measurements of S2, the real-time water flow measurements for acquiring evaporator main feedwater flow redundant measurement channel and steam flow redundant measurement channel；S3, the references object that the intersection of Steam-water Flow Measurement channel compares is determined；S4, real-time water flow measurements and real-time steam flow measurements are compared operation with references object, by comparison operation result compared with intersecting standard of comparison and carrying out intersection.The present invention is compared operation by the parameter and feature characterized to system or equipment; and judge to verify the exception or failure of main water supply Measurement channel or vapour survey channel online according to comparison operation result; both it can guarantee functions of the equipments availability; it is also ensured that equipment dependability, and maintenance is all small compared with Interventional maintenance in personnel's investment, maintenance duration, resource input etc..
Description
Technical Field
The invention relates to the field of steam-water flow measurement of evaporators of nuclear power plants, in particular to a method and a system for comparing steam-water flow measurement channels of evaporators of nuclear power plants.
Background
The existing nuclear power station can meet the requirements of diversity, redundancy and independence, and the measurement of the same measurement object in the same, redundant or equivalent mode is a conventional measurement method of the nuclear power station, for example, the measurement of the main feed water flow of an evaporator of the nuclear power station and the measurement of the steam flow of the evaporator.
The measurement method of redundant design is adopted for measuring the main feedwater flow of the evaporator and the steam flow of the evaporator of the nuclear power station, however, the design increases the maintenance amount of equipment at the same time, and when the measurement equipment in the redundant measurement has deviation, whether a main feedwater flow measurement channel or a steam flow measurement channel of the evaporator is abnormal or fails cannot be effectively judged. In addition, the existing maintenance mode adopts interventional maintenance activities, the maintenance mode cannot ensure the availability of equipment functions, and the implementation risk of the maintenance activities is relatively high.
Disclosure of Invention
The invention aims to solve the technical problem of providing a method and a system for comparing steam-water flow measuring channels of an evaporator of a nuclear power station aiming at the defects in the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows: a method for comparing steam-water flow measuring channels of an evaporator of a nuclear power station is constructed, and comprises the following steps:
s1, determining a cross comparison standard by using an uncertainty root mean square method;
s2, collecting a real-time water flow measurement value of a main feed water flow redundancy measurement channel of the evaporator and a real-time steam flow measurement value of a steam flow redundancy measurement channel;
s3, determining a reference object of cross comparison of the steam-water flow measuring channels;
and S4, comparing the real-time water flow measurement value and the real-time steam flow measurement value with the reference object, and cross-comparing the comparison operation result with the cross comparison standard.
Preferably, the cross-comparison criteria include:
standard of allowed deviation under low flow cut-off conditions;
the uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator are obtained;
and (4) the allowable deviation standard under the allowable error condition of the function of the reactor protection channel.
Preferably, if the cross-comparison criteria are: the uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator are obtained;
the step S1 includes:
s11, calculating uncertainty of measurement of main water supply flow differential pressure of the evaporator;
s12, calculating uncertainty of steam flow differential pressure measurement of the evaporator;
s13, calculating uncertainty of flow measurement fluctuation of the main water supply of the evaporator;
s14, calculating the uncertainty of the whole main water supply flow redundancy measuring channel and the uncertainty of the whole steam flow redundancy measuring channel according to the uncertainty of the main water supply flow differential pressure measurement, the uncertainty of the measurement fluctuation and the uncertainty of the steam flow differential pressure measurement of the evaporator and by combining the uncertainties of all the modules of the main water supply measuring channel and the uncertainties of all the modules of the steam measuring channel;
and S15, carrying out root mean square operation on the integral uncertainty of the main feedwater flow redundancy measuring channel and the integral uncertainty of the steam flow redundancy measuring channel to obtain the integral uncertainty of the evaporator main feedwater flow redundancy measuring channel and the allowable deviation standard of the evaporator steam flow redundancy measuring channel under the uncertainty condition.
Preferably, if the cross-comparison criteria are: standard of allowed deviation under low flow cut-off conditions;
the step S1 includes:
s21, setting a small flow cutting point;
s22, calculating the integral uncertainty of the main water supply flow redundancy measuring channel of the small flow point and the integral uncertainty of the steam flow redundancy measuring channel according to the small flow cutting point;
and S23, carrying out root mean square operation on the integral uncertainty of the main feed water flow redundancy measuring channel of the small flow point and the integral uncertainty of the steam flow redundancy measuring channel to obtain an allowable deviation standard under the condition of the small flow point.
Preferably, if the cross-comparison criteria are: the allowable deviation standard under the condition of the allowable error of the function of the reactor protection channel;
the step S1 includes:
s31, acquiring uncertainty of all single modules of the evaporator main feed water flow redundancy measurement channel and uncertainty of all single modules of the evaporator steam flow redundancy measurement channel;
s32, respectively calculating a function verification value of the evaporator main water supply flow redundancy measurement channel and a function verification value of the evaporator steam flow redundancy measurement channel according to the uncertainty of all single modules of the evaporator main water supply flow redundancy measurement channel and the uncertainty of all single modules of the evaporator steam flow redundancy measurement channel;
and S33, performing root mean square operation on the function verification value of the evaporator main feed water flow redundancy measurement channel and the function verification value of the evaporator steam flow redundancy measurement channel to obtain an allowable deviation standard under the condition of a reactor protection channel function allowable error.
Preferably, the reference object comprises: measuring the average value of the water flow of the main water supply of the evaporator;
or a real-time water flow measurement of the evaporator feedwater is compared in a set with a real-time steam flow measurement of the evaporator steam.
Preferably, if the reference object is: real-time water flow measurements of the evaporator mains water are compared in groups with real-time steam flow measurements of the evaporator steam;
the step S4 includes:
s411, grouping all real-time steam flow measurement values and the real-time water flow measurement values for comparison and operation;
s412, summing the comparison operation result and the blowdown flow value of the evaporator;
and S413, cross-comparing the summation operation result with the cross comparison standard.
Preferably, if the reference object is: measuring the average value of the water flow of the main water supply of the evaporator;
the step S4 includes:
s421, performing difference operation on all the real-time steam flow measurement values and the water flow measurement average value one by one to obtain a difference value between the real-time steam flow measurement value and the water flow measurement average value;
s422, summing the difference value and the blowdown flow value of the evaporator;
and S423, cross-comparing the summation operation result with the cross comparison standard.
Preferably, the step S4 is followed by:
and S5, judging the abnormal condition of the steam-water flow measuring channel according to the cross comparison result.
The invention also provides a system for comparing the steam-water flow measurement channels of the evaporator of the nuclear power station, which comprises:
the standard making unit is used for making a cross comparison standard by adopting an uncertainty root mean square method;
the data acquisition unit is used for acquiring a real-time water flow measurement value of the main water supply flow redundancy measurement channel of the evaporator and a real-time steam flow measurement value of the steam flow redundancy measurement channel;
the determining unit is used for determining a reference object of cross comparison of the steam-water flow measuring channels;
and the cross comparison unit is used for comparing the real-time water flow measurement value and the real-time steam flow measurement value with the reference object, and cross comparing a comparison operation result with the cross comparison standard.
The method and the system for comparing the steam-water flow measuring channels of the evaporator of the nuclear power station have the following beneficial effects: according to the invention, through carrying out comparison operation on the parameters and characteristics represented by the system or the equipment and judging and verifying the abnormity or the fault of the main water supply measuring channel or the steam measuring channel on line according to the comparison operation result, the functional availability of the equipment can be ensured, the reliability of the equipment can also be ensured, and the maintenance activities are less in personnel investment, maintenance period, resource investment and the like than interventional maintenance activities.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic diagram of the configuration of redundant measurements of the primary feedwater flow and steam flow of a nuclear power plant evaporator of the present invention;
FIG. 2 is a flowchart of a procedure of a method for comparing steam-water flow measuring channels of an evaporator of a nuclear power plant according to the present invention;
FIG. 3 is a flowchart illustrating the process of obtaining the uncertainty of the entire main feedwater flow redundancy measurement channel of the evaporator and the allowable deviation criteria of the uncertainty of the entire steam flow redundancy measurement channel of the evaporator according to the present invention;
FIG. 4 is a flowchart of a process for obtaining the allowable deviation criteria for a low flow cut-off condition in accordance with the present invention;
FIG. 5 is a flowchart of a procedure for obtaining the allowable deviation criteria under the condition of the allowable error of the function of the protection channel of the reactor according to the present invention;
FIG. 6 is a schematic diagram of a main feed water flow measurement channel of the nuclear power plant evaporator of the present invention;
FIG. 7 is a schematic diagram of a nuclear power plant evaporator steam flow measurement channel of the present invention;
FIG. 8 is a cross comparison standard curve diagram of the redundancy measurement of the steam-water flow measuring channels of the nuclear power station.
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
As shown in fig. 1, the measurement of the main feed water flow and the measurement of the steam flow of the evaporator of the nuclear power plant of the invention are both provided with two measuring channels, each steam flow measuring channel is arranged corresponding to the main feed water flow measuring channel, and measuring equipment in each measuring channel can adopt a transmitter (flow sensor) to carry out real-time online measurement.
As shown in fig. 2, the invention provides a method for comparing steam-water flow measurement channels of a nuclear power station evaporator, which can be applied to a main feedwater flow redundancy measurement channel and a steam flow redundancy measurement channel of the nuclear power station evaporator. The method specifically comprises the following steps:
and step S1, determining a cross comparison standard by adopting an uncertainty root mean square method.
Due to the measurement characteristics of the flow measurement channel, the uncertainty of measurement under the low-power condition is larger than that under the rated power, so that the overall uncertainty of the flow measurement channel is adopted as the cross comparison standard under the low condition, and the allowable deviation is calculated under the condition that the function allowable error of a nuclear power station Final Safety Analysis Report (FSAR) on the protection channel is adopted as the cross comparison standard under the condition of approaching the rated power.
Optionally, the cross comparison standard formulated by using the uncertainty root mean square method in the embodiment of the present invention may include: standard of allowed deviation under low flow cut-off conditions; the uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator are obtained; and the allowable deviation standard under the allowable error condition of the function of the reactor protection channel.
Specifically, each cross-comparison criterion can be calculated in the following manner.
As shown in fig. 3, if the cross-comparison criteria are: the uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator are obtained; step S1 includes:
and step S11, calculating uncertainty of the measurement of the differential pressure of the main water supply flow of the evaporator.
Obtaining the following results according to the relation between the main water supply flow and the differential pressure:
and further it is possible to obtain,
wherein ρ is the fluid density; delta PMAXIs the differential pressure range; qMAXFor the flow range (i.e., the theoretical maximum), δ is the sign of the differentiation.
In addition, the temperature of the main feed water of the evaporator of the nuclear power plant is positively correlated with the nuclear power, and the temperature of the main feed water is increased along with the increase of the nuclear power. However, since the interval in which the temperature of the feedwater changes is small and the amount of influence on the density of the feedwater is small, the feedwater density is substantially constant, that is, the feedwater density is substantially constantAnd the uncertainty of the differential pressure measurement can be calculated. The specific calculation process is as follows:
getThereby, it is possible to obtain:thus, the uncertainty of the main feedwater differential pressure measurement can be found:
wherein, λ is an uncertain coefficient1For uncertainty factor, δ Q, of differential pressure measurementFW′Uncertainty flow value (t/h), epsilon, measured for main feedwater flow differential pressureFW′Percent (%) uncertainty measured for the main feedwater flow differential pressure. It will be understood that reference herein to the uncertainty of the main feedwater differential pressure measurement is to the percentage of uncertainty of the main feedwater flow differential pressure measurement.
And step S12, calculating uncertainty of the steam flow differential pressure measurement of the evaporator.
The relation between the steam flow and the differential pressure of the nuclear power station is as follows:
wherein Q is a measured value of steam flow; Δ P is a differential pressure signal; ρ is the vapor fluid density.
The relationship between the steam flow rate and the differential pressure can be obtained as follows:
and further it is possible to obtain,
the operation conditions of the steam flow channel of the nuclear power station are as follows: 65-75 bar, and the relation between the steam density and the pressure is as follows: rho is 0.58P-4.25, rhoAVG＝36.6kg/m3Therefore, the steam mass flow is greatly influenced by the steam density, and therefore the uncertainty of the steam flow differential pressure measurement can be calculated. The specific calculation process is as follows:
further obtaining:
therefore, the uncertainty of the steam flow differential pressure measurement is:
wherein Q isSTIs the measured average of the steam flow; delta QST′An uncertainty flow value (t/h) measured for steam flow Δ P; epsilonST′Percent uncertainty (%) measured for steam flow Δ P. It is to be understood that for purposes of uniformity, the uncertainty of the steam flow differential pressure measurement is referred to herein as the percentage uncertainty of the steam flow Δ P measurement.
And step S13, calculating uncertainty of the measurement fluctuation of the evaporator main water flow.
Since the liquid may have a certain influence on the measurement, in the embodiment of the present invention, the influence of the measurement fluctuation needs to be considered. Specifically, the uncertainty of the measurement fluctuation can be calculated by:
wherein λ is2For measuring fluctuationsConstant coefficient, δ QFW″Measuring the fluctuating uncertainty flow value (t/h), epsilon, for the prevailing feedwater flowFW″Is the percent uncertainty (%) of the measured fluctuation of the main feedwater flow. It will be understood that reference herein to the uncertainty of the measured fluctuation of the main feedwater is to the percentage uncertainty of the measured fluctuation of the main feedwater flow.
And step S14, calculating the uncertainty of the whole main water supply flow redundancy measuring channel and the uncertainty of the whole steam flow redundancy measuring channel according to the uncertainty of the main water supply flow differential pressure measurement, the uncertainty of the measurement fluctuation and the uncertainty of the steam flow differential pressure measurement of the evaporator and by combining the uncertainties of all the modules of the main water supply measuring channel and the uncertainties of all the modules of the steam measuring channel.
Specifically, the uncertainty of the whole main feedwater flow redundancy measurement channel is calculated as follows:
after uncertainty of differential pressure measurement and uncertainty of measurement fluctuation are obtained, the integral uncertainty of the main water supply flow redundancy measurement channel can be calculated by using an error root mean square method according to the uncertainty of all modules of the measurement channel. The method comprises the following specific steps:
wherein epsilonFWUncertainty (%) of the main feed water flow passage as a whole1、ε2、……、εkFor the uncertainty of a single module in a redundant measurement channel, k is the number of modules contained in the redundant measurement channel.
The uncertainty of the steam flow redundancy measurement channel as a whole is calculated as follows:
and after the uncertainty of the steam flow differential pressure measurement is obtained, combining the uncertainties of all modules of the measurement channel, and performing root mean square operation by using an error root mean square method to obtain the integral uncertainty of the steam flow redundancy measurement channel.
Specifically, it can be obtained by the following calculation formula:
wherein epsilonSTMeasuring the overall channel uncertainty (%) for steam flow redundancy; epsilon1、ε2、……、εmThe uncertainty of a single module in the steam flow redundancy measurement channel is measured, and m is the number of modules contained in the steam flow redundancy measurement channel.
And step S15, carrying out root mean square operation on the integral uncertainty of the main feedwater flow redundancy measuring channel and the integral uncertainty of the steam flow redundancy measuring channel to obtain the integral uncertainty of the evaporator main feedwater flow redundancy measuring channel and the allowable deviation standard of the evaporator steam flow redundancy measuring channel under the uncertainty condition.
The uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator can be expressed by the following mathematical formula:
as shown in fig. 4, if the cross-comparison criteria are: the step S1 includes the following steps:
and step S21, setting a small flow cutting point.
Because the main water supply flow and the differential pressure have an evolution relation, the smaller the signal is, the larger the error is when the evolution is carried out, so that the flow dead zone, namely the small flow cutting point, is needed to be set in order to ensure the validity of the cross comparison standard when the cross comparison standard is accurately timed.
Similarly, since the steam flow rate and the differential pressure have an evolution relationship, a small signal error is large when the evolution is performed, and therefore, when the cross comparison criterion is made, in order to ensure the validity of the cross comparison criterion, it is necessary to provide a flow dead zone, that is, a small flow cut-off point. In the embodiment of the invention, the small flow cutting point of the steam flow and the small flow cutting point of the main feed water flow can be set to be the same.
And step S22, calculating the integral uncertainty of the main feedwater flow redundancy measuring channel of the small flow point and the integral uncertainty of the steam flow redundancy measuring channel according to the small flow cutting point.
Specifically, in the embodiment of the invention, the main feed water flow cut-off point is represented by a small flow cut-off point alpha, and the real-time water flow measurement value measured in real time is QFWTheoretical maximum value of QMAXWherein α is a percentage. Because a small flow cut-off point is arranged, when the flow value Q is measuredFW＜α×QMAXWhen, the flow rate is shown as 0; when measuring the flow rate value QFW≥α×QMAXThe flow is displayed as the current measurement. Therefore, when the measured flow rate value QFW < alpha x QMAX, the uncertainty of the whole main feed water flow channel is QFWa＝α×QMAXSo that the overall uncertainty of the main feed water flow channel, i.e. the cut point of small flow, can be calculated
Specifically, in the embodiment of the invention, the small flow cut-off point of the steam flow is also expressed by alpha, and the real-time measured real-time steam flow value is QSTThe theoretical maximum value of the steam flow is also QMAXWherein α is a percentage. Because a small flow cut-off point is arranged, when the real-time steam flow value Q is obtainedST＜α×QMAXWhen, the flow rate is shown as 0; when real-time steam flow value QST≥α×QMAXThe flow is displayed as the current measurement. Therefore, when the real-time steam flow value QST＜α×QMAXWhile, the uncertainty of the whole steam flow channel is taken as QSTa＝α×QMAXSo that the overall uncertainty of the steam flow channel, i.e. the point of low cut, can be calculated
Wherein epsilonSTaThe overall uncertainty of the steam flow channel at the small flow cut-off point.
And step S23, carrying out root mean square operation on the integral uncertainty of the main feed water flow redundancy measuring channel of the small flow point and the integral uncertainty of the steam flow redundancy measuring channel to obtain an allowable deviation standard under the condition of the small flow point.
The standard of allowable deviation under conditions of a small flow cut-off point can be expressed mathematically as:
as shown in fig. 5, if the cross-comparison criteria are: the step S1 includes the steps of:
and step S31, obtaining the uncertainty of all single modules of the redundant measurement channel of the main feedwater flow of the evaporator and the uncertainty of all single modules of the redundant measurement channel of the steam flow of the evaporator.
The uncertainty of all single modules of the main water supply flow redundant measurement channel and the evaporation flow redundant measurement channel is the measurement precision of each single module, and can be directly obtained through the use instruction of each single module.
And step S32, respectively calculating the function verification value of the evaporator main water supply flow redundancy measurement channel and the function verification value of the evaporator steam flow redundancy measurement channel according to the uncertainty of all single modules of the evaporator main water supply flow redundancy measurement channel and the uncertainty of all single modules of the evaporator steam flow redundancy measurement channel.
In the embodiment of the invention, the measuring equipment of the main feedwater flow redundancy measuring channel is the same as the measuring equipment of the steam flow redundancy measuring channel, so that the function allowable errors of the measuring equipment of the main feedwater flow redundancy measuring channel and the steam flow redundancy measuring channel are the same, and the measuring equipment can be obtained by the following formula:
δ(FS)＝(δ(FP)2-δ(FT)2)1/2；
therefore, combining all the uncertainties of the individual modules and performing the root mean square operation yields: the main water supply flow redundancy measurement channel function verification value is as follows:
steam flow redundancy measurement channel function verification value:
and step S33, performing root mean square operation on the function verification value of the evaporator main feed water flow redundancy measurement channel and the function verification value of the evaporator steam flow redundancy measurement channel to obtain an allowable deviation standard under the condition of a reactor protection channel function allowable error.
Specifically, the allowable deviation standard under the allowable error condition of the reactor protection channel function can be expressed by the following mathematical formula:
the cross comparison standard of the flow rate measurement of the evaporator steam water can be obtained in conclusion and is expressed by the following mathematical formula:
from this equation, it can be seen that the value of Q is less thanzWhen the flow is measured, the uncertainty of the whole channel objectively exists is larger than the function allowable error of the channel, so the uncertainty of the whole channel is used as a standard; when greater than QzWhen the flow is measured, the uncertainty existing in the whole client of the channel is smaller than the allowable error of the channel function, so the allowable error of the channel function is taken as a standard.
Further, in the embodiment of the present invention, in order to make the accuracy of the established cross comparison standard higher, the established cross comparison standard may be modified by using the normal distribution probability.
In particular, according to the normally distributed probabilityAnalysis, according to the parameter μ ═ 0, σ2Normal distribution probability density function of (σ is standard deviation):
wherein x is the uncertainty of the main feedwater flow redundancy measurement channel or the steam flow redundancy measurement channel, when-1.96 sigma is less than or equal to x and less than or equal to +1.96 sigma, the normal distribution function phi (x) is 95%, and the judgment requirement of the steam flow measurement channel availability can be met in the interval according to the design standard, so that 1.96 sigma is C (fv). Different flow measurement channels have difference in severity, so that a C (fv) coefficient can be set according to normal distribution probability analysis, and the coverage probability of abnormity and fault judgment is realized.
And step S2, acquiring a real-time water flow measured value of the main water supply flow redundancy measuring channel of the evaporator and a real-time steam flow measured value of the steam flow redundancy measuring channel.
The real-time water flow measurement value of the main water supply flow redundancy measurement channel and the real-time steam flow measurement value of the steam flow redundancy measurement channel can be multiple, and the real-time water flow measurement value and the real-time steam flow measurement value are determined according to the number of the set measurement equipment, namely one measurement equipment corresponds to one real-time measurement value. In the embodiment of the invention, because the steam flow redundancy measurement channel and the main feed water flow redundancy measurement channel are correspondingly arranged, the steam flow measurement equipment and the main feed water flow measurement equipment are correspondingly arranged, and therefore, the quantity of the steam flow measurement equipment is the same as that of the main feed water flow measurement equipment.
Assuming that the number of the steam flow measuring devices and the number of the main feedwater flow measuring devices are both n, the collected real-time main feedwater flow measured values are as follows: qFW1、QFW2、QFW3、……、QFWn(ii) a The real-time steam flow measurements are: qST1、QST2、QST3、……、QSTn。
And step S3, determining a reference object of the cross comparison of the steam-water flow measuring channels.
Optionally, in the embodiment of the present invention, there are two types of reference objects for cross comparison.
The first one is: the average value is measured for the water flow of the evaporator main feed water.
The second method is as follows: real-time water flow measurements of the evaporator feedwater are compared in groups with real-time steam flow measurements of the evaporator steam. Since the main feedwater flow and the evaporator flow are physically grouped, a real-time water flow measurement of the evaporator main feedwater can be grouped with a real-time steam flow measurement of the evaporator steam for comparison as a reference.
And step S4, comparing the real-time water flow measurement value and the real-time steam flow measurement value with a reference object, and cross-comparing the comparison operation result with a cross comparison standard.
Since the water level in the evaporator is a dynamic equilibrium process and the evaporator output is equal to the input, Q is theoreticallyFW＝QST+QbdWherein Q isbdThe blowdown flow for the evaporator. The cross-comparison is performed in principle in the evaporator blowdown stop state, i.e. QbdIs 0; if the evaporator blow-off flow is in a non-stop state, the evaporator blow-off flow Q needs to be consideredbdThe cross comparison standard needs to consider the uncertainty of the evaporator blowdown flow, therefore, when the evaporator blowdown flow is in a non-stop state, the cross comparison standard needs to be further corrected, and the corrected cross comparison standard is as follows:
wherein epsilonbdUncertainty of evaporator blow-down flow, QBDIs the range of the sewage discharge flow of the evaporator.
If the reference object is: real-time water flow measurements of the evaporator mains water are compared in groups with real-time steam flow measurements of the evaporator steam;
step S4 includes:
and step S411, all real-time steam flow measurement values and real-time water flow measurement values are grouped for comparison and calculation.
And step S412, summing the comparison operation result and the discharge flow value of the evaporator.
And step S413, performing cross comparison on the summation operation result and a cross comparison standard.
I.e. QST1、QST2、QST3、……、QSTnAnd QFW1、QFW2、QFW3、……、QFWnMaking comparisons in groups, if cross-comparison criteria are exceeded, e.g.The abnormality of the main water supply or steam flow measuring channel of the evaporator is indicated, and further inspection and treatment or an interventional maintenance mode are required. On the contrary, ifThe flow measurement channels of the main water supply and the steam flow of the evaporator are within the deviation allowable range, and the result is qualified and does not need to be processed.
If the reference object is: measuring the average value of the water flow of the main water supply of the evaporator; step S4 includes:
and step S421, performing difference operation on all the real-time steam flow measurement values and the water flow measurement average value one by one to obtain a difference value between the real-time steam flow measurement value and the water flow measurement average value.
And step S422, summing the difference value and the discharge flow value of the evaporator.
And step S423, cross-comparing the summation operation result with a cross-comparison standard.
I.e. QST1、QST2、QST3、……、QSTnOne by one with QFWMaking a comparison if the cross-comparison criterion is exceeded, e.g.The abnormality of the main water supply or steam flow measuring channel of the evaporator is indicated, and further inspection and treatment or an interventional maintenance mode are required. On the contrary, ifThe flow measurement channels of the main water supply and the steam flow of the evaporator are within the deviation allowable range, and the result is qualified and does not need to be processed.
Further, step S4 is followed by:
and S5, judging the abnormal condition of the steam-water flow measuring channel according to the cross comparison result.
The invention also provides a system for comparing the steam-water flow measurement channels of the evaporator of the nuclear power station, which is characterized by comprising the following components:
and the standard making unit is used for making the cross comparison standard by adopting an uncertainty root mean square method.
And the data acquisition unit is used for acquiring a real-time water flow measurement value of the main water supply flow redundancy measurement channel of the evaporator and a real-time steam flow measurement value of the steam flow redundancy measurement channel.
And the determining unit is used for determining a reference object of the cross comparison of the steam-water flow measuring channels.
And the cross comparison unit is used for comparing the real-time water flow measurement value and the real-time steam flow measurement value with a reference object, and cross comparing the comparison operation result with a cross comparison standard.
The technical solution of the present invention is explained in detail by a specific example.
The measurement of the main feed water flow of the nuclear power station evaporator is shown in fig. 6, a main feed water flow transmitter measures a front differential pressure signal and a rear differential pressure signal of a throttling element and converts the front differential pressure signal and the rear differential pressure signal into 4-20 mA current signals, an RS current-to-voltage conversion module converts the 4-20 mA current signals into 1-5V voltage signals, one path of the signals is sent to a DC power generation module for power generation operation, and the signals participate in reactor protection logic (RPR) and evaporator water level control; and the other path IS sent to an EU computer for display through an IS isolation module. Wherein M represents a flow transmitter, RS IS a current-to-voltage module, DC IS an evolution module, IS IS an isolation module, CA IS a voltage signal conversion module, XU IS a threshold module, and EU IS computer display.
The steam flow measurement of the nuclear power station evaporator is shown in fig. 6, a steam flow transmitter measures a front differential pressure signal and a rear differential pressure signal of a throttling element and converts the front differential pressure signal and the rear differential pressure signal into 4-20 mA current signals, and an RS current-to-voltage module converts the 4-20 mA current signals into 1-5V voltage signals. The differential pressure voltage signal is subjected to pressure correction through a multiplier-divider, and then is sent to a DC evolution module for evolution operation, and one path of the differential pressure voltage signal participates in reactor protection logic (RPR); and the other path IS sent to an EU computer for display and evaporator water level control through an IS isolation module. Wherein, MP represents the pressure transmitter, and MU is the multiplier-divider module.
Knowing the uncertainty, Q, of the Δ P measurementMAX2442(t/h), the uncertainty factor λ of Δ P measurement is set according to the measurement principle and characteristics11.01%, uncertainty coefficient lambda of measurement fluctuation20.5%, and 0.5% small flow cut-off point α. The Final Safety Analysis Report (FSAR) of the nuclear power plant requires that δ (FP) be 3% for the allowable error of the main feedwater flow and steam flow channel functions.
The uncertainty of all modules of the measurement channel is given in the following table:
| module | RS | DC | XU | IS | CA | EU | MU |
| Degree of uncertainty | ε1＝0.15％ | ε2＝0.5％ | ε3＝0.5％ | ε4＝0.5％ | ε5＝0.1％ | ε6＝0.5％ | ε7＝0.5％ |
According to the relation between the flow and the differential pressure, the following results are obtained:
uncertainty of nuclear power station main water supply flow delta P measurement:
uncertainty of main feed water flow measurement fluctuation:
the uncertainty of the whole main feed water flow measuring channel is as follows:
uncertainty of nuclear power plant steam flow Δ P measurement:
the integral uncertainty of a nuclear power station steam flow measurement channel:
the final evaporator steam-water flow cross comparison standard is as follows:
according to the formula, a cross comparison standard curve of the steam-water flow channel measurement of the evaporator of the nuclear power station is obtained, and the cross comparison standard curve is shown in fig. 8.
The scheme of the invention can realize the following effects:
(1) ensuring availability of device functionality
The operation states of the system and the equipment are reflected by the parameters and characteristics of the online system or equipment, and the model ensures that the system or the equipment can be used and is in a normal operation state, so that the possibility of destructive maintenance is limited, and the implementation risk of maintenance activities is low.
(2) Guarantee in terms of device reliability
The initial reliability of the equipment is kept, the established maintenance strategy preferentially selects to carry out inspection or test activities such as supervision or verification, and the like, and then the next action is determined according to the supervision or verification result, so that systematic periodic maintenance activities are avoided. Through supervision or periodic verification, possible system or equipment deviation and abnormality are detected, the health state of the equipment is evaluated, and whether interventional maintenance is carried out or not is determined according to the health state of the equipment.
(3) Small investment for maintenance activities
The parameters and characteristics represented by the system or the equipment are verified, and the maintenance activities are smaller than the intervention maintenance activities in personnel investment, maintenance period, resource investment and the like.
(4) The establishment of the cross comparison standard and the establishment of the reference object have scientificity, and the abnormity or the fault existing in the redundant measurement channel can be effectively found.
The above embodiments are merely illustrative of the technical ideas and features of the present invention, and are intended to enable those skilled in the art to understand the contents of the present invention and implement the present invention, and not to limit the scope of the present invention. All equivalent changes and modifications made within the scope of the claims of the present invention should be covered by the claims of the present invention.
It will be understood that modifications and variations can be made by persons skilled in the art in light of the above teachings and all such modifications and variations are intended to be included within the scope of the invention as defined in the appended claims.
Claims (6)
1. A method for comparing steam-water flow measuring channels of an evaporator of a nuclear power station is characterized by comprising the following steps:
s1, determining a cross comparison standard by using an uncertainty root mean square method;
the cross-comparison criteria include: standard of allowed deviation under low flow cut-off conditions; the uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator are obtained; the allowable deviation standard under the condition of the allowable error of the function of the reactor protection channel;
if the cross-comparison criteria are: the uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator are obtained;
the step S1 includes:
s11, calculating uncertainty of measurement of main water supply flow differential pressure of the evaporator;
s12, calculating uncertainty of steam flow differential pressure measurement of the evaporator;
s13, calculating uncertainty of flow measurement fluctuation of the main water supply of the evaporator;
s14, calculating the uncertainty of the whole main water supply flow redundancy measuring channel and the uncertainty of the whole steam flow redundancy measuring channel according to the uncertainty of the main water supply flow differential pressure measurement, the uncertainty of the measurement fluctuation and the uncertainty of the steam flow differential pressure measurement of the evaporator and by combining the uncertainties of all the modules of the main water supply measuring channel and the uncertainties of all the modules of the steam measuring channel;
s15, carrying out root mean square operation on the integral uncertainty of the main feedwater flow redundancy measuring channel and the integral uncertainty of the steam flow redundancy measuring channel to obtain the integral uncertainty of the evaporator main feedwater flow redundancy measuring channel and an allowable deviation standard under the condition of the integral uncertainty of the evaporator steam flow redundancy measuring channel;
if the cross-comparison criteria are: standard of allowed deviation under low flow cut-off conditions;
the step S1 includes:
s21, setting a small flow cutting point;
s22, calculating the integral uncertainty of the main water supply flow redundancy measuring channel of the small flow point and the integral uncertainty of the steam flow redundancy measuring channel according to the small flow cutting point; the integral uncertainty of the main water supply flow channel of the small flow point is as follows:(ii) a The overall uncertainty of the steam flow redundancy measurement channel is as follows:(ii) a Wherein,Q FWa =α×Q MAX alpha is a small flow cutting point of the main water supply flow,Q MAX is the theoretical maximum value of the main feed water flow;Q STa =α'×Q ' MAX ，α'is a small flow cut-off point for the steam flow,Q ' MAX is the theoretical maximum value of steam flow;
s23, carrying out root mean square operation on the integral uncertainty of the main water supply flow redundancy measuring channel of the small flow point and the integral uncertainty of the steam flow redundancy measuring channel to obtain an allowable deviation standard under the condition of the small flow point;
if the cross-comparison criteria are: the allowable deviation standard under the condition of the allowable error of the function of the reactor protection channel;
the step S1 includes:
s31, acquiring uncertainty of all single modules of the evaporator main feed water flow redundancy measurement channel and uncertainty of all single modules of the evaporator steam flow redundancy measurement channel;
s32, respectively calculating a function verification value of the evaporator main water supply flow redundancy measurement channel and a function verification value of the evaporator steam flow redundancy measurement channel according to the uncertainty of all single modules of the evaporator main water supply flow redundancy measurement channel and the uncertainty of all single modules of the evaporator steam flow redundancy measurement channel in combination with function allowable errors;
s33, carrying out root mean square operation on the function verification value of the evaporator main water supply flow redundancy measurement channel and the function verification value of the evaporator steam flow redundancy measurement channel to obtain an allowable deviation standard under the condition of a reactor protection channel function allowable error;
s2, collecting a real-time water flow measurement value of a main feed water flow redundancy measurement channel of the evaporator and a real-time steam flow measurement value of a steam flow redundancy measurement channel;
s3, determining a reference object of cross comparison of the steam-water flow measuring channels;
and S4, comparing the real-time water flow measurement value and the real-time steam flow measurement value with the reference object, and cross-comparing the comparison operation result with the cross comparison standard.
2. The method for comparing the steam-water flow measuring channels of the evaporators of the nuclear power plants according to claim 1, wherein the reference object comprises: measuring the average value of the water flow of the main water supply of the evaporator;
or a real-time water flow measurement of the evaporator feedwater is compared in a set with a real-time steam flow measurement of the evaporator steam.
3. The method for comparing the steam-water flow measuring channels of the evaporator of the nuclear power plant as recited in claim 2, wherein if the reference object is: real-time water flow measurements of the evaporator mains water are compared in groups with real-time steam flow measurements of the evaporator steam;
the step S4 includes:
s411, grouping all real-time steam flow measurement values and the real-time water flow measurement values for comparison and operation;
s412, summing the comparison operation result and the blowdown flow value of the evaporator;
and S413, cross-comparing the ratio of the summation operation result and the theoretical maximum value of the steam flow with the cross comparison standard.
4. The method for comparing the steam-water flow measuring channels of the evaporator of the nuclear power plant as recited in claim 2, wherein if the reference object is: measuring the average value of the water flow of the main water supply of the evaporator;
the step S4 includes:
s421, performing difference operation on all the real-time steam flow measurement values and the water flow measurement average value one by one to obtain a difference value between the real-time steam flow measurement value and the water flow measurement average value;
s422, summing the difference value and the blowdown flow value of the evaporator;
and S423, cross-comparing the ratio of the summation operation result and the theoretical maximum value of the steam flow with the cross comparison standard.
5. The method for comparing the steam-water flow measuring channels of the evaporators of the nuclear power plants as claimed in claim 1, wherein the step S4 is followed by further comprising:
and S5, judging the abnormal condition of the steam-water flow measuring channel according to the cross comparison result.
6. The utility model provides a nuclear power station evaporimeter soda flow measurement passageway comparison system which characterized in that includes:
the standard making unit is used for making a cross comparison standard by adopting an uncertainty root mean square method;
the cross-comparison criteria include: standard of allowed deviation under low flow cut-off conditions; the uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator are obtained; the allowable deviation standard under the condition of the allowable error of the function of the reactor protection channel;
if the cross-comparison criteria are: the uncertainty of the whole main feed water flow redundancy measuring channel of the evaporator and the allowable deviation standard under the uncertainty condition of the whole steam flow redundancy measuring channel of the evaporator are obtained;
the standard formulation unit is specifically configured to:
calculating the uncertainty of the differential pressure measurement of the main water supply flow of the evaporator;
calculating uncertainty of steam flow differential pressure measurement of the evaporator;
calculating uncertainty of measurement fluctuation of the main water supply flow of the evaporator;
calculating the uncertainty of the whole main water supply flow redundancy measuring channel and the uncertainty of the whole steam flow redundancy measuring channel according to the uncertainty of the main water supply flow differential pressure measurement, the uncertainty of the measurement fluctuation and the uncertainty of the steam flow differential pressure measurement of the evaporator and by combining the uncertainties of all modules of the main water supply measuring channel and the uncertainties of all modules of the steam measuring channel;
carrying out root mean square operation on the integral uncertainty of the main feedwater flow redundancy measuring channel and the integral uncertainty of the steam flow redundancy measuring channel to obtain the integral uncertainty of the main feedwater flow redundancy measuring channel of the evaporator and an allowable deviation standard under the condition of the integral uncertainty of the steam flow redundancy measuring channel of the evaporator;
if the cross-comparison criteria are: standard of allowed deviation under low flow cut-off conditions;
the standard formulation unit is specifically configured to:
setting a small flow cutting point;
calculating the integral uncertainty of the main feed water flow redundancy measuring channel of the small flow point and the integral uncertainty of the steam flow redundancy measuring channel according to the small flow cutting point; the integral uncertainty of the main water supply flow channel of the small flow point is as follows:(ii) a The overall uncertainty of the steam flow redundancy measurement channel is as follows:(ii) a Wherein,Q FWa =α×Q MAX alpha is a small flow cutting point of the main water supply flow,Q MAX is the theoretical maximum value of the main feed water flow;Q STa =α'×Q ' MAX ，α'is a small flow cut-off point for the steam flow,Q ' MAX is the theoretical maximum value of steam flow;
carrying out root mean square operation on the integral uncertainty of the main feed water flow redundancy measuring channel of the small flow point and the integral uncertainty of the steam flow redundancy measuring channel to obtain an allowable deviation standard under the condition of the small flow point;
if the cross-comparison criteria are: the allowable deviation standard under the condition of the allowable error of the function of the reactor protection channel;
the standard formulation unit is specifically configured to:
the uncertainty of all single modules of a main water supply flow redundancy measuring channel of the evaporator and the uncertainty of all single modules of a steam flow redundancy measuring channel of the evaporator are obtained;
respectively calculating a function verification value of the main feedwater flow redundancy measuring channel of the evaporator and a function verification value of the steam flow redundancy measuring channel of the evaporator according to the uncertainty of all single modules of the main feedwater flow redundancy measuring channel of the evaporator and the uncertainty of all single modules of the steam flow redundancy measuring channel of the evaporator in combination with a function allowable error;
performing root mean square operation on the function verification value of the evaporator main feed water flow redundancy measurement channel and the function verification value of the evaporator steam flow redundancy measurement channel to obtain an allowable deviation standard under the condition of a reactor protection channel function allowable error;
the data acquisition unit is used for acquiring a real-time water flow measurement value of the main water supply flow redundancy measurement channel of the evaporator and a real-time steam flow measurement value of the steam flow redundancy measurement channel;
the determining unit is used for determining a reference object of cross comparison of the steam-water flow measuring channels;
and the cross comparison unit is used for comparing the real-time water flow measurement value and the real-time steam flow measurement value with the reference object, and cross comparing a comparison operation result with the cross comparison standard.
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