CN112967825A - Reactivity measurement method based on correction signal uncertainty analysis - Google Patents

Reactivity measurement method based on correction signal uncertainty analysis Download PDF

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CN112967825A
CN112967825A CN202110297324.6A CN202110297324A CN112967825A CN 112967825 A CN112967825 A CN 112967825A CN 202110297324 A CN202110297324 A CN 202110297324A CN 112967825 A CN112967825 A CN 112967825A
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汪文聪
阳林锋
邓艾宁
黄礼渊
刘才学
闫晓
徐建军
牛江
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Nuclear Power Institute of China
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Abstract

The invention discloses a reactivity measurement method based on correction signal uncertainty analysis, which comprises the following steps: s1, maximum frequency sampling processing; s2, down-sampling by an averaging method to obtain a neutron signal sequence I with the sampling frequency of f1f1And its uncertainty … neutron signal sequence I with sampling frequency fnfnAnd its uncertainty; f1, fn are both smaller than fmax; s3, evaluating the uncertainty of actual measurement; s4, correcting to obtain the uncertainty of the corrected neutron signal sequence; s5, optimal judgment; s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the optimal neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the optimal neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.

Description

Reactivity measurement method based on correction signal uncertainty analysis
Technical Field
The invention relates to the field of nuclear reactor reactivity measurement and processing, in particular to a reactivity measurement method based on correction signal uncertainty analysis.
Background
The reactivity measurement of the nuclear reactor core mainly aims at the measurement processes of control rod integral value, rod clamping subcritical degree, shutdown depth and the like in the physical test process.
The commonly used reactivity measurement methods for nuclear power plants are: boron adjusting method, rod changing method and dynamic rod carving method. The boron regulation method measures the micro and integral values of the control rod by regulating the boron concentration, but has long measuring time and high cost;
the rod changing method does not need to adjust boron, consumes a little short time and can measure the integral value of the control rod;
the dynamic rod-carving method can accurately measure the control rod integral value in a short time by inserting the control rod downwards and combining calculation analysis and actual measurement data, and is a method widely used by the conventional nuclear power station.
However, the above methods are generally used for reactivity measurements within about 2000pcm, with limitations for large reactivity measurements.
The currently used method for measuring large reactivity is the rod drop method.
The basic principle of the rod dropping method is as follows: and (3) instantaneously dropping the control rod into the reactor in a critical state, measuring the change of the neutron counting rate along with time, and calculating the reactivity to be measured by combining the neutron counting rates before and after dropping the rod. According to the method, the rod drop is adopted, the quick measurement of the large reactivity such as the control rod integral value, the rod clamping subcritical degree and the shutdown depth can be realized, but the method is based on a point reactor model, the measurement result is easily influenced by the neutron flux space effect, and an error exists in the large reactivity measurement process. In order to obtain a more accurate measurement result with large reactivity, the measurement process of the rod drop method needs to be corrected based on three-dimensional space-time dynamics analysis.
In the process of reactivity measurement, a neutron signal is a key parameter for reactivity measurement, the quantity is influenced by factors such as statistical fluctuation, high-voltage ripples and electromagnetic interference in the measurement process, and the measurement result has certain uncertainty. Therefore, uncertainty analysis is needed in the reaction measurement process, measurement data are optimized, and the influence of uncertainty is reduced, so that the measurement efficiency and accuracy are improved.
At present, no other unit develops research on a reactivity measurement method based on corrected signal uncertainty analysis or reports of related patent technologies in China. Therefore, it is necessary to master an autonomized reactivity measurement method based on corrected signal uncertainty analysis for the difference between the autonomous reactor core and the foreign reactor core, and to provide capability for efficient and accurate measurement of reactor core reactivity.
Disclosure of Invention
The invention aims to provide a reactivity measurement method based on correction signal uncertainty analysis, which can reduce the influence of factors such as neutron signal statistical fluctuation, high-voltage ripples, electromagnetic interference and the like in the reactivity measurement process, make up the defects of the existing measurement method aiming at dynamic reactivity measurement, and improve the efficiency and the accuracy of reactor reactivity measurement.
The invention is realized by the following technical scheme:
a method of reactivity measurement based on a modified signal uncertainty analysis, comprising the steps of:
s1, maximum frequency sampling processing: when the reactor is introduced with reactivity, neutron signal monitoring is carried out, and neutron signal sampling is carried out by adopting a data acquisition card with the maximum sampling frequency; a group of neutron signal sequences I with the maximum sampling frequency fmax output by the data acquisition cardfmax(ii) a The neutron signal sequence IfmaxIncludes I neutron signal data measured values, I1、I2、…Ii(ii) a i represents a sampling point, and the size of i is determined according to fmax;
s2, average down-sampling: using arithmetic mean method or weighted mean method of adjacent dot data to neutron signal sequence IfmaxPerforming down-sampling for n times to obtain samplesNeutron signal sequence I with frequency f1f1… neutron signal sequence I with sampling frequency fnfn(ii) a f1, fn are both smaller than fmax;
s3, evaluating the uncertainty of the actual measurement: for neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnCarrying out actual measurement uncertainty evaluation to obtain actual measurement uncertainty of the neutron signal sequence under different sampling frequencies;
s4, correction: neutron signal sequence I with correction factor pair sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnCorrecting to obtain a corrected neutron signal sequence; correction factor-introduced uncertainty versus neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnCarrying out uncertainty synthesis on the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal sequence;
s5, optimal judgment: according to the neutron signal sequence I with the modified sampling frequency f1f1Corrected composite uncertainty … neutron signal sequence I with sampling frequency fnfnThe corrected synthesis uncertainty is subjected to optimal judgment, a corrected signal data set with the optimal uncertainty is selected from the corrected synthesis uncertainty, and a neutron signal sequence corresponding to the optimal uncertainty is recorded as an optimal neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the optimal neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the optimal neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
The design principle of the invention is as follows:
in existing measurements, the environmental impact is generally not taken into account, but the measured neutron signal is directly substituted into the reactivity calculation.
The application field of the invention is reactivity measurement of nuclear reactors, the measurement environment is more complex, and the general influence factors are as follows: the signal statistics is influenced by factors such as fluctuation, high-voltage ripple, electromagnetic interference and the like; if the environmental influence is not considered and only the systematic error of the point stack measurement model is considered, the obtained reactivity has certain uncertainty.
The invention needs to design a processing method, which effectively reduces the influence of the measuring environment; the invention carries out down-sampling processing on the corrected neutron signal, and simultaneously constructs standard uncertainty or adopts a synthesis method to evaluate the uncertainty of the down-sampled neutron signal, thereby optimizing and reconstructing the actually measured and corrected data to reduce the uncertainty thereof, thereby reducing the influence of the actually measured environment. It can be preferred from these data sets to have a set of neutron signals with an optimum uncertainty, which reduces environmental impact; the optimal set of neutron signals selected by the neutron detector can be used for subsequent reactivity processing. In the invention, the neutron signal is subjected to down-sampling processing and neutron signal correction, the system error of the point stack measurement model is eliminated, the influence of uncertainty caused by a measurement environment is reduced, and finally the reactivity calculation is carried out.
The invention firstly adopts the maximum frequency to sample, thus enough data points can be obtained by one-time sampling, and then adopts the average method to carry out down-sampling processing to form different data groups, thus directly obtaining the data groups with different frequencies under the same sampling environment, and the external environments of the data groups are the same. In the conventional method, the sampling times are repeated, the measurement time is greatly increased in each sampling with different frequencies, the measurement effect is too low, and the environmental conditions of each measurement cannot be completely the same, which is not beneficial to comparison.
The actual measurement uncertainty evaluation refers to the uncertainty evaluation of the neutron signal obtained by the reactor in the actual environment, so that the uncertainty of the actual measurement neutron signal is obtained. The actual measurement uncertainty evaluation process is carried out relative to the actual measurement neutron signal obtained by the average method down-sampling processing, specifically, the uncertainty of the neutron signal in a typical state can be adopted for calibrating the neutron signal, and the uncertainty can also be directly obtained by calculating the uncertainty by adopting an uncertainty evaluation algorithm; the uncertainty of the neutron signal in the typical state is constructed equivalently by constructing a standard look-up table or a fitting curve, and then the measured neutron signal is calibrated by adopting the standard sample, wherein the standard neutron signal calibrated by the uncertainty required by the standard look-up table or the fitting curve and the measured neutron signal are measured by adopting the same transmission line; this reduces errors, and the real-time construction of the standard look-up table or fitted curve advantageously eliminates environmental effects, which are consistent with the measured environment, and the two data remain consistent with the environment.
Preferably, the method for determining uncertainty of the measured neutron signal by constructing the standard look-up table comprises the following steps:
s3, the specific process of actually measured uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and calculating the uncertainty of the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, forming a standard uncertainty query table according to the uncertainty obtained in the S31;
s33, sampling the neutron signal sequence I with the frequency of f1f1… neutron signal sequence I with sampling frequency fnfnSubstituting or interpolating into a standard uncertainty query table to obtain the table look-up uncertainty, and recording the table look-up uncertainty as the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies.
Preferably, the method for determining uncertainty of the actually measured neutron signal by constructing the standard uncertainty curve comprises the following steps:
s3, the specific process of actually measured uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and calculating the uncertainty of the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, fitting according to the uncertainty obtained in the S31 to form a standard uncertainty curve;
s33, sampling the neutron signal sequence I with the frequency of f1f1… neutron signal sequence I with sampling frequency fnfnSubstituted or interpolated in the uncertainty of the standardAnd obtaining fitting uncertainty in the degree curve, wherein the fitting uncertainty is recorded as the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies.
In the step S31, uncertainty calculation is performed
Figure BDA0002984837520000051
The calculation is carried out in such a way that,
Figure BDA0002984837520000052
comprises the following steps: 1 neutron signal measurement xiUncertainty of (d); under a certain typical state, obtaining the measured value x of a single standard neutron signal, and obtaining Y measured values x of the neutron signal under repeated condition measurementi(i＝1,2,…,Y)。
Preferably, the first and second liquid crystal materials are,
s2, the specific process of the average method down-sampling treatment is as follows:
neutron signal sequence I by using adjacent dot data arithmetic mean method or weighted mean methodfmaxWhen the down-sampling processing is carried out, the arithmetic mean or the weighted mean is calculated by the neutron signal data measured values of a adjacent point positions, so that the neutron signal data measurement after the down-sampling can be obtained; where a is pre-down-sampling frequency/post-down-sampling frequency.
The essence of down-sampling is to obtain new data sets after reducing sampling points, and reconstruct a plurality of new data sets under the same maximum frequency sampling environment. For example, assuming that the maximum sampling frequency is 1000Hz, assuming that the downsampled frequency of 500Hz is the target, the sampling points are reduced by 1 time, and therefore a is set to 2, wherein 1000 sampling points obtained by the maximum sampling frequency are sequentially ordered to form a sequence, the sequence after downsampling processing includes 1 st sampling point and 2 nd sampling point, which are averaged and then merged into 1 new downsampled sampling point, and so on to obtain 500 sampling point data, and the 500 sampling point data form a new sequence.
Preferably, the uncertain method for determining the measured neutron signal by direct synthesis is as follows:
s2, the specific process of the average method down-sampling treatment is as follows:
neutron signal sequence I by using adjacent dot data arithmetic mean method or weighted mean methodfmaxWhen the down-sampling processing is carried out, the arithmetic mean or the weighted mean is calculated by the neutron signal data measured values of a adjacent point positions, so that the neutron signal data measurement after the down-sampling can be obtained; wherein a is pre-down-sampling frequency/post-down-sampling frequency;
s3, the specific process of the measured uncertainty evaluation is as follows:
obtaining a sampling frequency f by an uncertainty synthesis formula1Neutron signal sequence If1… neutron signal sequence I with sampling frequency fnfnSynthetic uncertainty of (a); the synthetic uncertainty is recorded as the measured uncertainty of the neutron signal sequence obtained at different sampling frequencies.
The formula of the synthetic uncertainty is as follows:
Figure BDA0002984837520000061
Figure BDA0002984837520000062
a composite uncertainty for a down-sampled neutron signal data measurement; pl is the weight factor of the weighted average;
Figure BDA0002984837520000063
Figure BDA0002984837520000064
comprises the following steps: the uncertainty of a neutron signal data measured value after down-sampling; x is the number oflFor the single neutron signal data measured value after down-sampling, k neutron signal measured values x with the sampling point number of k corresponding to the frequency after down-sampling are obtained after down-samplingl(l＝1,2,…,k)。
Specifically, fmax is 1000Hz, f1 is 800Hz, and fn is 100Hz, which represents only one example.
The process of neutron monitoring when the reactor is introduced with reactivity is as follows:
after the reactor is in a critical steady state for a certain time, introducing reactivity by adjusting the rod position of a control rod, and simultaneously measuring a neutron signal in the adjusting process by adopting a neutron detector; in the measuring process, an amplifier is adopted to amplify a measuring signal of the neutron detector, and the measuring signal is converted into a voltage signal and then transmitted to a data acquisition card with the maximum sampling frequency.
S5, the optimal judgment standard is as follows:
and (4) carrying out average value or weighted average value calculation on the corrected and synthesized uncertainty of the neutron signal sequences obtained at different sampling frequencies after S4 correction, and selecting 1 group of neutron signal sequences with the lowest calculation result value as the optimal neutron signal sequence.
S4, the specific correction process is as follows:
introducing a correction factor C (t) to a neutron signal sequence I with the sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnNeutron signal data measured value I at middle t momentm,i(t) correcting to obtain corrected neutron signal data measured value Ii(t)＝Im,i(t) C (t); the correction factor C (t) is the correction factor of the signal at the sampling moment t;
uncertainty u [ C (t) ] incorporating correction factors]For neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnSynthesizing the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal data measured value;
Figure BDA0002984837520000071
u[Im,i(t)]is Im,i(t) measured uncertainty.
The invention has the following effects: aiming at the influence of factors such as neutron signal statistical fluctuation, high-voltage ripples, electromagnetic interference and the like in the reactivity measurement process, the nuclear reactor reactivity measurement method capable of reducing the influence is established. By adopting a mathematical algorithm based on uncertainty analysis, the uncertainty of neutron signal measurement is reduced, the uncertainty introduced by a correction factor is reduced, and the reactivity measurement efficiency and accuracy are improved.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic flow diagram of a standard uncertainty reference process.
FIG. 2 is a schematic flow chart of the evaluation using synthesis uncertainty.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
As shown in fig. 1 and 2:
a method of reactivity measurement based on a modified signal uncertainty analysis, comprising the steps of:
s1, maximum frequency sampling processing: when the reactor is introduced with reactivity, neutron signal monitoring is carried out, and neutron signal sampling is carried out by adopting a data acquisition card with the maximum sampling frequency; a group of neutron signal sequences I with the maximum sampling frequency fmax output by the data acquisition cardfmax(ii) a The neutron signal sequence IfmaxIncludes I neutron signal data measured values, I1、I2、…Ii(ii) a i represents a sampling point, and the size of i is determined according to fmax;
s2, average down-sampling: using arithmetic mean method or weighted mean method of adjacent dot data to neutron signal sequence IfmaxPerforming down-sampling processing for n times to obtain a neutron signal sequence I with the sampling frequency of f1f1… neutron signal sequence I with sampling frequency fnfn(ii) a f1, fn are both smaller than fmax;
s3, evaluating the uncertainty of the actual measurement: for neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnEvaluating uncertainty of actual measurement to obtain different samplesActual measurement uncertainty of the neutron signal sequence at frequency;
s4, correction: neutron signal sequence I with correction factor pair sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnCorrecting to obtain a corrected neutron signal sequence; correction factor-introduced uncertainty versus neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnCarrying out uncertainty synthesis on the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal sequence;
s5, optimal judgment: according to the neutron signal sequence I with the modified sampling frequency f1f1Corrected composite uncertainty … neutron signal sequence I with sampling frequency fnfnThe corrected synthesis uncertainty is subjected to optimal judgment, a corrected signal data set with the optimal uncertainty is selected from the corrected synthesis uncertainty, and a neutron signal sequence corresponding to the optimal uncertainty is recorded as an optimal neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the optimal neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the optimal neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
The invention firstly adopts the maximum frequency to sample, thus enough data points can be obtained by one-time sampling, then the average method is adopted to carry out down-sampling processing to form different data groups, thus the data groups with different frequencies under the same sampling environment are directly obtained, the external environments of the data groups are the same, the traditional method is repeated sampling times, and in each sampling, because the influences of factors such as neutron signal statistical fluctuation, high-voltage ripple, electromagnetic interference and the like in the measurement process of different times are different, the data sampled in each time are not finished under the same environment, and the final reactive error is increased.
The actual measurement uncertainty evaluation refers to the uncertainty evaluation of the neutron signal obtained by the reactor in the actual environment, so that the uncertainty of the actual measurement neutron signal is obtained. The actual measurement uncertainty evaluation process is carried out relative to the actual measurement neutron signal obtained by the average method down-sampling processing, specifically, the uncertainty of the neutron signal in a typical state can be adopted for calibrating the neutron signal, and the uncertainty can also be directly obtained by calculating the neutron signal by adopting an uncertainty synthesis algorithm; the uncertainty of the neutron signal in the typical state is constructed equivalently by constructing a standard look-up table or a fitting curve, and then the measured neutron signal is calibrated by adopting the standard sample, wherein the standard neutron signal calibrated by the uncertainty required by the standard look-up table or the fitting curve and the measured neutron signal are measured by adopting the same transmission line; this reduces errors, and the real-time construction of the standard look-up table or fitted curve advantageously eliminates environmental effects, which are consistent with the measured environment, and the two data remain consistent with the environment.
Example 2
As shown in fig. 1 and 2:
on the basis of the above embodiment 1, the method for determining uncertainty of an actually measured neutron signal by constructing a standard look-up table includes:
s3, the specific process of actually measured uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and calculating the uncertainty of the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, forming a standard uncertainty query table according to the uncertainty obtained in the S31;
s33, sampling the neutron signal sequence I with the frequency of f1f1… neutron signal sequence I with sampling frequency fnfnSubstituting or interpolating into a standard uncertainty query table to obtain the table look-up uncertainty, and recording the table look-up uncertainty as the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies.
Example 3
As shown in fig. 1 and 2:
on the basis of the above embodiment 1, the method for determining uncertainty of an actually measured neutron signal by constructing a standard uncertainty curve is as follows:
s3, the specific process of actually measured uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and calculating the uncertainty of the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, fitting according to the uncertainty obtained in the S31 to form a standard uncertainty curve;
s33, sampling the neutron signal sequence I with the frequency of f1f1… neutron signal sequence I with sampling frequency fnfnAnd substituting or interpolating the measured value into a standard uncertainty curve to obtain fitting uncertainty, and recording the fitting uncertainty as the measured uncertainty of the neutron signal sequence under different sampling frequencies.
In the step S31, uncertainty calculation is performed
Figure BDA0002984837520000111
The calculation is carried out in such a way that,
Figure BDA0002984837520000112
comprises the following steps: 1 neutron signal measurement xiUncertainty of (d); under a certain typical state, obtaining the measured value x of a single standard neutron signal, and obtaining Y measured values x of the neutron signal under repeated condition measurementi(i＝1,2,…,Y)。
Preferably, the first and second liquid crystal materials are,
s2, the specific process of the average method down-sampling treatment is as follows:
neutron signal sequence I by using adjacent dot data arithmetic mean method or weighted mean methodfmaxWhen the down-sampling processing is carried out, the arithmetic mean or the weighted mean is calculated by the neutron signal data measured values of a adjacent point positions, so that the neutron signal data measurement after the down-sampling can be obtained; where a is pre-down-sampling frequency/post-down-sampling frequency.
The essence of down-sampling is to obtain new data sets after reducing sampling points, and reconstruct a plurality of new data sets under the same maximum frequency sampling environment. For example, assuming that the maximum sampling frequency is 1000Hz, assuming that the downsampled frequency of 500Hz is the target, the sampling points are reduced by 1 time, and therefore a is set to 2, wherein 1000 sampling points obtained by the maximum sampling frequency are sequentially ordered to form a sequence, the sequence after downsampling processing includes 1 st sampling point and 2 nd sampling point, which are averaged and then merged into 1 new downsampled sampling point, and so on to obtain 500 sampling point data, and the 500 sampling point data form a new sequence.
Example 4
Preferably, the uncertain method for determining the measured neutron signal by direct synthesis is as follows:
as shown in fig. 1 and 2:
based on the foregoing embodiment 1, the specific process of S2 and the average down-sampling process includes:
neutron signal sequence I by using adjacent dot data arithmetic mean method or weighted mean methodfmaxWhen the down-sampling processing is carried out, the arithmetic mean or the weighted mean is calculated by the neutron signal data measured values of a adjacent point positions, so that the neutron signal data measurement after the down-sampling can be obtained; wherein a is pre-down-sampling frequency/post-down-sampling frequency;
s3, the specific process of the measured uncertainty evaluation is as follows:
obtaining a sampling frequency f by an uncertainty synthesis formula1Neutron signal sequence If1… neutron signal sequence I with sampling frequency fnfnSynthetic uncertainty of (a); the synthetic uncertainty is recorded as the measured uncertainty of the neutron signal sequence obtained at different sampling frequencies.
The formula of the synthetic uncertainty is as follows:
Figure BDA0002984837520000121
Figure BDA0002984837520000122
a composite uncertainty for a down-sampled neutron signal data measurement; p is a radical oflBeing weighted averagesA weight factor;
Figure BDA0002984837520000123
Figure BDA0002984837520000124
comprises the following steps: the uncertainty of a neutron signal data measured value after down-sampling; x is the number oflFor the single neutron signal data measured value after down-sampling, k neutron signal measured values x with the sampling point number of k corresponding to the frequency after down-sampling are obtained after down-samplingl(l＝1,2,…,k)。
Specifically, fmax is 1000Hz, f1 is 800Hz, and fn is 100Hz, which represents only one example.
The process of neutron monitoring when the reactor is introduced with reactivity is as follows:
after the reactor is in a critical steady state for a certain time, introducing reactivity by adjusting the rod position of a control rod, and simultaneously measuring a neutron signal in the adjusting process by adopting a neutron detector; in the measuring process, an amplifier is adopted to amplify a measuring signal of the neutron detector, and the measuring signal is converted into a voltage signal and then transmitted to a data acquisition card with the maximum sampling frequency.
S5, the optimal judgment standard is as follows:
and (4) carrying out average value or weighted average value calculation on the corrected and synthesized uncertainty of the neutron signal sequences obtained at different sampling frequencies after S4 correction, and selecting 1 group of neutron signal sequences with the lowest calculation result value as the optimal neutron signal sequence.
In order to reduce the amount of subsequent reactivity calculation, the invention directly determines a data set with optimal uncertainty as the basis of subsequent measurement calculation.
For example: the neutron signal sequences under different sampling frequencies respectively have: neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnNeutron signal sequence If1The method comprises the following sampling points: i isf1，1、.....、If1，xThe corresponding corrected composite uncertainty includes: u. off1，1、.....、uf1，xWherein the sub-signal sequence If1Comprises the following steps: (u)f1，1+....+uf1，x) X or q uf1，1+....+q*xuf1，xCalculating by the aid of the/X, and recording the calculation result value as uf1In the same way, wherein the sub-signal sequence IfnComprises the following steps: the calculation result value is recorded as ufn(ii) a Optimal decision rule refers to comparison uf1.....ufnThe size of (d); and selecting the 1 group of neutron signal sequences with the lowest value as the optimal. And X is a sampling point in the corresponding group of neutron signal sequences. q is a weight.
S4, the specific correction process is as follows:
introducing a correction factor C (t) to a neutron signal sequence I with the sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnNeutron signal data measured value I at middle t momentm,i(t) correcting to obtain corrected neutron signal data measured value Ii(t)＝Im,i(t) C (t); the correction factor C (t) is the correction factor of the signal at the sampling moment t;
uncertainty u [ C (t) ] incorporating correction factors]For neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnSynthesizing the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal data measured value;
Figure BDA0002984837520000131
u[Im,i(t)]is Im,i(t) measured uncertainty.
For reactivity, a final reactivity measurement result can be obtained by combining the corrected reactivity measurement neutron signal obtained by the method and the uncertainty thereof with a reactivity measurement formula; and based on standard uncertainty synthesis algorithm or other approximate uncertainty synthesis algorithm specified by the laws and regulations, performing uncertainty synthesis to obtain the uncertainty of the method.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.

Claims (10)

1. A method for reactivity measurement based on corrected signal uncertainty analysis, comprising the steps of:
s1, maximum frequency sampling processing: when the reactor is introduced with reactivity, neutron signal monitoring is carried out, and neutron signal sampling is carried out by adopting a data acquisition card with the maximum sampling frequency; a group of neutron signal sequences I with the maximum sampling frequency fmax output by the data acquisition cardfmax(ii) a The neutron signal sequence IfmaxIncludes I neutron signal data measured values, I1、I2、…Ii(ii) a i represents a sampling point, and the size of i is determined according to fmax; s2, average down-sampling: using arithmetic mean method or weighted mean method of adjacent dot data to neutron signal sequence IfmaxPerforming down-sampling processing for n times to obtain a neutron signal sequence I with the sampling frequency of f1f1… neutron signal sequence I with sampling frequency fnfn(ii) a f1, fn are both smaller than fmax;
s3, evaluating the uncertainty of the actual measurement: for neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnCarrying out actual measurement uncertainty evaluation to obtain actual measurement uncertainty of the neutron signal sequence under different sampling frequencies;
s4, correction: neutron signal sequence I with correction factor pair sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnCorrecting to obtain a corrected neutron signal sequence; correction factor-introduced uncertainty versus neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnCarrying out uncertainty synthesis on the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal sequence;
s5, optimal judgment: according to the neutron signal sequence I with the modified sampling frequency f1f1Is modified byNeutron signal sequence I with sampling frequency fn of uncertainty …fnThe corrected synthesis uncertainty is subjected to optimal judgment, a corrected signal data set with the optimal uncertainty is selected from the corrected synthesis uncertainty, and a neutron signal sequence corresponding to the optimal uncertainty is recorded as an optimal neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the optimal neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the optimal neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
2. The method of claim 1, wherein the step of determining the reactivity of the sample includes determining the degree of uncertainty of the signal,
s3, the specific process of actually measured uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and calculating the uncertainty of the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, forming a standard uncertainty query table according to the uncertainty obtained in the S31;
s33, sampling the neutron signal sequence I with the frequency of f1f1… neutron signal sequence I with sampling frequency fnfnSubstituting or interpolating into a standard uncertainty query table to obtain the table look-up uncertainty, and recording the table look-up uncertainty as the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies.
3. The method of claim 1, wherein the step of determining the reactivity of the sample includes determining the degree of uncertainty of the signal,
s3, the specific process of actually measured uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and calculating the uncertainty of the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, fitting according to the uncertainty obtained in the S31 to form a standard uncertainty curve;
s33, sampling the neutron signal sequence I with the frequency of f1f1… neutron signal sequence I with sampling frequency fnfnAnd substituting or interpolating the measured value into a standard uncertainty curve to obtain fitting uncertainty, and recording the table look-up uncertainty as the measured uncertainty of the neutron signal sequence under different sampling frequencies.
4. A method of reactivity measurement based on corrected signal uncertainty analysis according to claim 2 or 3,
in S31, uncertainty calculation is performed
Figure FDA0002984837510000031
The calculation is carried out in such a way that,
Figure FDA0002984837510000034
comprises the following steps: 1 neutron signal measurement xiUncertainty of (d); under a certain typical state, obtaining the measured value x of a single standard neutron signal, and obtaining Y measured values x of the neutron signal under repeated condition measurementi(i＝1,2,…,Y)。
5. A method of reactivity measurement based on corrected signal uncertainty analysis according to claim 2 or 3,
s2, the specific process of the average method down-sampling treatment is as follows:
neutron signal sequence I by using adjacent dot data arithmetic mean method or weighted mean methodfmaxWhen the down-sampling processing is carried out, the arithmetic mean or the weighted mean is calculated by the neutron signal data measured values of a adjacent point positions, so that the neutron signal data measurement after the down-sampling can be obtained; where a is pre-down-sampling frequency/post-down-sampling frequency.
6. The method of claim 1, wherein the step of determining the reactivity of the sample includes determining the degree of uncertainty of the signal,
s2, the specific process of the average method down-sampling treatment is as follows:
neutron signal sequence I by using adjacent dot data arithmetic mean method or weighted mean methodfmaxWhen the down-sampling processing is carried out, the arithmetic mean or the weighted mean is calculated by the neutron signal data measured values of a adjacent point positions, so that the neutron signal data measurement after the down-sampling can be obtained; wherein a is pre-down-sampling frequency/post-down-sampling frequency;
s3, the specific process of the measured uncertainty evaluation is as follows:
obtaining a sampling frequency f by an uncertainty synthesis formula1Neutron signal sequence If1… neutron signal sequence I with sampling frequency fnfnSynthetic uncertainty of (a); and recording the synthesis uncertainty as the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies.
The formula of the synthetic uncertainty is as follows:
Figure FDA0002984837510000032
Figure FDA0002984837510000033
a composite uncertainty for a down-sampled neutron signal data measurement; p is a radical oflA weight factor that is a weighted average;
Figure FDA0002984837510000041
Figure FDA0002984837510000042
comprises the following steps: the uncertainty of a neutron signal data measured value after down-sampling; x is the number oflFor the single neutron signal data measured value after down-sampling, k neutron signals with the sampling point number of k corresponding to the frequency after down-sampling are obtained after down-samplingMeasured value xl(l＝1,2,…,k)。
7. The method of claim 1, wherein the step of determining the reactivity of the sample includes determining the degree of uncertainty of the signal,
fmax is 1000Hz, f1 is 800Hz, and fn is 100 Hz.
8. The method of claim 1, wherein the step of determining the reactivity of the sample includes determining the degree of uncertainty of the signal,
the process of neutron monitoring when the reactor is introduced with reactivity is as follows:
after the reactor is in a critical steady state for a certain time, introducing reactivity by adjusting the rod position of a control rod, and simultaneously measuring a neutron signal in the adjusting process by adopting a neutron detector; in the measuring process, an amplifier is adopted to amplify a measuring signal of the neutron detector, and the measuring signal is converted into a voltage signal and then transmitted to a data acquisition card with the maximum sampling frequency.
9. The method of claim 1, wherein the step of determining the reactivity of the sample includes determining the degree of uncertainty of the signal,
s5, the optimal judgment standard is as follows:
and (4) carrying out average value or weighted average value calculation on the corrected and synthesized uncertainty of the neutron signal sequences obtained at different sampling frequencies after S4 correction, and selecting 1 group of neutron signal sequences with the lowest calculation result value as the optimal neutron signal sequence.
10. The method of claim 1, wherein the step of determining the reactivity of the sample includes determining the degree of uncertainty of the signal,
s4, the specific correction process is as follows:
introducing a correction factor C (t) to a neutron signal sequence I with the sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnNeutron signal data measured value I at middle t momentm,i(t) correcting to obtain corrected neutron signal data measured value Ii(t)＝Im,i(t) C (t); the correction factor C (t) is the correction factor of the signal at the sampling moment t;
uncertainty u [ C (t) ] incorporating correction factors]For neutron signal sequence I with sampling frequency f1f1… neutron signal sequence I with sampling frequency fnfnSynthesizing the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal data measured value;
Figure FDA0002984837510000051
u[Im,i(t)]is Im,i(t) measured uncertainty.
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