CN113192659A - Nuclear reactor reactivity measurement method based on average sampling of primary neutron signals - Google Patents
Nuclear reactor reactivity measurement method based on average sampling of primary neutron signals Download PDFInfo
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Abstract
The invention discloses a nuclear reactor reactivity measuring method based on average sampling of original neutron signals, 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 f1f1… neutron signal sequence I with sampling frequency fnfn(ii) a f1, fn are both smaller than fmax; s3, evaluating the uncertainty of actual measurement; s4, optimal judgment; s5, correcting to obtain the uncertainty of the corrected neutron signal sequence; s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the corrected neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the corrected neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
Description
Technical Field
The invention relates to the field of nuclear reactor reactivity measurement and processing, in particular to a nuclear reactor reactivity measurement method based on average sampling of original neutron signals.
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 the research of a reactivity measurement method based on uncertainty analysis or reports of related patent technologies in China. Therefore, it is necessary to master an autonomous reactivity measurement method based on uncertainty analysis for the difference between the autonomous core and the foreign core, and to provide the capability of efficient and accurate measurement of the reactor core reactivity.
Disclosure of Invention
The invention aims to provide a nuclear reactor reactivity measuring method based on average sampling of original neutron signals, which can reduce the influence of factors such as neutron signal statistical fluctuation, high-voltage ripples, electromagnetic interference and the like in the reactivity measuring process, make up the defects of the existing measuring 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:
the nuclear reactor reactivity measuring method based on average sampling of primary neutron signals comprises the following steps:
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 FangjiangSampling treatment: 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 the uncertainty of the neutron signal sequence under different sampling frequencies;
s4, optimal judgment: according to a neutron signal sequence I with the sampling frequency of f1f1With an uncertainty … of the neutron signal sequence I with a sampling frequency fnfnCarrying out optimal judgment on the uncertainty, selecting the optimal uncertainty from the uncertainty, and recording a neutron signal sequence corresponding to the optimal uncertainty as an optimal neutron signal sequence;
s5, correction: introducing a correction factor to correct the optimal neutron signal sequence to obtain a corrected neutron signal sequence; synthesizing the optimal uncertainty by introducing the uncertainty of the correction factor to obtain the uncertainty of the corrected neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the corrected neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the corrected 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 neutron signal which is directly obtained, and simultaneously constructs standard uncertainty or adopts a synthesis method to process the uncertainty of the neutron signal after down-sampling, thereby optimizing and reconstructing the actually measured data to reduce the uncertainty thereof, and 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, neutron signals are firstly subjected to down-sampling processing, the influence of uncertainty caused by a measuring environment is reduced, and then the systematic error elimination of the point stack measurement model is realized by adopting space effect correction and subsequent reactivity calculation.
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 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.
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 fnfnAnd substituting or interpolating the neutron signal sequence into a standard uncertainty query table to obtain the 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 fnfnAnd substituting or interpolating the neutron signal sequence into a standard uncertainty curve to obtain the uncertainty of the neutron signal sequence under different sampling frequencies.
In the step S31, uncertainty calculation is performed
The calculation is carried out in such a way that,
Preferably, the first and second liquid crystal materials are,
s2, the specific process of the average method down-sampling treatment is as follows:
when the original data is down-sampled by an adjacent point data arithmetic mean method or a weighted mean method, obtaining a down-sampled neutron signal data measurement by calculating the arithmetic mean or the weighted mean of the neutron signal data measurement values of a adjacent point bits; 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:
when the original data is down-sampled by an adjacent point data arithmetic mean method or a weighted mean method, obtaining a down-sampled neutron signal data measurement by calculating the arithmetic mean or the weighted mean of the neutron signal data measurement values of a adjacent point bits; 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 formula of the synthetic uncertainty is as follows:
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.
S4, the optimal judgment standard is as follows:
and (4) after the uncertainty of the actual measurement is evaluated at S3, calculating the average value or weighted average value of the uncertainties of the obtained neutron signal sequences under different sampling frequencies, and selecting 1 group of neutron signal sequences with the lowest value as the optimal.
In order to reduce the amount of correction calculation and the amount of subsequent reactivity calculation, the invention directly determines a data set with optimal uncertainty as the basis of subsequent measurement calculation.
S5, the specific correction process is as follows:
introducing a correction factor C (t) to neutron signal data measured value I at time t in the optimal neutron signal sequencem,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]Synthesizing the optimal uncertainty to obtain the uncertainty of the neutron signal data measured value after correction;
u[Im,i(t)]is Im,i(t) 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:
the nuclear reactor reactivity measuring method based on average sampling of primary neutron signals comprises the following steps:
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 the uncertainty of the neutron signal sequence under different sampling frequencies;
s4, optimal judgment: according to a neutron signal sequence I with the sampling frequency of f1f1With an uncertainty … of the neutron signal sequence I with a sampling frequency fnfnCarrying out optimal judgment on the uncertainty, selecting the optimal uncertainty from the uncertainty, and recording a neutron signal sequence corresponding to the optimal uncertainty as an optimal neutron signal sequence;
s5, correction: introducing a correction factor to correct the optimal neutron signal sequence to obtain a corrected neutron signal sequence; synthesizing the optimal uncertainty by introducing the uncertainty of the correction factor to obtain the uncertainty of the corrected neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the corrected neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the corrected 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 fnfnAnd substituting or interpolating the neutron signal sequence into a standard uncertainty query table to obtain the 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 fnfnSubstituting or interpolating in standard uncertainty curve to obtain neutron signal under different sampling frequencyUncertainty of number sequence.
In the step S31, uncertainty calculation is performed
The calculation is carried out in such a way that,
Preferably, the first and second liquid crystal materials are,
s2, the specific process of the average method down-sampling treatment is as follows:
when the original data is down-sampled by an adjacent point data arithmetic mean method or a weighted mean method, obtaining a down-sampled neutron signal data measurement by calculating the arithmetic mean or the weighted mean of the neutron signal data measurement values of a adjacent point bits; 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:
example 4
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:
when the original data is down-sampled by an adjacent point data arithmetic mean method or a weighted mean method, obtaining a down-sampled neutron signal data measurement by calculating the arithmetic mean or the weighted mean of the neutron signal data measurement values of a adjacent point bits; 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 formula of the synthetic uncertainty is as follows:
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.
S4, the optimal judgment standard is as follows:
and (4) after the uncertainty of the actual measurement is evaluated at S3, calculating the average value or weighted average value of the uncertainties of the obtained neutron signal sequences under different sampling frequencies, and selecting 1 group of neutron signal sequences with the lowest value as the optimal.
In order to reduce the amount of correction calculation and 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 uncertainty includes: u. off1，1、.....、uf1，xWherein the sub-signal sequence If1The uncertainty of (a) is: u. off1，1+....+uf1，xX or q uf1，1+....+q*xuf1，xX, result is uf1Wherein the sub-signal sequence IfnThe uncertainty of (a) is: u. offn，1+....+ufn，yY or q ufn，1+....+q*xufn，yY, result is ufnThe optimum judgment means comparison uf1.....ufnThe size of (d); and selecting the 1 group of neutron signal sequences with the lowest value as the optimal. And X and y are sampling points in the corresponding group of neutron signal sequences respectively. q is a weight.
S5, the specific correction process is as follows:
introducing a correction factor C (t) to neutron signal data measured value I at time t in the optimal neutron signal sequencem,i(t) correcting to obtain corrected neutron signal data measured value Ii(t)＝Im,i(t) C (t); the correction factor C (t) is t sampling time signalA correction factor for the number;
uncertainty u [ C (t) ] incorporating correction factors]Synthesizing the optimal uncertainty to obtain the uncertainty of the neutron signal data measured value after correction;
u[Im,i(t)]is Im,i(t) 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. The nuclear reactor reactivity measurement method based on average sampling of primary neutron signals is characterized by comprising the following 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 IfmaxDown-sampling n timesProcessing to obtain a neutron signal sequence I with the sampling 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 the uncertainty of the neutron signal sequence under different sampling frequencies;
s4, optimal judgment: according to a neutron signal sequence I with the sampling frequency of f1f1With an uncertainty … of the neutron signal sequence I with a sampling frequency fnfnCarrying out optimal judgment on the uncertainty, selecting the optimal uncertainty from the uncertainty, and recording a neutron signal sequence corresponding to the optimal uncertainty as an optimal neutron signal sequence;
s5, correction: introducing a correction factor to correct the optimal neutron signal sequence to obtain a corrected neutron signal sequence; synthesizing the optimal uncertainty by introducing the uncertainty of the correction factor to obtain the uncertainty of the corrected neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the corrected neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the corrected neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
2. The method of nuclear reactor reactivity measurement based on in-situ neutron signal average sampling of claim 1,
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 with the frequency of f1Sequence If1… neutron signal sequence I with sampling frequency fnfnAnd substituting or interpolating the neutron signal sequence into a standard uncertainty query table to obtain the uncertainty of the neutron signal sequence under different sampling frequencies.
3. The method of nuclear reactor reactivity measurement based on in-situ neutron signal average sampling of claim 1,
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 neutron signal sequence into a standard uncertainty curve to obtain the uncertainty of the neutron signal sequence under different sampling frequencies.
4. The method of measuring reactivity of a nuclear reactor based on mean sampling of raw neutron signals according to claim 2 or 3,
in S31, uncertainty calculation is performed
The calculation is carried out in such a way that,
5. The method of measuring reactivity of a nuclear reactor based on mean sampling of raw neutron signals according to claim 2 or 3,
s2, the specific process of the average method down-sampling treatment is as follows:
when the original data is down-sampled by an adjacent point data arithmetic mean method or a weighted mean method, obtaining a down-sampled neutron signal data measurement by calculating the arithmetic mean or the weighted mean of the neutron signal data measurement values of a adjacent point bits; where a is pre-down-sampling frequency/post-down-sampling frequency.
6. The method of nuclear reactor reactivity measurement based on in-situ neutron signal average sampling of claim 1,
s2, the specific process of the average method down-sampling treatment is as follows:
when the original data is down-sampled by an adjacent point data arithmetic mean method or a weighted mean method, obtaining a down-sampled neutron signal data measurement by calculating the arithmetic mean or the weighted mean of the neutron signal data measurement values of a adjacent point bits; 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 formula of the synthetic uncertainty is as follows:
7. The method of nuclear reactor reactivity measurement based on in-situ neutron signal average sampling of claim 1,
fmax is 1000Hz, f1 is 800Hz, and fn is 100 Hz.
8. The method of nuclear reactor reactivity measurement based on in-situ neutron signal average sampling of claim 1,
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 nuclear reactor reactivity measurement based on in-situ neutron signal average sampling of claim 1,
s4, the optimal judgment standard is as follows:
and (4) after the uncertainty of the actual measurement is evaluated at S3, calculating the average value or weighted average value of the uncertainties of the obtained neutron signal sequences under different sampling frequencies, and selecting 1 group of neutron signal sequences with the lowest value as the optimal.
10. The method of nuclear reactor reactivity measurement based on in-situ neutron signal average sampling of claim 1,
s5, the specific correction process is as follows:
introducing a correction factor C (t) to neutron signal data measured value I at time t in the optimal neutron signal sequencem,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]Synthesizing the optimal uncertainty to obtain the uncertainty of the neutron signal data measured value after correction;
u[Im,i(t)]is Im,i(t) uncertainty.
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